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Studsv ik R ep or t

STUDSVIK/ES-95/10

ADVANC ED NUCLEAR REA CTO R TYPES

AN D TECHNOLOGIES

Part I R eactors fo r Power Prod u ctio n

Victor Ignat iev (Edi tor )

Olga Feinberg

A le x e i M o r o z o v

Lennar t Devel l

S t u d s v i k E c o S a f e

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S T U D S V K ECO & SAFETY A B ST U D SV K /E S-95/10

1995-02-13

Victor Ignatiev (Editor)

Olga F einberg

Ak xei Morozov

Lennart D eve ll

ADVANCED NUCLEAR REACTOR TYPES AND TECHNOLOGIES

Part I Reactors for Power Production

Abstract

The docum ent is a comprehen sive world-wide catalogue of concepts and designs of advanced fission

reactor types and fuel cyc le tech nolog ies. Tw o parts have been prepared:

Pan I

Pann

Reactors for Power Production

Heating and Other Reactor App lications

Pa n m , which will cov er advanced waste management technology, reprocessing and disposal for

different nuclear fission options is planned for compilation during 1995.

This catalogue was prepared according to a special format which briefly presents the project title,

technical approach, develop men t status, application of the technolog y, reactor type, power output,

and organization which deve loped these design s.

Parts I and II cover water cooled reactors, liquid metal fast reactors, gas-coo led reactors and m olten

salt reactors. Subcritical accelerator-driven systems are also considered. Various reactor applications

as pow er produ ction, heat generation, ship propulsion, space pow er sources and transmutation of such

waste are included.

Each project is described within a few pages with the main features of an actual design using a table

with m ain technical data and figure as well a s references for additional information. Each chapter

starts with an introduction w hich briefly describes m ain trends and approaches in this field.

Explanations of terms and abbreviations are provided in a glossary.

ISBN 91-7010-258-9

Reviewed by Approved by

© Studsvik Eco

&

Safety AB, Sweden 1995

y ^

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STUDSVIK ECO & SAFETY AB STUDSVK/ES-95/10

1995-02-13

Preface

For several years Studsvik AB has had d r special task, rii«gn»>pH by dr.

Swedish Ministry of Industry and Commerce of surveying, analysing and

reporting on die development efforts and achievements abroad, concerning

advanced nuclear fission technology. Program management and most of die

task-

K

| E fr f n" " ^ M * i " **«» ̂ h ^ E F y

r ^fff^y

SmHwrilr Er a * S afety At t

The results are presented in an annual summary report as well as in topical

reports in Swedish. Contacts and collaboration widi colleagues abroad and

institut es »m l TMrareh « ^» niffrfifln t y y nf inipniianrii» in this wflfk In

recent

years,

do se contacts have been established between die Russian

Research Centre "Kurchatov Institute",

in

Moscow and Studsvik.

A s

a joint

project and

in

close co-operation

k

was decided to prepare

a

document

which briefly presented die plans, projects and achievements widiin die area

of advanced nuclear fission technology and dieir present status in various

countries.

The first and second parts o f this work concern nuclear fission reactors. The

last will examine front- and back-end of advanced nuclear fuel cycles. The

intention is to extend and also update die material compiled in new editions

when necessary. The first two parts were compiled by Victor Ignatiev

(Editor), Olga Feinberg and Alexei Morozov who are leading scientists of

die RRC "Kurchatov Institute" and

I

would like

to

tiiank diem all for their

efforts which made this report possible.

Acknowle ? * ;nts are due to Acad. N Ponomarev-Stepnoi and

Prof.

A C t -h sk if io m RRC "Kurchatov Institute" who supported the

work anc / »a

M L ,

V Krett, C Goetzman from IAEA, Stanislav Subbotine

from RC. ' S jrchatov Institute", Tor Pedersen of ABB Atom and Bengt

Pershagt r 01 providing necessary information and useful suggestions.

I would ? r» like to thank other contributors, among diem Elisabet

Appelf r for the typing and Monica Bowen-Schrire for correcting die

EngiisJ

I hope tV it the report will be of help to those who would like to obtain an

overview j f recent advancements in dus area

Lennart Devcll

Program Manager

Advanced Nuclear Technology

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STUDSV K ECO

&

SAFETY

AB

STUDSVK/ES-95/10

1995-02-13

Table of Contents

Introduction

Table of Descriptio» Fi

Part I Reactors for Power Production

Introduction

A Advanced Water-Cooted Reactors

AE Evolutionary desig ns for large pow er plants

AEO Introduction

AEP1 N4

AEP2 SizewellB

AEP3 KWU-Convoy

AEP4 APWRM/W

AEP5 System

80

Plus

AEP6 W E R 1 00 0 (V-392)

AEP7

EPR

AEB1 ABWR

AEB2 BWR90

AEH1 CANDU9

AT Evolutionary designs for medium power plants

ATO Introduction

ATP1 W E R 500/600

ATP2 AP-600

ATP3 MS-600

ATP4 AC-600

ATB1

ATB2

ATB3

ATB4

ATB5

ATG1

ATH1

SBWR

HSBWR

TOSBWR-900P

1000 Natural Circulation

BW R

SWR-1000

MKER-800

C A N D U 3

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S T U D S V K E C O & S A F E T Y A B

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AI Innovat ive des igns

AIO Int roduct ion

AIP1

P I U S - 6 0 0

AIP2

I SE R

A I P3 I S I S

AIP4 MAP

A I P 5 V P B E R - 6 0 0

A I P 6 SIR

A I P 7 S P W R

A I P 8 B - 5 0 0 S K D I

A D S S C L W R

B Liquid Metal Fast Reactors

BO Introduct ion

B T S 1 EFR

B T S 2 B N - 6 0 0 M

B I S 3 D E M O F B R

B I S4 SA FR

B I S5 A I .M R ( PR I SM )

B I L 1 B R E S T 3 0 0

B I L 2 L FB R

Gas-Cooled Reactors

CO

cii

CI2

CI3

CI4

Introduct ion

H T R - M o d u l

M H T G R

G T - M H R

H T G R M H D

D Molten Salt Reactors

DO

DI1

DI2

DI3

Introduct ion

USR

FUJl -Pu

M S R - N C

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STUDSVIK ECX) & SAFETY AB STUDSVIK/ES-95/10

1995-02-13

Part II Heating and Other Reactor Applications

Introduction

E

F

G

District-Heating Reactors

E0

El

E2

E3

E4

E5

E6

E7

E8

E9

E10

E l i

Introduction

AST-500M

MARS

SECURE-H

NHP-200

Thermos-100

NHR-200

RUTA

KNDHR

Slowpoke (SES-10)

Geyser

GHR-20

Decentralized Nuclear Heating

FO

Fl

F2

F3

F4

F5

F6

Introduction

CAREM-25

PAES-100

TRIGA Power System

ABV

ELENA

Compact HTGR Gas Turbine

Ship Reactors

GO

Gl

G2

G3

G4

Introduction

OK-900A

KLT-40

MRX

DRX

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S T U D S V K ECO & SAFETY A B ST U D SV K /E S-95/10

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Space Nuclear Reactors

10

II

12

13

14

15

16

TJ

18

19

Introduction

GPHS-RTG

ROMASHKA

T O P A Z - n

STAR-C

SP-100

ERATO

LMCPBR

R over / N E R V \

NPPS

Subcritical Accelerator-Driven W aste Transmutation

and Energy Generation Systems

JO

J l

J2

J3

J4

J5

J6

Introduction

Energy Amplifier

P H O E N K

J A E R I - T P C

ATW/ABC

AMSB

BBR

Appendix I List of Abbreviations and Glossary of Terms

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STUDSVIK ECO & SAFETY STUDSVK/ES-95/10

1995-02-13

Introduction

Since the beginn ing of the nuclear fission era, illustrated e.g. by the start-up of

the Fermi pile in 194 2, increasing efforts have b een m ade to develop and use

improved nuclear fission reactors. The civilian application of nuclear fission is

mainly pow er plants for electricity generation bu t, to a sma ll extent, also for

heat generation. There are reactors for research, radio-nuclide production,

medical treatment, water desalination, ship propulsion and space applications.

Also, som e different system s in critical or subcritical accelerator driven mode

have been studied for waste transmutation, weapon plutonium incineration,

tritium production etc .

Many ov erviews and proceedings from recent conferences are available which

describe the evolution of reactor design, tech nologies and applications in

various countries (som e of them are listed be low ). The present document is a

comprehensive collection of short descriptions o f new and advanced nuclear

reactor types and technologies on a global sca le (see Table 1). The purpose o f

the document is to provide an overview of present plans, projects, designs and

concepts o f future reactors. The m aterial has be en collected from the open

literature and from information from the vend ors.

The description of each d esign or conce pt follow s a standardized format (see

Table 2) to facilitate comparison. The current status of the technology is

described for each d esign as well as type of application, reactor type, power

output etc.

Compilation o f data began in J anuary 1994 and the present document has been

issued as the first edition which is intended to be updated. The authors would

therefore appreciate any comments, corrections and additions.

References

o

o

Status of Advanced T echnolog y and Design for W ater-Cooled

Reactors: Light W ater Reactors

Vienna, 1988, IAEA-TECDOC-479.

KABAN OV, L, KUPITZ, J and GOETZM ANN, C A

Advanced reactors: Safety and environmental considerations.

An international perspective on the next generation of nuclear

plants.

IAEA Bulletin, 2/1992.

GAGARINSKI, A Yu, IGNATIEV, V V , NOVIKOV, V M and

SUBBOTINE, S A

Advanced light-water reactor: Russian approaches

IAEA Bulletin, 2/1992.

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STUDSVIK ECO & SAFETY STUDSVIK/ES-95/10

1995-02-13

o

PERSHAGEN, B

Advanced li gh t W ater Reactors (in S wedish)

Studsvik AB , Sweden 1990 (STUDSV IK/NS-90/141).

PERSHAGEN, B

Ne w l ig h t W ater Reactors (in Swedish)

Studsvik AB , Sweden 1992 (STUDSV IK/NS-92/61).

Sm all and medium reactors. Status and pro spects. Report by an

expert group, OECD NEA, Paris, 199 1.

ALEK SEEV, P N, IGNATTEV, V V , SUBBO T1NE, S A e a

Reactor plant designs with die enhanced safety: ana lysis of die

concept (in R ussian)

Energoatemizdat, 1993.

PORSBERG, C W and REICH, W J

W orld-wide Advanced Nuclear Power Reactors with Passive and

Inherent Safety; W hat, W hy, How, and W ho.

Report ORNL/TM-11907, Sept, 1991.

A N GE L O. JA

Space nuclear power, 198S, Orbit book com pany, U SA .

AN S Top ical Meeting on Safety of Ne xt Generation P ower

Reactors

Seattle, May 1988.

IAEA W orkshop on the Safety of N uclear Installations: Future

Directions

Chicago, August 1989.

IAEA Technical Committee M eeting on Technical and Eco nom ic

Aspects of High Converters

Niimberg, March 1990.

ENS/ANS-Foratom ENC90 Conference

Lyon, September 1990.

ENS TOPNUX'93 International ENS TOPical Meeting Towaros

the Ne xt Generation o f L ight W ater Reactors.

The Hague 25 - 28 April, 1993.

Global '93 - International Conference and Technology Exhibition

on Future Nuclear Systems: Emerging Fuel C ycles and W aste

Disposal Options.

September 12 -17 ,1 99 3 ,, Seattle, W ashington.

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STUDSVIK ECO & SAFETY

ST U D SV K/ E S-95 / 10

1995-02-13

o

7th International Conference on Emerging Nuclear Energy

Systems (ICENES '93).

September 20 - 24 ,1 99 3, M akuhari, Chiba, Japan.

Advanced pow er system s - d esign technology and

strategies for their dep loym ent

18-22 October 1993. Seoul Rubublk of Korea.

AR S "94 International Topical M eeting on A dvanced Reactors

Safety.

17 - 21 April 1 994 . Pittsburg. USA-

Overv iew o f ph ysics aspects of D ifferent Transmutation Concepts.

1 9 9 4 , OEC D, Report NEA /NSC/DO C(94 )11.

Developing T echnology to Reduce R adioactive W aste M ay Take

Decad es and Be Costly.

1 9 9 3 , December. USA , Report GAO /RCED-94-16.

AIP Conference Proceedings 324 .

1 9 9 5 ,

January 8-12 , US A, NM . Albuquerque.

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ECO &

SAFETY

STUDSVIK/ES-95/10

1995-02-13

Tablel

Advanced Reactors

Ptftl KtMlOfS

wO t

FtHHX

MW (e )

AE

E

AEP1

N4

PWR

M00

AEP2

SöeweCB

PWR 1 2 »

U S A *

W c

N K k a r B e c s k

AEP3

KWU-Conoy

PWR

1287

AEP4

APWR

PWR

1350

Dettfleddcsgn

AEPS

Syflem80PhB

PWR

1345 ABB-CE

ign

AEP6

WER-1000(V-392)

PWR

1000

RF

AEP7

EPR PWR

1500

SioKK-KWU/

Baoc design

AEB1

ABWR

BWR

13S6

O WIIM Itlll

AEB2

BW R

90

BWR

1379

ABBAiom

AEH1

CANDU9

HWR

1050

ABCL

AT

EvolatiooaryDesipH

for

Mc di aa Power Plaatt

ATP1

WE R- 5 0 0 /60 0

PWR

600

RF

Hydroprcs

Detåksl

ATP2 AP-600

PWR 630

US

Detailed design

ATP3

MS^OO

PWR 630

J a p »

Kfimbidu

Basic design

ATTH AC-600

PWR 600

Q u n a

CNNC

ATB1

SBWR

BWR

600

US

Gcrtcxal Ficftnc

gn

ATB2

HSBWR

BWR

600

J a p a n

Hitachi

esgn

ATB3

TOSBWR-900P

BWR

310

Japan

Toshiba

gn

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ST U D SV K/ E S-9S/ 10

1995-C2-13

Table 1 Advanced reactors (confd)

SE

ATB4

A7B5

A T C 1

A T H 1

Al

A O > 1

AV 2

AIP3

ADM

A K

AIP6

AIF7

AIP8

AIP9

B

BT

B T S 1

BTS2

BI

BIS3

BIS4

BUS

lOOONanml

CkaååömVWR

SWR1000

MEER-SOO

CANDU3

BW R

BWft

LM »

HWR

S K /

1000

1000

no

450

I S

Gaw

RF

C t a a *

r r — r w u

R D Ö t

AECL

Banc design

Sate

Dcaäled dcspi

PIUS-600

BER

ISIS

MAP

VPBER-600

SIR

SPWR

B-5OOSKDI

SCLWR

PWR

PWR

PWR

PWR

PWR

PWR

PWR

PWR

PWR

600

200

200

300

600

320

600

515

1100

S m * .

J - P -

taiy

US

RF

US/UK

RF

Japan

ABB A n a

JABU

fVHala^HaV < f

a

B

Ä;

OKBM

ABB-CE

^tolkRojwe

JAERI

KRC-KJfHyauprcss

UancnMy of Tokyo

Saafcs

Sariia

Banc design

Basic design

Banc design

Sojdks

Stadia

Stadks

Liqaid Metal

F aa

Reactors

Evote tmaryDeafas

EFR

BN-600M

LMR

LMR

1500

600

Fnact/GB/

GamanyAtaly

RF

EdF/NS/

Bayuawut/ENEL

OKBM

Banc design

1 ailvraMB^an

n^^^ wk

laaorative Designs

DEMOFBR

SAFR

ALMR (PRISM)

LMR

LMR

LMR

660

450

150

Japan

US

US

FEPS

RockweO IntCE

Gen enl Electric

Bapc design

Banc design

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STUDSVDC

ECO &

SAFETY

STUDSVK/ES-95/10

1995-02-13

Table 1 Advanced reactors (cont'd)

Abbre-

riatioB

BIL1

BIL2

C

d l

CD

CD

O 4

D

DU

DI2

DI3

Name

BREST300

LFBR

Type

LMR

LMR

She/

MW(e)

300

625

Co n t r y

RF

Japm

Vcador

RDIFE

JAERI

DeveiopBent

Studies

Studies

G u Co okd ReactofiA noTrtive derigM

HTR-Mntal

MHTGR

GT-MHR

HTGR-MHD

USR

FUJI-Pu

MSR-NC

Ritat

HTGR

Hit»

Ritat

MSR

MSP.

MSR

80

190

300

860

P i

625

100

470

US

I S

j * r »

US

Jspin

RF

Skmen-KWU

Genenl Atomics

JAERI

ORNL

Tokii Univcnily

RRC-KI

BttK dcsgn

Studies

Studies

Studies

Studies

Studies

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STUDS VK ECO & SAFETY

STUDSVIK/ES-95/10

1995-02-13

Table 1 Advanced Reactors (cont'd)

P a r tn Heating and Other Reactor Applications

A b b r e -

TiatMB

E

E l

E 2

E 3

E 4

ES

E 6

E 7

E 8

E 9

E 10

E l l

Name

Type

S a c /

MW(t)

Cmmry

Vcatdar

Onuiuliiia

D e r d o p m e n t

District Heatiag Reactors

A S T - 5 0 0 M

M A R S

S E C U R E - H

N H P - 2 0 0

Th e rm os -100

N H R - 2 0 0

R U T A

K N D H R

Slow pok e (SE S-10)

Geyser

G H R - 2 0

PW R

PW R

PW R

PW R

PW R

PW R

LW R

LW R

LW R

PW R

H T G R

500

600

400

200

100

200

20

10

10

10-50

20

R F

Italy

Sw e de n

Germany

France

d u n a

RF

Korea

Canada

Switzerland

Germany/Switz .

O K B M

R om e Unive rs i ry

A S E A

CEA

I N E T

R D I P E

K A E R I

A E C L

PSI

KW U

Commercia l

Studies

Studies

Detailed dPsiRP

B a s ic de s ign

Deta i led des ign

Studies

Studies

Commercia l

Studies

F D e c e n t r a li ze d N u c l e a r H e a t in g P o w e r R e a c t o r s

F l

F2

F3

F4

F5

F6

G

G l

G2

C A R E M - 2 5

P A E S - 1 0 0

TR IGA Pow e r Sy stem

ABV

E L E N A

C o m pa c t H T G R G a s

Turb ine

PW R

PW R

PW R

PW R

PW R

H T G R

100

160-170

64

60

3

29

Arge n t ina

RF

US

RF

RF

US

I N V A P

O K B M

Ge ne ra l A tom ic

O K B M

R R r . K I

Genera l Atomic

Studies

Commercia l

Commercia l

Deta i led des ign

Bask des ign

Studies

S h i p R e a c t o r s

O K - 9 0 0 A

K L T - 4 0

PW R

PW R

170

170

RF

RF

O K B M

O K B M

C o m m e r c i a l

C o m m e r c i a l

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STUDSVK EC » & SAFETY

STUDSVK/ES-95/10

1995-02-13

Table

1

Advanced Reactors (cont'd)

Abbrt-

G3

G4

I

11

Q

D

M

15

16

n

18

19

J

Jl

J2

J3

J4

J5

J6

Naaae

MRX

DRX

GPHS-RTG

ROMASHKA

TOPAZ-n

STAR-C

SP-100

ERATO

LMCPBR

Rov«/NERVA

NPPS

Type

PWR

PWR

doctnc

Fan.

ckrnn

LMR,

Fatt.

ThfTTnknuc

LMR7HTR

LMR/HIR

HTGR

H I T »

S a t /

MW(t )

100

0.75

Inwiriai

3 - H H M W e

MWe

6-10-

J

MW c

MWe

0.1 MW e

210"

2

M W e

10

3 6 7 - 1 5 6 6

1200

Sabcritieal Accelerator Drives W aste Tr a a w ta ti o a i

Energy A mplifier

PHOENIX

JAERI-TPC

ATW/ABC

AMSB

BBR

LWR/HTGR

LMR

MSR/LMR

MSR/LMR

MSR

MSR

200

3 6 0 0

820

3 0 0 0

1000-2100

5 0 0 0

Coaatry

Japan

J a p -

US

RF

RF

US

US

Fiance

Japan

US

RF

MdE ae r ty Ge ne n

Swioeriand

US

Japan

US

Japan

Pnnc t

Vendor

C X f A u a t u a

JAERI

JAERI

w

. ^ ^

RRC-K1

RRC-K1

Rockwell Insände

(fffnrral FJenric

CNES/CEA

JAERL Toshiba

LANL,

, ifgnmiff

RRC-H

CERN

BNL

JAERI

LANL

Tokay University

CEA

Ptyclopmcnt

Bane desgn

Detailed

design

Basic

deä

Batiedesini

Stadia

Stadia

Ran* ilfjuun

Stadia

Stadia

Stadia

Stadia

Stadia

Stadia

Stadia

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S T U D S V IK E C O & S A F E T Y

S T U D S V I K y E S - 9 5 / 1 0

1 9 9 5 - 0 2 - 1 3

Table 2

Advanced Nuclear Design Description Format

F o r m a t

D e s c r i p t i o n

T e c h n i c a l a p p r o a c h

Ti t l e

A p p li c a t o n o f t he r e a c t o r

R e a c t o r t y p e

P o w e r o u t pu t

O r g a n i z a t i o n

D e v e l o p m e n t s t a t u s

De s c r i p t i on

S c h e d u l e

R e f e re nc e s

E E v o l u t i o n a r y d e s i g n fo r l a r g e p o w e r p la n t s

T E v o l u t i o n a r y d e s i g n fo r m e d i u m p o w e r p la n t s

I I n n o v a t i v e d e s i g n

Ti t l e o f p ro j e c t

N P P N u c l e a r p o w e r p la n t

N H P N u c l e a r h e at in g p la n t

N H P P N u c l e a r h e a t a n d p o w e r p la n t

S M S S h i p m o b i le s y s te m

S N S S p a c e n u c l e a r s o u r c e

T W S T r a n s m u t a t i o n w a s t e s y st e m

P W R , B W R , H W R , L W G R , F B R , H T G R , M S R , SA D S

(s ubc r i t i c a l a c c e l e ra t o r -d r i ve n s ys t e m) e . a .

L L a r g e p o w e r ( m o r e t ha n 1 0 0 0 M W e )

M M e d i u m p o w e r ( m o r e t ha n 1 0 0 M W e , l e ss t ha n 1 0 0 0 M W e )

S S m a ll p o w e r ( m o r e t ha n 1 M W e , l e s s t ha n 1 0 0 M W e )

V S V e r y s m a ll p o w e r ( le s s t ha n 1 M W e )

Type of o rga n i za t i on , whi c h de ve l ope d de s i gn

C C o mme rc i a l ly a va i l a bl e de s i gn

D D e t a il e d e n g i n e e r i n g d e s ig n

B B a s i c e n g i n e e r i n g d e s ig n

S S t u d i e s o f c o n c e p t

G e ne ra l de s c r i p ti on o f the de s i gn . T hi s wi ll ge n e ra l l y i nc l ude a

s imple desc r ipt ion of the reac tor plant . This may be fo l lowed by a

s umma ry wi t h t he ma i n f e a tu re s o f an a c t ua l de s i gn u s i ng t a b le s

wi th main technica l da ta or f igures

S c h e d u l e fo r d e v e l o p m e n t

R e f e re nc e s f o r a dd i t i ona l i n f o rma t i on .

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Part I Reactors for power production

Introduction

I n m a n y c o u n t r i e s , n u c l e a r p o w e r h a s d e m o n s t r a t e d i t s c a p a c i t y t o g e n e r a t e

e l e c t r i c i ty on a l a rge s c a l e , c os t - e ff ic i e n t l y a nd wi t h l ow e nv i ro nme n t a l i mpa c t

O f t he c u r r e n t 4 3 0 o p e r a ti n g N P P u n i t s , a l m o s t 3 5 0 a r e L W R o n e s . T h e

o p e r a t in g e x p e r ie n c e o f t he s e p l a n t s s h o w s t h a t th e y r e p r e s e n t a n e c o n o m i c a n d

r e l i a bl e s o u r c e o f e l e c t ri c i ty pr o d u c t i o n . T h e y a l s o r e p r e s e n t a b r o a d l y

d e v e l o p e d a n d m a t u r e b a s i s o f t e c h n o l o g y fo r f u r th e r n u c l e a r p o w e r d e v e l o p -

m e n t T h e o bje c t i v e s f o r i m pr o v e m e n t s c o v e r a br o a d r a n g e o f in t e r e s t s u c h a s

r i s k mi n i mi za t i on , lowe r e ne rgy c o s t p rodu c t i on , i mprov e d re l i a b i li t y a nd

e nha nc e d s a f e t y .

P r o g r e s s

and schedule for the development and deployment of ALW R

A f te r t h e s e v e r e a c c i d e n t a t T h r e e M i l e I s l a n d U n i t 2 a u t h o r i ti e s i n s e v e r a l

c o u n t r ie s r e q u e s t e d m e a s u r e s f o r e n h a n c e d s a fe t y a t o p e r a t i n g p l a n t s . A m o n g

t he s e me a s u re s , f il te re d ve n t i ng o f t he c on t a i n me n t wa s i n s t a l le d i n ma ny p l a n t s

i n o r d e r t o m i ti g a t e c o n s e q u e n c e s i n t h e e v e n t o f s o m e s p e c i fi c s e v e r e a c c id e n t

s c e n a r i o s .

T h e d e v e l o p m e n t o f t h e A L W R P r o g r a m s t a rt e d in t h e U S A i n th e be g i n n i n g o f

t he 8 0 's o n t h e i n i t ia t i v e o f E P R I s u p p o r t e d b y u t i li t ie s , D O E , U S r e a c t o r

v e n d o r s a n d a r c h it e c t e n g i n e e r i n g fi r ms .

T h i s p r o g r a m p r o v i d e d a f o u n d a t i o n f o r t h e N u c l e a r P o w e r O v e r s i g h t

C o m m i tt e e ( N P O C ) c o m p r e h e n s i v e i n i t ia t iv e fo r r e v i t a l iz in g n u c l e a r p o w e r in

t he U S A , a s s e t fo r th i n i ts " S t ra t e g i c P l a n fo r B u i l d i n g N e w N u c l e a r P o w e r

P l a n t s " , p u b li s he d i n N o v e m b e r 1 9 9 0 a n d u p d a t e d a n n u a l l y e a c h N o v e m b e r .

W o r k o n t he U t i l it y R e q u i r e m e n t D o c u m e n t , U R D , s t a r te d i n 1 9 8 5 a n d w a s

c o m p l e te d i n 1 9 9 0 . T h e c o o p e r a t i v e e ffo r t s , F i r s t -o f - a - K i n d E n g i n e e r i n g ,

( F O A K E ) b e t w e e n t h e U S u t i l i t i e s , D O E a n d t h e v e n d o r s s t a r t e d i n 1 9 9 2 .

I n t he U S A t he l ic e n s i n g p r o c e s s w a s c h a n g e d i n 1 9 9 4 . A n i m p o r t a n t n e w

f e a tu re o f t h is p roc e s s i s t he i s s u i ng o f a fi na l de s i gn a pprova l (F D A ) .

T h e t i m e s ch e d u l e fo r s a fe t y e v a l u a t i o n , F D A a n d F O A K E i s g i v e n i n t he

fo l lo w i n g t a b l e , r e p r o d u c e d f ro m a n I A E A d o c u m e n t I n f a c t, th e F D A fo r

A B W R a n d S y s te m 8 0 P l u s w a s is s u e d i n m id 1 9 9 4 n o t fa r b e hi n d s c h e d u l e .

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A B W R System 80+ A P-600 SB W R

F i n a l S a fe ty E v a l u a t io n 5 / 9 4

R e p o r t

F i n a l D e s i g n A p p ro v a l 6 / 9 4

6 / 9 4

8 / 94

F i r s t -o f -a -Ki nd

E n g i n e e r i n g

9 / 9 6

- 4 / 9 6

- 6 / 9 6

9 / 9 6

-3 / 96

- 5 / 9 6

A ft e r t h e s e v e r e a c c i d e n t a t C h e r n o b y l U n i t 4 , t h e I A E A r e q u e s t e d i ts

I n t er n a ti o n a l N u c l e a r S a fe ty A d v i s o ry G r o u p I N S A G t o g i v e r e c o m m e n d a t i o n s

fo r a c t io n t o e n h a n c e r e a c t o r s a fe ty . I n 1 9 8 8 th e I A E A i s s u e d t h e I N S A G - 3

re por t wi t h t he t it l e o f B a s i c S a f e ty P r i n c i p l e s fo r N uc l e a r P owe r P l a n t s . Thi s

wa s fo l l owe d by fu r t he r r e por t s :

o I N S A G - 4

o I N S A G - 5

o I A E A S a f e ty F u n d a m e n t a ls

S a f e t y C u l t u r e ( 1 9 9 1 )

T h e S a f e t y o f N u c l e a r P o w e r ( 1 9 9 2 )

T h e S a f e ty o f N u c l e a r I n s t a l l a t io n s ( 1 9 9 3 )

A l r e a d y in t he I N S A G - 3 r e po r t fr o m 1 9 8 8 , a d i s t in c t i o n w a s m a d e b e t w e e n

ope ra t i ng p l a n t s a nd f u t u re p l a n t s . F o r fu t u re p l a n t s , t he proba bi l i t y o f s e v e re

c o r e d a m a g e s h o u l d b e l e s s th an 1 fo r e v e r y 1 0 0 0 0 0 r e a c t o r y e a r s a n d t h e

proba bil i ty o f l a rge r e l e a s e s t o t he e n v i ron me n t s hou l d be l e s s t ha n 1 fo r e ve ry

1 mi l l i on r e a c t o r ye a r s .

A s i m i l a r d e v e l o p m e n t e ffo r t fo r a E u r o p e a n P r e s s u r i ze d W a t e r R e a c t o r ( E P R )

w a s l a u n c h e d i n E u r o p e be t we e n F r a n c e a n d G e r m a n y i n e a r l y 1 9 9 2 f o ll o w ed b y

t he s t a r t in 1 9 9 2 o f p r o d u c i n g a E u r o p e a n U t i li ty R e q u i r e m e n t D o c u m e n t ,

( E U R ) .

T h e f ir s t tw o v o l u m e s o f t h e E U R w e r e p u b li s h e d i n F e b r u a r y 1 9 9 4 a n d

t he ma i n pa r t o f t he r e ma i n i ng do c um e n t i s s c he du l e d f o r c o mpl e t i on by the e nd

o f 1 9 9 4 .

T h e a d v a n c e d n u c l e a r po w e r p la n t d e s i g n s c u r r e n t l y be i n g d e v e l o p e d r e p r e s e n t

a w i d e r a n g e o f a l t e r n a t i v e s . M o s t o f t h e r e a c t o r c o n c e p t s a r e e v o l u t i o n a r y a n d

r e p r e s e n t s m a l l o r m o d e r a t e e x te n s i o n s o f c u r r e n t d e s i g n s . S o m e o f t he m u s e

u p g r a d e s o f o p e r a ti n g p la n t s . F e w c o n c e pt s b as e d o n w e l l- k n o w n L W R , H W R ,

L M F B R t e c h n o l o g i e s ha v e s i g n i fi c a n t d e p a r tu r e s f ro m t h e c u r r e n t o n e s . T h e r e

a r e a l s o s o m e n e w d e s i g n s t h a t u s e i n n o v a t i v e p r in c i p l e s , w h ic h a r e u n i q u e

c o m p a r e d t o c u r r e n t p r a c t ic e , e . g . t h e P I U S p r i n c i pl e fo r L W R , m o d u l a r h ig h

t e m p e ra t u r e g a s - c o o l e d r e a c t o r s

(HTR),

l i q u i d m e t a l r e a c t o r s ( L M R ) a n d

m o l te n s a lt re a c t o r s ( M S R ) .

T h e t yp ic a l d e s i g n s b e lo n g i n g t o w a t er - c o o l e d , L M R , H T R a n d M S R g r o u p s

a r e pr e s e n t e d i n T a b l e 1 ( s e e p 4 ) .

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I n t h is c a t a l o g u e , r e a c t o r d e s i g n i m p r o v e m e n t f o l l o w s t hr e e d i r e c t io n s ( s ee

F i g u r e 1 , p 1 4 ) d e s c r i b e d b e l o w .

Evolutionary d esigns for large power plants

A d e s i gn a pproa c h i nvo l v i ng " s t e p by s t e p" mod i fi c a t i ons o f pre s e n t -da y

d e s i g n s , wi th a n e m p h a s i s o n d e s i g n p r o v e n e s s . H e r e , m o r e t r a d it io n a l d e s i g n e r s

fi n d s m a l l e r w a y s t o m o d e r n i z e d e s i g n t o m e e t m o r e s t r in g e n t n e w s t a n d a r d s .

T h e s e ( m a i n l y la r g e p o w e r - m o r e th a n 1 0 0 0 M W e ) p r o v i d e th e i m pr o v e m e n t

of N P P re l i a b i li t y a nd ope ra t i ng s a f e ty wi t h t he s i mul t a ne o us i mprov e me n t o f

e c onomi c f e a t u re s due t o f u r t he r i mprove me n t a nd s i mpl i f i c a t i on , t o s ome

e xt e n t o f t he de s i g n . The s e de s i gn s , whi c h i nc o rpora t e d e x t ra s a f e ty f e a t u re s ,

r e qu i re on l y s ma l l a dd i t i ona l t e s t ing .

E v o l u t i o n a r y d e si g n s

for medium power plants

A d e s i gn a pproa c h whi c h a l l ows fo r t he i mprov e me n t o f the N P P re l i a b il i ty a nd

s a f e t y wi t h s i mul t a ne ous i mprove me n t o f t he e c onomy a nd c ompe t i t i ve ne s s due

t o s i mpl i fi c a t ion o f t he N P P de s i gn a n d re du c t i on o f s pe c i fi c c o re powe r a nd t he

u n i t po w e r o f a re a c t o i ( m a i n l y a b o u t 6 0 0

M W e ),

t he c ons t ruc t i on pe r i od , t he

de g re e o f f i na nc i a l r i s k a nd e xpe c t e d broa de n i ng o f t he ma rke t i n t he de ve l op i ng

c ou n t r i e s . Thi s a pproa c h re f e r s t o t he e vo l u t i on a ry p l a n t wi th s i gn i fi c a n t

i nno va t i ve f e a t u re s , whic h a re , howe ve r , wi t hi n t he r a n ge o f e x is t i ng t e c hn i c a l

k n o w l e d g e .

I n n o v a t i v e d e s i g n s

S o m e o f th e n e w A L W R d e s i g n s e n s u r e th e i m pr o v e m e n t o f L W R - b a s e d N P P

a nd N H P re l i a b il i ty a nd s a fe ope ra t i on m a i n l y due t o c ha ng e s i n t he de s i g n

a r ra nge me n t a nd pe r f o rma nc e s o r i n p l a n t r e s pons e s t o t he a c c i de n t s . The ma j o r

de v e l opme n t g oa l s s t a te d f o r s ome of t he s e p l a n t de s i g ns a re s i mpl if ic a t ion a nd

a n e nha nc e d u s e o f pa s s i ve s a f e t y f e a t u re s , ba s e d on c u r re n t p l a n t de s i gn

t e c hn o l o g y . O t h e r s , m a in l y n o n - A L W R r e a c t o r t y p e s , h a v e m o r e a m b it io u s

de v e l opme n t g oa l s t ha t, i n t u rn , r e qu i re more r a d i c a l mod i fi c a t i ons o f de s i gn

a iming a t the maximum poss ible u t i l iza t ion of inherent safe ty fea tures and

self-

pro t e c t i on c a pa c i t y .

ww v ic tor/95- 10a ea

References

T A Y L O R , J J an d S A N T U C C I , J

S a f e t y , t e c hn i c a l , a nd e c onomi c obj e c t i ve s o f EP R F s a dva nc e d

l i gh t wa t e r r e a c t o r p rog ra m.

S y m p o s i u m o n A d v a n c e d N u c l e a r P o w e r S y s t e m s .

S e o u l , R e p u b li c of K o r e a , 1 8 - 2 2 O c t , 1 9 9 3 ( I A E A - S M - 3 3 2 / I I .l )

R e v i e w o f a d v a n c e d L W R d e s i g n a p p r o a c h e s , 1 9 9 4 ,

1 A E A - T C - 8 7 9 .

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STUDSVIK/ES-95/10

1995-02-13

13

BACHER, P and BOA RD , J

IAEA-SM-332.

G O L A Y . M W

Advanced Fission Power Reactors.

Ännu Rev Part Sci, 199 3, v 4 3, p 29 7-3 32.

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c

s

o.

C O

c

o

I

ABWR

Size we li B[ lBWR 9̂Öl [ÄPWR W /M

Convoi EPR W ER-92

N4l [Sy stem 80+1 [Candu 9

Current

LWR

\ Large siz e

ALWR

MS-600

WER-500 AP-600

Candu 3 | lAC-600

MKER-8001

1

SBW R

1

iTSBWRl

HSBWR

Mid size

ALWR

VPBER MHTGR

ALMR

SIR MARS

PIUS-PW R, BWR

Modular HTR

Modular LMR (Na, Pb)

MSR, other

Figure I

Different approaches to improvemen ts of advan ced f i ss ion reac tor des igns .

Innovations

C/3

m

3

i-- C/3

v »

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S T U D S V I K / E S - 9 5 / 1 0

1 9 9 5 - 0 2 - 1 3

A Advanced W ater-Cooled Reactors

AE Evolutionary designs for large power plants

AEO Introduction

T h e d e s i g n s o f n e w l i g h t w a t e r r e a c t o r s h a v e t o m e e t c r i te r i a c o n c e r n i n g

i mprove d s a f e t y , e c onomi c c ompe t i t i ve ne s s a nd u s e r f r i e nd l i ne s s . C r i t e r i a

ha ve be e n i s s ue d by u t il i ty g rou ps a nd a u t ho r i t i e s , whi c h ha ve be e n

me n t i one d e a r l i e r .

The e vo l u t i ona ry a pproa c h ha s t he be ne f i t o f p rov i d i ng t he f o l l owi ng :

o

o

o

o

o

o

P r e d i c t a bl e pe r fo r m a n c e b a s e d o n e x p e ri e n c e

E n h a n c e d s a f e ty , p e r fo r m a n c e a n d e c o n o m i c s

I n c r e m e n t a l c h a n g e s in t e c h n o l o g y

A va i l a b il i ty o f prov e n e qu i pme n t a nd s ys t e ms

A v o i d i n g n e e d t o a d d i t o n a l e x pe r i m e n t a l v e r i fi c a ti o n

As s u re d a c c e pt a nc e a nd l i c e ns i b i l i t y

In c o m p a r is o n w i th th e fi rs t s t a g e L W R g e n e r a t i o n e v o l u t i o n a r y A L W R

d e s i g n s u n d e r w e n t a c o n s i d e r a b l e c h a n g e . T h e c h a n g e i n v o l v e d , b a s ic a l ly , th e

e n h a n c e m e n t o f a po w e r o f u n i t s , t h e r m o d y n a m i c p a r a m e t e r s o f a s t e a m -

turbine cyc le , fue l u t i l iza t ion, opera t iona l re l iabi l i ty and safe ty.

The s a f e t y o f e vo l u t i ona ry powe r p l a n t de s i gns ha s be e n i mprove d on a

re a l i s t ic a nd e ffi c ie n t ba s i s wi thou t je o pa rd i z i ng e c o no mi c s .

In summary, the fo l lowing i s a l i s t of the most s ignif icant safe ty improve-

m e n t s a p pl ic a b l e t o o n e o r m o r e r e a c t o r t y p e s :

o R e d u c t i o n o f t he c o r e p o w e r d e n s i t y

o I n c r e a s e in t he n u m b e r o f c o n t r o l d r i v e s

o A ppli c a t ion o f s pe c t ra l c on t ro l s t o c o mpe ns a t e t he va r i a t i on o f

re a c t i v i t y wi th bu r nu p

o I n c r e a s e in t he c o o l i n g w a t e r i n v e n t o r y c a p a b l e o f b e in g s t o r e d

wi th in t he c on t a i nme n t a nd pr i ma ry c i r c u i t s pa c e

o A p pl ic a t io n o f t h e e m e r g e n c y c o r e c o o l i n g s y s te m ( E C C S ) t o

e a c h l oop

o Improv e me n t o f N P P pro t e c t i o n i n c a s e o f a l o s s o f o f f- s i te

p o w e r

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STUDSVIK ECO & SAFETY AB ST U D SV K /E S-95/10

1995-02-13

A :2(3 )

o Improvement of off- and in-rcactor monitoring for predicting

the reactor pow er density and temperature distributions on a

real time basis

o Reduction of the neutron fluence on the reactor vesse l

o Mitigation measures for severe core damage accidents with

failure of the reactor pressure vessel (RPV)

o Filtered containment venting

o Application of a double containment protected from external

effects by strong reinforced concrete structure

o Replacem ent of block-type control boards with multifunctional

displays

o Division of the personnel's function among the operators

responsible for maintaining rated operating conditions,

engineers responsible for N PP control under emergency

conditions, operators responsible for maintaining reactor

availability during outage, refuelling, repair

o Increased use of periodical simulator training of operator,

maintenance personnel etc

o Development of systems capable of checking the main

equipment operability during reactor operation

This design approach o bviously implies a step-wise evolution of the plant

design on the basis of the utility requirements and stated preferences. Large

power ALW R designs are now under consideration in France, Germany, UK ,

US A, Japan, Russia, Sw eden and som e other countries. Canadian HW R lines

are also presented.

References

o

G A G A R I N S K L A Y u e t a l

Advanced L ight W ater Reactors: new ideas and approaches.

Nuclear Society International, M oscow , RF, 1992.

The new reactors, Special session .

Nuclear News , 1992, September, p 69 6 -90.

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S T U D S V K ECO & SAFETY AB ST U D SV K /E S-95/10

1995-02-13

A : 3 ( 3 )

o

PE D E R SE N . T J

Current trends ii? safety philosoph y and des ign goa ls for

advanced nuclear power plant design s.

Proceedings ASME/ISME Nuclear Engineering Conference,

Vol 2 ,199 3, ASME, p 539-544 .

Survey of containment designs for new/advan ced water

reactors.

1994, OE CD, Report NEA /CSN1/R(94 )5.

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1 9 9 5 - 0 2 - 1 3

AEPl:i(3)

AEP1

Format

Title

A ppli c a t i on o f t he

r e a c t o r


P o w e r o u t p u t

O r g a n i z a t i o n ( n a m e )


De s c r i p t i on

Description

N 4

N P P

P W R

La rge powe i

E l e c t r i c i t é d

C o m m e r c i a l

T h e F r e n c h

S c h e d u l e

T h e F r e n c h N 4 p la n t is a 1 4 0 0 M W e P W R w it h 4 t r a in s y s t e m s o r g a n i z a bo n .

T h e N 4 i s fu e l le d b y e n r i c he d U O 2 p e l l r t s a n d u s e s Z i r c a l l o y - 4 a s a c l a d d i n g

ma t e r i a l . T he a c t i ve c o re he i gh t is 4 . 2 m a nd i t c on t a i n s 2 05 f ue l a s s e mbl i e s

wi t h a 17x17 a r ra y . As r e ga rds s a f e t y , i t wa s de s i gne d i n a n e vo l u t i ona ry

pe rs pe c t i ve , be ne f i t i ng t he e xpe r i e nc e ga i ne d f rom t he pre v i ous s t a nda rd i ze d

s e ri es o f 9 0 0 M W e a n d 1 3 0 0 M W e p la n t s , a n d u s i n g t e c h n o l o g i c a l p ro g r e s s

a nd ne w de ve l opme n t s a f t e r c a re f u l va l i da t i on .

The s a f e ty i mprove me n t s a re t he f o l lowi ng :

0 M o r e a c c u r a te a n d fu n c t io n a l l y a d a p t e d i n s t r u m e n t a t i o n

0 A be tt e r g l oba l me t hodo l og i c a l a pproa c h f o r fi re ha za rds

0 M e a ns t o de a l wi th t o t a l l o s s o f f re que n t l y u s e d s ys t e ms , a nd

wi t h s hu t -down c ond i t i ons

0 A n i n c re a s e d r o le fo r P S A in t he d e s i g n a n d l ic e n s i n g p r o c e s s

Ot he r i mpor t a n t f e a t u re s o f N4 p l a n t a rc a c omput e r i ze d c on t ro l room a nd

mi t iga t i on o f c o re me l t in u l t i ma t e c on d i t i ons , wi th f i l te re d ve n t i ng

c on t a i nme n t a s l a s t op t i on .

T h e N 4 t hr e e u n i t s a re u n d e r c o n s t r u c ti o n in F r a n c e . T h e f i r st N 4 u n i t

C h o o z B - l is to b e c o m m i s s io n e d in 1 9 9 5 .

ww victor/ AEP1 ca

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S TU D S V IK E C O & S A F E T Y A B

S T U D S V K / E S - 9 5 / l ö

1995-02-13

AEP1:2(3)

N 4 U n i t

Data

Thermal power

R e a c to r C o re

Equivalent diameter

N umber of control assemblies

Initial enrichment

En richment at equilibrium

A verage fuel burn -up at equilibrium

To ta l weight of UO 2

Reac to r C oolan t S ys tem

O perating pressure

R eactor vessel in let temperature

Reactor vessel outle t temperature

N umber of reac to r coo lan t pumps

Reac to r P ressure V esse l

Inside diameter

To tal height

Design pressure

D esign temperature

Containment

Configuration

G ross vo lume

D esign pressure

S te am G e n e ra to r s

Number

Steam pressure a t SG ou t le t

Steam temperature a t SG ou tle t

4 270MW

3.47 m

7 3

1.8/2.4/3.1 % U - 23 5

3 .4 U - 2 3 5

3 9 M W d / k g

1 1 0 . 4 1

155 bars .

2 9 2 .2 ° C

3 2 9 .6 ° C

4

4 .5 m

13.64 m

172 bar

3 4 3 ° C

Double

7 2 0 0 0 m

3

5.3 bar

4

72 .3 bar

2 8 8 ° C

References B E R G E R - P E R R I A , M M (E d F ) an d L A N G E , M ( F ra m at om e)

"Basic Information on D esign Features of the N 4 N uclear Power Plant"

Review of Advanced L igh t W ate r Reac to r Des ign A pproaches , M oscow,

RF, 10-13 M ay, 1994, IAE A -TC-879 .

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ea

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> 1

i

t i ) .v

N

\

\1 1M

n V l . l ' l

tt di

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S T U D S V I K / E S - 9 5 / 1 0

1 9 9 5 - 0 2 - 1 3

A E P 2 : i ( 3 )

A E P 2

Format

Ti t l e

A ppli c a t ion o f t he

r e a c t o r





De s c r i p t i on

Description

Sizewel l B

N P P

P W R

L a r g e P o w c

W e s t i n g h o u

C o m m e r c i a l

Th e reactor i

S c h e d u l e

ww victor/AEP2

ea

W e s t i n g h o u s e / N u c l e a r E l e c t r i c , U S A J n i t e d K i n g d o m

T h e r e a c t o r d e s i g n i s d e v e l o p e d o n t h e b a s i s o f we l l- e s t a bl i sh e d P W R

p r a c t i c e s , d e r i v e d fr o m th e W e s t i n g h o u s e S N U P P S ( S t a n d a r d i s e d N u c l e a r

U n i t P o w e r P l a n t S y s te m ) d e s i g n .

The f ue l i s l ow-e n r i c he d u ra n i um oxi de c l a de d i n Z i rc a l oy 4 . The c o re

c on t a i n s 193 f ue l a s s e mbl i e s , c ons i s t i ng o f 236 f ue l rods e a c h . C on t ro l rods

f o rmi ng rod c l u s t e r c on t ro l a s s e mbl i e s c a n be i n s e r t e d i n t o t he c o re i n

i n t e r s t i ti a l s pa c e s wi t h in c e r t a i n o f t he fue l a s s e mbl i e s a nd t he y a re g roupe d

i n t o a numbe r o f " ba nks " f o r r e a c t o r c on t ro l a nd f o r s hu t down.

T h e c o r e i s c o o l e d b y w a t e r a t a pr e s s u r e o f 1 5 . 5 M P a . The r e a c t o r c o o l a n t

s ys t e m c ompr i s e s t he r e a c t o r p re s s u re ve s s e l , f ou r c e n t r i f uga l r e a c t o r c oo l a n t

pumps , fou r v e r t i c a l s t e a m ge ne ra t o r s wi t h the pr ima ry c oo l i ng c i r c u i t

pa s s i ng t h rough a n i n s e r t e d U- t ube bund l e , a p re s s u r i ze r a nd l i nk i ng

pi pe work .

The i mpor t a n t e ng i ne e r i ng s a f e t y f e a t u re s o f t he r e a c t o r p l a n t a re :

o 4 - t r a in s ys te m o rga n i za t ion

o 30 mi nu t e s t o l e ra nc e be fo re ope ra t o r a c t i on

o F u l l y c ompu t e r i ze d re a c t o r p ro t e c t i on s ys t e m

o S t a ti o n b la c k - o u t a d d r e s s e d b y t w o r e l ia b le g r i s a n d fo u r

e me rge nc y s ys t e ms

T h e r e a c t o r d e s i g n i n c o r p o r a t e s a c o n s i d e r a b l e d e g r e e o f r e d u n d a n c y a n d

d i ve r s i t y in s ys t e ms prov i d i ng s a fe t y f unc t ions .

The p l a n t i s owne d a nd o pe ra t e d by Nu c l e a r E l e c t r i c , t he e l e c t r i c a l u t i li t y

o p e r a t o r o f n u c l e a r p o w e r s t a ti o n s i n E n g l a n d a n d W a l e s , w i th s c h e d u l e d

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S T U D S V K / E S - 9 5 / 1 0

1 9 9 5 - 0 2 - 1 3

AEP2:2(3)

s t a r t- u p i n 1 9 9 4 . N u c l e a r E l e c t r ic h a s f o r m a ll y a p p li e d f o r p l a n n i n g c o n s e n t

t o bu i l d S i ze we l l C un i t whi c h wou l d r e p l i c a t e t he S e ze we l l B de s i gn .

R e f e re nc e s

S i ze w e ll B U n i t

Data

The rma l c a pa c i t y

F u e l

M a t e r i a l

En r i c he d ( f e e d f ue l )

F ue l c l a d ma t e r i a l

R e a c t o r c o r e

A c t iv e h e i g h t

E q u i v a l e n t d i a m e t e r

M a s s o f U O 2 in t h e c o r e

R e a c t o r v e s s e l

Ove ra l l he i gh t

I n s i d e d i a m e te r

M a t e r i a l

I n t e rn a l c l a d d i n g

Dry we i ght

S t e a m g e n e r a t o r

N u m b e r

T u r b o g e n e r a t o r

N u m b e r

C o n t a i n m e n t

C onf i gu ra t i on

G r o s s v o l u m e

D e s i g n e d p r e s s u r e

3 4 1 1 M W t

s i n te r e d U O 2

3 . 1 %

Z i r c a l o y 4

3 . 6 6 m

3 . 3 7 m

1 0 1 1

1 3 . 5 2 m

4.394

m

l ow a l l oy s t e e l

s t a i n l e s s s t e e l

4 3 5 t

4

2

D o u b l e

9 1 0 0 0 m

3

3 . 5 ba r

B O A R D , L A a n d Q U I C K , M V

T h e S i ze w el l B P W R D e s i g n ,

R e v i e w of A d v a n c e d L i g h t W a t e r R e a c t o r D e s i g n A p pr o a c h e s , 1 0 - 1 3 M a y ,

1994, R F , M o s c o w, I A E A - T C - 8 7 9 .

N uc l e a r E l e c t r i c Ann

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> I i 1

^ \ I K i t ) v s \

M V 1

f f i ;

'" i

J --

' 1

i

i

i

i

f

C o n t r o l r o d d r i v e

m e c h a n i s m

T h e r m a l .

s l e e v e

U p p e r s u p p o r t .

p l a t e

I n t e r n a l s s u p p o r t

l e d g e

C o r e b a r r e l

C l o s u r e h e a d

a s s e m b l y

L i f t i n g l u g

O u t l e t n o z z l e

U p p e r c o r e

p l a t e


C o r e s u p p o r t

c o l u m n s

I n l e t n o z z le

F u e l a s s e m b l i e s

I r r a d i a t i o n

s p e c i m e n g u i d e

L o w e r c o r e

p l a t e

N e u t r o n s h i e l d

B o t to m s u p p o r t

f o r g i n g

R a d i a l s u p p o r t

L o w e r

i n s t r u m e n t a t i o n

g u i d e t u b e

I i m i i v \ l l ' 2

S i / - A • ' , K

M ,

i

I ' ;

• , i i • \

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S T U D S V n C E C O & S A F E T Y A B S T U D S V K / E S - 9 5 / 1 0

1 9 9 5 - 0 2 - 1 3

A E P 3 : l ( 3 )

A E P 3

Format

T i d e

Appl ica t ion of the

r e a c t o r

R e a c t o r t y pe




De s c r i p t i on

Description

K W U - C o n v o y

N P P

P W R

L a r g e p o w e r / 1 2 8 7 M W e

S i em e n s - K W U , G e r m a n y

C o m m e r c i a l

T h e K W U - C o n v o y N u c l e a r S te a m S u pp ly S y st e m ( N S S S ) c o n s i s ts o f a P W R

w i th fo u r p r i m a r y c o o l a n t l o o p s , a p r e s s u r i z e r c o n n e c t e d t o o n e o f t he l o o p s , 4

s t e a m ge ne ra t o r s , f ou r r e a c t o r c oo l a n t pumps a nd t he a uxi l i a ry a nd s a f e t y

s y s t e m s d i r e c t l y r e l a t e d t o t he N S S S . T h e N S S S g e n e r a t e s a p pr o x im a t e ly

3 7 8 2 M W t pr o d u c i n g s t e a m a t 6 3 . 5 b a r a t t h e s te a m g e n e r a t o r o u t l e t. T h e

t u r b in e g e n e r a t o r p r o v i d e s a n e t p o w e r o f a p p r o x im a t e l y 1 2 8 7 M W e . F u ll

l oa d re j e c t i on i s a c c e p t e d wi t hou t a r e a c t o r o r t ub i ne t r i p . The t u rb i ne p l a n t i s

c o m p l e te l y a u t o m a t ic a n d s u p e r v i s e d fr o m t h e c o n t r o l r o o m .

A s hor t s umma ry of ma i n s a f e t y a nd ope ra t i ona l f e a t u re s i s g i ve n be l ow.

T h e r e a c t o r c o r e c o n c e p t i n c l u d e s :

o A n R P V w i th a w i d e g a p b e t w e e n t he c o r e b a r r e l a n d R P V

s he l l whi c h ke e ps t he i n t e g ra l ne u t ron dos e t o t he R P V be l t l i ne

a t a low leve l Qimita t ion of embri t t l ement ) .

o Lo w l i ne a r he a t ge n e ra t i on r a t e , r e s u l t i ng i n h igh bumu p

capabi l i ty and inc reased fue l management f lexibi l i ty.

o The us e o f Z i rc a l oy 4 gu i de t h i mbl e s a nd s pa c e r s i nc re a s e s

n e u t ro n e c o n o m y .

o G a do l i n i um po i s on i ng o f fue l rod s i mprove s fue l u t i l iza t ion .

T h e r e a c t o r b u i ld i n g c o n c e p t i n c l u d e s :

o

The us e o f the s phe r i c a l s t e e l c on t a i nme n t , de s i g ne d fo r fu l l

p r e s s u r e a n d t e m p e r a t u r e a f t e r a d o u b l e - e n d e d L O C A .

A fue l poo l i n s i de c on t a i nme n t , whi c h fa c i l it a t e s ha nd l i ng a nd

shortens refue l ing t ime .

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S T U D S V U C E C O & S A F E T Y A B S T U D S V K / E S - 9 5 / 1 0

1 9 9 5 - 0 2 - 1 3

A E P 3 : 2 ( 3 )

S c he d i i l e

o T h e u s e o f a r e i n f o r c e d c o n c r e t e c o n t a i n m e n t p r o te c t s t he

N P P a g a i n s t e x te r n a l e v e n t s .

T h e l a s t s e r i e s o f P W R s b u i l t i n G e r m a n y i s t h e s ta n d a r d i z e d t yp e of K W U -

C o n v o y c o n c e p t H o w e v e r , th e r e i s a l w a y s r o o m fo r f u r th e r i m p r o v e m e n t s i n

t he t e c hn i c a l f ie l d .

K W U - C o n v o y U n i t

Data

T h e r m a l p o w e r

F ue l a s s e mbly

A r r a y

Numbe r o f f ue l rods

N u m b e r o f g u i d e t u b e s fo r a b s o r b e r

F u e l R o d

L e n g t h

O u t s i d e d i a m e t e r

C l a dd i ng ma t e r i a l

F ue l pe l l e t

E n r i c hme n t f o r t he fi r s t c o re

F o r th e r e l o a d c o r e

A v e r a g e fu e l b u m u p

Tot a l we i ght o f t he UO2

R e a c t o r c o o l a n t s y s t e m

D e s i g n c o n d i t i o n s

P r e s s u r e

T e m p e r a t u r e

R e a c t o r c o o l a n t p u m p

T y p e

N u m b e r


T y p e

N u m b e r



Di a me t e r

D e s i g n e d p r e s s u r e

3 7 8 2 M W t

1 8 x 1 8 - 2 4

3 0 0

2 4

4 . 4 m

9 . 5 m m

Z i r c a l o y 4

1.9; 2 .5; 3 .2 %

3 . 2 ; 3 . 4 %

3 1 . 8 M W d / k g

1 0 3 1

1 7 5 b a r

3 5 0 ° C

S i ng l e - s t a ge c e

4

U - t ube , ve r t ic a

4

D o u b l e

5 6 m

5 . 3 b a r

w w v ic to r /AEP 3 e a

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S TU D S V U C E C O & S A F E T Y A B

S T U D S V K / E S - 9 5 / 1 0

1 9 9 5 - 0 2 - 1 3

AEP4:i(4)

AEP4

Format

T i d e


r e a c t o r





De s c r i p t i on

Description

A P W R ( A d v a n c e d P r e s s u r i z e d W a t e r R e a c t o r )

N P P

P W R

L a r g e p o w e r / 1 3 5 0 M W e

M i ts u b is h i/ K a n s a i E l e c tr ic P o w e r C o ( K E P C O

D e t a il e d d e s i g n

T h e A P W R is ba s e d o n t h e d e s i g n , w h ic h i n c o i

s i mpl i fi c a t ion a nd a dd i t iona l ope ra t i ng ma rg i ns , a nd ope ra t i ng e xpe r i e nc e o f

c u r r e n t P W R s . B a s i c al ly , t he A P W R i s a fo u r - lo o p P W R . T h e th e rm a l p o w e r

of t he r e a c t o r i s 3823 M W L T h e fu e l r o d s a r e a s s e m b l e d i n s q u a r e a r r a y s .

C o m p a r ed w i th S iz ew e ll B a n d K W U - C o n v o y p la n t s ( se e A E P 2 a n d A E P 3 ) ,

t he numbe r o f fue l a s s e mbl i e s i s unc ha ng e d , bu t t he c o re de ns i t y i s l owe re d

by 20

r e l a t i ve t o c onve n t i ona l de s i gns , by us i ng l a rge r s i ze a s s e mbl i e s .

E a c h f uel a s s e mbl y c ons i s t s o f a 19 x 19 a r ra y o f p ins c l a d de d by Zi rc a l oy 4

( i n s t e a d o f a 17 x 17 t r a d i t iona l a r ra y) . A f uel a s s e mbl y c on t a i n s 16 t h imbl e s

t o h o u s e s p e c t r a l c o n t r o l b y in t r o d u c i n g w a t e r - d i s p la c i n g r o d s . T h e

displace rs remain inse r ted in to the fue l a ssembly dur ing the f i rs t ha lf of the

fue l e lement l i fe t ime . At the core leve l in the fue l a ssembly, a la rge number of

Z i rc a loy 4 g r i d s i s u s e d . To e n ha nc e t he me c ha n i c a l s t r e ng t h o f t he fue l

a s s e mbl y, t he f ue l e l e me n t c l a dd i ngs a nd g r i d s a re t h i c ke ne d . To re duc e

ne u t ron l e a ka g e , t he c o re i s e nc l o s e d by a s t e e l ne u t ron re f l e c t o r . W i t h 3

f ue l e n r i c hme n t i n U-235 , t he pe r i od o f c on t i nuous powe r ope ra t i on i s 13 . 5

m o n t h s . T h e 1 0

c o s t re d u c t i o n o f t he A P W R fu e l c y c l e re s u l t s fr o m a b o v e

no t e d f e a t u re s . The ma j o r pa r t o f t he s e i mprove me n t s i s due t o a s pe c t ra l

c o n t r o l . W i th " g r e y" c o n t ro l r o d s r e p la c e d b y c o n v e n t i o n a l o n e s , th e r e a c t o r

c a n ope ra t e wi th a mixe d U O2-P UO2 fue l .

O t he r t ypi c a l fe a t u re s a re :

0 The i nc re a s e d s i ze o f t he R P V (a l l l a rge no zz le s a re no w we l l

a bove t he c o re t op)

0 T h e c o n t a i n m e n t w it h a n e m e r g e n c y w a t e r s t o r a g e t a n k a t t he

bo t t om a nd t he f ou r - t r a i n a r ra nge me n t o f e me rge nc y c oo l i ng

pumps (wi th "pa i rs" of d ive rs i f ied des ign)

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S T U D S V n C E C O & S A F E T Y A B

AEP4:2(4)

1 9 9 5 - 0 2 - 1 3

S c he du l e

T h e s t e a m g e n e r a t o r a n d t u r b i n e d e s i g n s a r e i m p r o v e d . T o r e d u c e t he

ra d i a t i on dos e o f t he pe r s onne l , a c c e s s i s i mprove d t o t he un i t s whi c h re qu i re

t o r e pa i r work . Low c oba l t c on t a i n i ng s t ruc t u ra l ma t e r i a l s a re t he n a ppl i e d .

The s i ze o f t he ha t c he s f o r s t e a m ge ne ra t o r e xa mi na t i on a nd re pa i r i s

i n c r e a s e d .

T h e d e s i g n a ti o n A P W R i s n o t g e n e r a ll y kn o w n i n th e U S . W e s ti n g ho u s e h as

n o t u s e d t he U S c e r t if ic a t io n p r o c e s s . S o m e d e s i g n a c t iv i t ie s h a v e c o n t i n u e d

i n J a p a n , bu t a d e c i s i o n o n c o n s t r u c t i o n o r s i t in g h a s n o t b e e n t a ke n y e t .

A l s o ,

b e c a u s e u t il it ie s e x pr e s s e d a d e s i r e fo r a n A P W R a t a n o m i n a l

1 0 0 0 M W e r a t in g , W e s t in g h o a s e d e v e l o pe d t h e n o m in a l 1 0 5 0 M W e t h re e

lo o p A P W R .

APW R Unit Data

El e c t r i c a l ou t pu t

R e a c t o r c o r e

N umbe r o f fue l a s s e mbl i e s

Ac t i ve he i gh t

E q u i v a l e n t d i a m e t e r

T o t a l w e i g h t o f U O 2

N u m b e r o f r o d c l u s t e r c o n t r o l

assembl ies

A v e r a g e p o w e r d e n s i t y

R e a c t o r c o o l a n t s y s te m

P r e s s u r e a t v e s s e l o u t l e t

F l ow ra t e


In s i de d i a me t e r

Ove ra l l he i gh t

R e a c t o r c o o l a n t p u m p

S pe e d

W e i g h t


He a t t r a ns f e r s u r f a c e

O u t l e t s t e a m p r e s s u r e



D i a m e t e r

1 3 5 0 M W e

193

3 . 9 m

3 . 9 8 m

1 1 9 . 2 1

6 9

8 0 k W / l

157 ba r

8 8 0 0 0 m

3

/h

5 m

16 m

1 1 8 5 r pm

9 2 t

6 0 3 9 m

2

6 9 b a r

D o u b l e

6 0 m

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S T U D S V K E C O & S A FE T Y A B

ST U D SV n C / E S- 9 5 / 1 0

1995-02-13

AEP4:3(4)

References

Technical Information on De sign Features of the APW R.

Review of Advanced Light W ater Reactor Design A pproaches.

10-13 May 1994, Moscow, RF, IAEA-TC-879.

The W estinghouse APW R

Nuclear New s, 1992, September, p 74 -75.

Spray Header

Core

Reflood

Tank

Spray Header

Spray Header

Core

Reflood

Tank

Spray Header

Emergency Water

Storage Tank

_J

H : High Head SI Pump (4 sets)

R : RHR/CV Spray Pump (4 sets)

Figure AEP4

A PW R: In tegra ted safeguards system layout around conta inment vesse l .

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S T U D S V I K E C O & S A F E T Y A B S T U D S V IK /E S -9 5 /1 0

1 9 9 5 - 0 2 - 1 3

AEP5:i(4)

AEP5

F o r m a t

T i t l e

A ppli c a t i on o f the

r e a c t o r





De s c r i p t i on

Description

S y s te m 8 0 P l u s

N P P

P W R

L a r g e p o w e r / 1 3 4 5 M W e

A B B - C E N u c l ea r P o w e r , U S


S y s te m 8 0 P l u s is a n a d v a n c e

e n h a n c e m e n t s o f t h e S y st e m 8 0 s t a n d a r d i ze d d e s i g n . T h e S y s t e m 8 0 p l a n t

d e s i g n i s u s e d f o r P a l o V e r d e u n i t s in A r i zo n a , t he U S A . T h e e n h a n c e m e n t s ,

a s i n te g r a t e d d e s i g n p r o c e s s , a d d r e s s n e w l i c e n s i n g i s s u e s , s a f e ty

improvements , improved operabi l i ty, ava i labi l i ty and mainta inabi l i ty, plant

s i mpl i f i c a t i on a nd c os t r e duc t i ons .

T h e t h e r ma l p o w e r o f th e r e a c t o r i s 3 8 1 7 M W t . T h e r e a c t o r v e s s e l i s

d e s i g n e d t o c o n t a i n a n d s u p po r t t he c o r e a n d t h e f u e l. T h e d e s i g n o f i he c o r e

i s ba s e d on t ha t on e o f S ys t e m 80 . T he re a c t o r v e s s e l i s a ve r t i c a l l y moun t e d

c yl ind r i c a l v e s s e l wi t h a he mi s phe r ic a l bo t t om a t t a c he d t o t he ve s s e l a nd a

re mov a bl e he mi s phe r i c a l u ppe r c l o s u re he a d . The re a c t o r ve s s e l i s fa br ic a t e d

from l o w a l l oy s t e e l a nd t he i n t e rna l s u r f a c e s t ha t a re i n c o n t a c t wi t h t he

r e a c t o r c o o l a n t a r e c l a d d e d w i th a u s t e n i t ic s t a i n l e s s s t e e l. T h e r e a c t o r c o r e

c o n s i s ts o f 2 4 1 f u el a s s e m b li e s a n d 9 4 o r m o r e c o n t r o l e l e m e n t s . A n

a dva nc e d bu rna bl e a bs o rbe r s t r a te gy i s i mpl e me n t e d t o s i mpl ify re a c t i v i ty

c on t ro l a nd prov i de f o r e x t e nde d f ue l bu rnup . F u l l - s t r e ng t h c on t ro l e l e me n t

a s s e mbl i e s c ons i s t o f a Inc o ne l c l a d wi th bo ron c a rb i de o r s i l ve r - i nd i um-

c a d m i u m a b s o r b e r ro d s . R e d u c e d s t re n g t h c o n t r o l r o d s c o m p o s e d o f s o l id

Inc one l p rov i de t he c a pa bi l i t y t o c ha nge ope ra t i ng powe r l e ve l u s i ng c on t ro l

rods o n l y . T hi s s impli fi e s r e a c t i v i t y c on t ro l du r i ng p l a n t l oa d c ha n ge s a n d

re duc e s l i qu i d wa s t e proc e s s i ng re qu i re me n t s t ha t no rma l l y a c c ompa ny

c h a n g e s i n s o l u b le b o r o n c o n c e n t r a ti o n .

L i k e p r e v i o u s A B B - C E r e a c t o r s , t h e R e a c t o r C o o l a n t S y s t e m ( R C S ) f o r

S y s te m 8 0 P l u s h a s t w o l o o p c o n f i g u r a t io n s . E a c h l o o p c o n s i s t s o f o n e h o t

leg,

o n e s t e a m g e n e r a t o r , t w o c o l d l e g s a n d t w o pu m p s .

A pre s s u r i ze r wit h a n i nc re a s e d vo l ume ( i n s pe c i fi c vo l ume , t he i nc re a s e

a m o u n t s t o 3 3

)

t o r e d u c e t h e p r e s s u r e c h a n g e s d u r i n g t r a n s i e n t s s u c h a s

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STUDSVIK ECO & SAFETY AB STU DSVlK/ES-95/10

1995-02-13

AEP5:2(4)

Schedule

reactor trip and load rejection. The increased secondary side water inventory

(by 25

%)

and heat transfer surface o f the steam generator are also aimed to

improved operating performance.

The most significant changes are in the engineering safety systems, in

particular, in the Safety Depressurization System (SDS) and in the Safety

Injection System (SIS). The SIS has been made simplier, more reliable and

the performance has been improved. It incorporates four-train safety

injection, an in-containment refuelling water storage tank, and direct vesse l

injection. The containment structure is a steel sphere enc losed in a cylindrical

concrete building. Gas turbines as a diverse A C source are used.

A P RA indicated a reduction in the risk of severe accidents b y tw o orders of

magnitude compared to that with previous system s.

No System 80 Plus plant has been ordered ye t The final d esign approval for

System 80 Plus was issued in 1994 . Also, construction of System 80 NPPs

with some S ystem 80 P lus design features is no w underway in the Republic

of Korea.

System 80 P lus Unit Design

Electrical output

Fuel assembly

Array

Number of fuel rods

Clad m aterial

Enrichment leve ls

Fuel outside diameter

Reactor core

Number of fuel assemblies

Core height (active fuel)

Core diameter

Reactor coolant system

Design pressure

Design temperature

Reactor inlet temperature

Reactor ou tlet temperature

Number of coolant pumps

Number of steam generators

1 3 4 5 M W e

16 x

236

16

Zircalov4

3.2,

2.8, 1.9 %

9.7 mm

24 1

3.81

3.65

170

343

291

323

4

2

m

m

bar

»C

°C

OC

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Nil MN\ ik H

M

S E C T I O N 1

S \ \ U ' I I 1 N i l | » l i

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S II PN\ Ik IS

S E C T I O N . ?

1

2

•}

•I.

5

B.

7

8.

9.

10.

11.

12.

13.

14.

15

16.

17.

16.

19.

20

21 .

22.

23.

24.

25

26 .

27.

26

29

Hp;n:Mr Ruling

Unit vi-ni

Slew t'nnl.immi'iit V H W .

Pul.v Cwm

CEA rlianyr» pMHcum

f.t«;nn Cituw^uloris

Main alPtiiTi pipBS

Sntfliy injm^tlon tanks

Hr*«S5irfiZöf.

CODITOI (jlemont clrivö moflumism

cnohng flciuipnien

Cont-ni olHnsnt dnvP nuichunisni

In-cof f dnvH mBctir»ni«,in.

Honclor vsssol

Dfltuoiiriq *a[ui storiigp lank

fl«aclnr cnnloni pumps

Sloam ponarntor sh'alc) wait

Fupl handhny hridge

Refueling canal.

Fuel transfer tube

Rpfltrtor drain tank.

In-cofi* initrunirtnlfll^on

Conlmnmen spray h ÂrJprs

f-eedwaier pipe.

Conlsmmflfit venitlaiion itnnltn.i tintis

Citarping pump.

Pipe cha»e.

Cahfs CIIÄSK find HVAC duel

SlMl-rtnwn cooling hea rt^chaniinr

30.

Furil Mflfi[(/ing iujriff-ntj

31 .

Cask hni i iHtnt} t : r; ine.

32.

Fil^l hrtntllini] Mndcii»

[ f^np

33,

Spflnl Kiei yoc

34. WatfT-ngiit g.iio

35 .

Tr/insf̂ r iwDe ymt» valve nini ro i whei»

38. Fupl Ctirrifigu

37 .

TftinsfBr sygiem winch

36. Caitfc araa

39. Fuit »tupping and reren/mg arHFi

40.

New fuel s fii«[)H nffla

41 , Ho'rt-up water stnrage tank

42 Rescior make-up water aiorage lank

43.

Main ?Iöam valvo onclosurt»

44 Ma;" îe.im isolation vafwoi»

4S. Wain slenm sa'eiv valves

46 .

Di«80 gener tiior

47-

Nupie* 8C + ' " ro nlrol rnivn

48 .

Computer room

49.

Conifol aröA HVAC Hjuipmoni

50. Turbin*» building

5). HP hirbma

52.

IP

turhinss

33. Qens rator

54 . AilflrrflK {exciier}

55.

Condensers

50. MolBluro separators

57 .

FW haafcra

58 .

Uppe' flurgft tanks.

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S T U D S V IK E C O & S A F E T Y A B S T U D S V I K /E S - 9 5 /1 0

1 9 9 5 - 0 2 - 1 3

A E P 6 : i ( 3 )

A E P 6

Format

Ti t l e


r e a c t o r





De s c r i p t i on


W E R - 1 0 0 0 ( V - 3 9 2 )

N P P

P W R

L a r g e p o we r /1 0 0 0 M W e

E D O H y d ro p re s s , R F


A n u m b e r o f a d v a n c e d \

w i t h a n e l e c t r ic o u t p u t 1 0 0 0 - 1 1 0 0 M W e a r e n o w u n d e r d e v e l o p m e n t in

E D O H y d r o p r e s s .

T he f o l lowi ng me a s u re s a i me d a t s a fe t y i mprove me n t i n c ompa r i s on wi t h

t he c o m m e r c i a l r e a c t o r p la n t V - 3 2 0 h a v e b e e n r e a l i z e d :

o

o

o

o

o

A d v a n c e d s t e a m g e n e r a t o r s w i th a la r g e w a t e r i n v e n t o r y

F ou r s a fe t y t ra i n de s i g n pr i nc i p l e

The re a c t o r c oo l a n t pump wi t h t he de s i gn o f s e a l i ngs

e xc l ud i ng t he i r l e a ks i n t he e ve n t o f l ong - t e rm bl a c kou t a nd

t he a bs e nc e o f s e a l i ng wa t e r s uppl y

R e a l i za t i on o f a d i a g no s t i c s ys t e m s e t a nd l e a k-bc f o re -bre a k

a pproa c h

A fi lt e re d do ubl e c on t a i nme n t wi t h re i n fo rc e me n t o f the f loo r

C on t a i nme n t f i l t e re d ve n t i ng s ys t e m

S ys t e m of r e t u rn i ng t he pr i ma ry c i r c u i t c oo l a n t

T he de s i gn l i f e ti me of t he pl a n t s ha s be e n i nc re a s e d up to

4 0 y e a r s .

T h e V - 3 9 2 a n d V - 4 1 3 a s w e ll a s t h e V - 3 2 0 c o m m e r c i a l r e a c t o r p la n t s

h a v e 4 h o r i zo n t a l s t e a m g e n e r a t o r s . T h e V - 4 1 0 v e r s i o n i n t r o d u c e s 4

v e r t i c a l s te a m g e n e r a t o r s .

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S T U D S V I K E C O

&

S A F E T Y A B S T U D S V n C /E S -9 5 /1 0

1 9 9 5 - 0 2 - 1 3

AEP6:2(3)

S c h e d u l e

A l l a d v a n c e d W E R - 1 0 0 0 r e a c t o r s u s e th e s a me fu e l r o d s ( d i a m e te r

9 . 1 m m a nd he i gh t 3 . 54 m ) a nd pra c t i c a l ly the s a me fue l a s s e mbl y de s i gn .

C o m p a re d w i t h V - 3 9 2 a n d V - 4 1 3 , t he l a te s t V - 4 1 0 v e r s io n h a s a d e c r e a s e d

v o l u m e t r i c c o r e p o w e r d e n s i t y ( fr o m a b o u t 1 1 0 t o a bo u t 8 5 K W / 1 ), i n c r e a s e d

R P V d i a m e te r a n d a s a r e s u lt r ed u c e d R P V n e u t r o n fl u e n c e.

T h e V - 4 1 3 v e r s i o n , d e v e l o p e d w i th F V O E n g i n e e r i n g I n t e r n a ti o n a l ( F i n l a n d )

i s b a s e d o n l y o n pr o v e n V - 3 2 0 s a fe ty s y st e m t e c h n o l o g y . T o i m p r o v e t h e

s a fe t y t h e V - 3 9 2 a n d V - 4 1 0 v e r s i o n s i n c o r p o r a t e a d d i t io n a l w a t e r

a c c u m u l a t o r s fo r e m e r g e n c y c o r e c o o l i n g a n d pa s s i v e r e s i d u a l h e a t r e m o v a l

s y s te m s v i a s t e a m g e n e r a t o r w i th a ir c o o l e r s o u t s i d e t h e c o n t a i n m e n t

N o a d v a n ce d W E R - 1 0 0 0 p l an t v e r s io n s h av e b ee n o rd e re d y e t T h e V - 4 1 3

v e r s i o n h a s b e e n o n e o f c o n t e n d e r s fo r N P P s i n F i n l a n d . E s p e c i a ll y fo r t h e

V-410 ve r s i on s i gn i f i c a n t ve r i f i c a t i on t e s t i ng a nd de t a i l e d de s i gn work

re ma i ns t o be done , p r i o r t o c omme rc i a l u t i l i za t i on .

VVE R-1000 Unit Data (V-392, V-413)

P r i ma ry pre s s u re

P r i ma ry t e mpe ra t u re

S e c o n d a r y p r e s s u r e

S t e a m t e m p e r a t u r e

N o m i n a l c o o l a n t fl o w r a t e

A ve ra g e l i ne a r he a t r a t i ng a t fue l e l e me n t s

H umi d i t y a t t he ou t l e t a t fu l l powe r

Numbe r o f c on t ro l me mbe rs

N umbe r o f a s s e mbl ie s

Ave ra ge f ue l bu rnup f ra c t i on , ( a t s t a t i ona ry

fuel cycle)

T i me of ope ra t i on a t r a t e d powe r f o r

a year (e ffec t ive )

1 5 7 b a r

3 2 0 ° C

6 3 b a r

2 7 8 ° C

8 8 0 0 0 m

3

ft

1 6 6 .7 W / c m

0 . 2 %

97

163

4 4 M W d / k g

7 0 0 0 h

R e f e re nc e s

F E D O R O V , V G e t a l

D e s i g n s o f a d v a n c e d V V E R - 1 0 0 0 r e a c t o r s .

P r o c e e d i n g s I n t e r n a t io n a l C o n f e re n c e o n D e s ig n a n d S a f e ty o f A d v a n c e d

N u c l e a r P o w e r P l a n t s , O c t 2 5 - 2 9 , 1 9 9 2 , T o k y o , J a p a n , v 4 , p

4 . 4 . 3 .

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S T U D S V I K / E S - 9 5 / 1 0

1 9 9 5 - 0 2 - 1 3

AEP6:3(3)

Pressurizer

/

e ̂

Figure AEP6

V - 4 1 0 : R e a c t o r c o o l a n t s y s t e m .

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S T U D S V n C E S - 9 5 / 1 0

1 9 9 5 - 0 2 - 1 3

AEP7:i(3)

AEP7

F o r m a t

T i t l e


r e a c t o r





De s c r i p t i on


E P R ( E u r o p e a n P r e s s u r iz ed W a t e r R e a c t o r )

N P P

P W R

L a r g e p o we r /1 5 0 0 M W e

S i e m e n s - K W U , G e r m a n y ; F r a m a t o m e , F r a

B a s i c d e s i g n

T h e E P R r e p r e s e n t s a n a d v a n c e d , e v o l u ti o n s

S c he du l e

h a s be e n d e v e l o p e d b y N u c l e a r P o w e r In t e r n a t i o n a l ( a c o m p a n y f o r m e d b y

F r a m a to m e a n d S i e m en s - K W U ) , ba s ed o n N 4 p la n t an d K W U - C o n v o y p la n t

d e s i g n s . T h e d e s i g n g o a l s f o r E P R i n c l u d e i m p ro v i n g fu n c t io n a l s a fe ty b y

s ys t e m de s i gn s i mpl i fi c a t ions , s t r e ng t he n i ng o f r e du nd a nc y by s t r i c t phys i c a l

s e p a r a t io n , e x t e n d i n g t h e g r a c e p e r io d ( u p t o 2 4 h ) b y a d d i t i o n a l a n d e n l a r g e d

wa t e r s t o ra ge c a pa c i t y . S pe c i a l a t t e n t i on i s g i ve n t o s e ve re a c c i de n t s i nvo l v i ng

c o r e m e l t c o r i u m s p r e a d i n g ; s t ro n g f u ll p r e s s u r e d o u b l e c o n t a i n m e n t fo r

m a r g i n s a n d n o n e e d fo r e a r ly he a t r e m o v a l fr o m c o n t a i n m e n t

The t he rma l powe r o f t he r e a c t o r i s 4 250 M W L T h e c o r e is b a s e d o n N 4

fu e l w it h 1 7 x 1 7 - 2 5 r o d s p e r a s s e mb ly . T h e c o r e c o n t r o l p ri n c i p l e s a r e

b a se d o n a c o m b in a t i o n o f t he S i e m e n s - K W U a n d F r a m a t o m e e x p e r i e n c e .

T h e c o n t a i n m e n t c o n s i s t s o f a p r e st re s s e d c o n c r e t e c y l in d e r w h i c h c a n b e

fi tt e d wi th a s t e el l i ne r . T o prov i de a d ua l wa l l c on t a i n me n t fun c t i on , t he

c o n t a i n m e n t i s s u r r o u n d e d b y a se c o n d n o n - p r e s tr e s s e d c o n c r e t e c y l i n d e r ,

f o rmi ng a n a nnu l a r s e c onda ry c on t a i nme n t S a f e t y s ys t e ms a re i n s t a l l e d i n a n

a n n u l a r b u i l d in g s u r r o u n d i n g t h e o u te r c o n t a i n m e n t . B o t h t h e r e a c t o r

bu i l d i ng a nd t he a nn u l a r bu i l d ing wi l l be bu i l t on t he s a me f oun da t i on ma t

( f o r s e i s mi c pro t e c t i on r e a s ons ) . S e pa ra t i on be t we e n t he f ou r s a f e t y d i v i s i ons

a n d o n e o p e ra t io n a l d i v i s io n i s ac c o m p li s he d i n a s e c to r a r r a n g e m e n t T h e

l owe r a re a o f t he c on t a i n me n t hous e s t he wa t e r s uppl y fo r t he s a f e ty

i n je c t ion s ys t e ms , t he i n -c on t a i nme n t r e fue l l ing wa t e r s t o ra g e t a n k .

T h e d e v e l o p m e n t o f t h e E P R h as n o t ye t be e n c o m p l e te d . F r e n c h a n d

Ge rma n a u t ho r i t i e s ha ve a g re e d upon t he ha rmon i za t i on o f l i c e ns i ng

r e q u i r e m e n t s . A c c o r d i n g t o t h e o v e ra ll t i m e s c h e d u l e , th e B a s i c D e s i g n s ha l l

be c ompl e t e d du r i ng 1995 wi t h a n a ppl i c a t i on f o r c ons t ruc t i on l i c e ns e

s c h e d u l e d f or t he e n d o f 1 9 9 5 . T h e ta r g e t c o n s t r u c t io n d a t a f o r F O A K E i s

1 9 9 8 .

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S T U D S V I K / E S - 9 5 / 1 0

1 9 9 5 - 0 2 - 1 3

A E P 7 : 3 ( 3 )

Figure AEP7

E P R : C o n t a i n m e n t b u i l d i n g .

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S T U D S V I K / E S - 9 5 / 1 0

1 9 9 5 - 0 2 - 1 3

A E B l : i ( 3 )

A E B 1

Format

Ti t l e

A ppli c a t i on o f t he

r e a c t o r


P o w e r o u t pu t



De s c r i p t i on

Description

A B W R

N P P

B W R

L a r g e p o w e r / 1 3 5 6 M W e

G e n e r a l E l e c t r i c , U S ; H i t a c h i / T o s h i b a T o k y o E l e c t r i c P o w e r C o ( T e p c o ) ,

J a pa n

C o m m e r c i a l

T h e A B W R w i th th e t he r m a l po w e r o u t p u t o f 3 9 2 6 M W t is a c o m b i n e d

a ppli c a t ion o f t he t e c hn i c a l s o l u t i ons a l r e a dy prove n i nd i v i du a l l y in d i ffe re n t

B W R s . T h e ma in f ea t u re s o f th e A B W R a r e :

o A d v a n c e d fu e l a n d c o r e d e s i g n

o In t e rna l r e c i r c u l a t i on pum ps , a t t he bo t t om of t he c o re

o D e c r e a s e d h yd r a u l i c r e s i s ta n c e o f R C S . L o w e r r e c i r c u l a ti o n

fl ow pumpi ng powe r

o F i ne mot i on c on t ro l rod d r i ve s wi t h d i ve r s i f ie d s c ra m a c t ua t i on

(hydra u l i c p i s t on d r i ve + e l e c t r i c mot o r d r i ve ba c kup)

o D i g i t a l a nd s o l id s t a te c on t ro l

o Mul t i p l e x i ng

o I m p ro v e d r e i n fo r c e d c o n c r e t e p r im a r y r e a c t o r c o n t a i n m e n t a n d

re a c t o r bu i l d i ng

o

T h r e e e m e r g e n c y c o r e c o o l i n g s y s t e ms ( E C C S ) d i v i s io n s .

The c o re a nd fue l d e s i gns a i m a t i mprov i ng ope ra t i ng e f fi c i e nc y, o pe ra b il i ty

a nd f ue l e c onomy by me a ns o f P C I (P e l l e t C l a d In t e ra c t i on ) - re s i s t a n t f ue l ,

a x i a l l y - zone d e n r i c hme n t , c on t ro l c e l l c o re de s i gn a nd i nc re a s e d c o re f l ow

c a pa bi l i ty . The l a t t e r a l l ows f o r hydra u l i c s pe c t ra l s hi ft ope ra t i on t o prov i de

a d d i t i o n a l b u r n u p t o w a r d s t h e e n d o f t he o p e r a t in g c y c l e . T h e r e a c t o r

p r e s s u r e v e s s e l h a s be e n d e s i g n e d t o r e d u c e t h e n u m b e r o f w e ld s a n d t o

ww victor/AEB 1

ea

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S T U D S V n C / E S - 9 5 / 1 0

1 9 9 5 -

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