advanced passive pwr radwaste minimization technology€¦ · as an advanced passive pwr, cap1400...

www.snerdi.com.cn

Advanced Passive PWR Radwaste Minimization Technology

2019. 06. 19

Shanghai Nuclear Engineering Research & Design Institute Co.LTD.

知识产权声明

本文件的知识产权属国家电力投资集团公司及其相关产权人所有，并含有其保密信息。对本文件

的使用及处置应严格遵循获取本文件的合同及约定的条件和要求。未经国家电力投资集团公司事

先书面同意，不得对外披露、复制。

Intellectual Property Rights Statement

This document is the property of and contains proprietary information owned by SPIC and/or its related

proprietor. You agree to treat this document in strict accordance with the terms and conditions of the

agreement under which it was provided to you. No disclosure or copy of this document is permitted

without the prior written permission of SPIC.

2

1. Overview of CAP1400 & Radwaste Minimization Principle

2. Waste Volume Reduction Process for SRTF

3. Future Development

Contents


Based of domestic PWR nuclear power technology R&D and engineering experience

for 50 years in China, China’s safe construction and operation experience of 44 units

in 20 years, whole assimilation and absorption of AP1000 Technology by organizing

all related Chinese enterprises.

As an Advanced Passive PWR,

CAP1400 is a National Key

Project of China!


Major ConcernBetter Safety

Better Economy

Friendly Environment


Guide Target

US, URD 50m3/unit*yrRadwaste Package for 1000MW NPP

EU, EUR 50m3/unit*yrRadwaste Package for 1000MW NPP

China, HAD 401/08 Nuclear Facility Radwaste Minimization

Radwaste Package ALARA compared with Best Practice worldwide

Radwaste Minimization provide a measurable target for Friendly Environment PWR.

In order to achieve this goal,

Available & Economy

management is required.


Radwaste Minimization

Source

Control

Less fuel defect

Water chemical

control

Material control

Technology

Innovation

Less

maintenance

Less secondary

waste

Common mode

Radwaste

Reduction

Activity ALARA

Volume ALARA

Green

Manufacturing

Less

consumption

Less discharge

Exemption &

Clearance

Excluded from radiation

regulation

Recycling

Economy

Waste Reuse

Easy to

Decommission

Design Operation Decommission




Contents

1. Overview of SRTF Waste Treatment Process

Chinese new nuclear power plants

follow the international nuclear power

waste treatment mode, simplifying the

nuclear island waste treatment process,

and treat the wastes (such as dry and

wet solid wastes) which are suitable for

central ized treatment in an Site

Radwaste Treatment Facility (SRTF)

s h a r e d b y t h e w h o l e p l a n t t o

complement the processing capabilities.

NI（Single Unit）

SRTF（Shared in Site）

Chemical liquid waste（heat pump evaporation+dry）

Spent resin、Spent filter、mixed waste（sorting、dry、super-

compaction、grouting）

◆ Complete waste treatment process

◆ Waste Volume Reduction

Interim storage、laundry

Gas waste（delay decay）

Liquid waste（filtration+flocculation+ion

exchange）

Solid waste（collection and 和temporary storage）

SRTF waste stream interface table

Waste stream

Producing

(collecting)

area

Transportation

destination

In-plant transfer

method

Normal condition

Spent filter NI Auxiliary building Shielded transfer cask

Spent resin NI Auxiliary building Shielded transfer cask

Chemical liquid waste NIRadioactive waste

buildingShielded transfer cask

HVAC filter NIRadioactive waste

buildingTransport truck

Compactable/ non-

Compactable wasteNI

Radioactive waste

buildingShielded transfer cask

Abnormal condition

Secondary circuit radioactive

sewageCI

Production wastewater

treatment building

Mobile treatment

device


Schematic diagram of waste treatment process

Spent filter

Spent resin

Chemical liquid

waste

HVAC filter

Compactable waste

Non-compactable

waste

receive &

transfer

pre-shred &

compact

Sort & pre-

compact

sort

vacuum dry

Evaporate &

In-drum dry

Super-compact

Overpack optimize

grout

Multi-drum dry

temporary storage

receive &

transfer

receive &

transfer


Main Waste Volume Reduction Process

2. Main Waste Volume Reduction Process for SRTF

Spent resin1 NI building Shielded transfer device Vacuum dryer

SRTF building

Disposal

Concrete HIC Grouting device Super-compactor

Interim storage

Spent

resin

2 Chemical liquid waste


NI building Shielded transfer

SRTF building

Disposal

Concrete HIC Super-compactor In-drum dryer

Interim storage Grouting device

Chemical liquid waste

Heat pump evaporator

3 Compactable waste


NI building Sorting box

SRTF building

Transport truck

Super-compactor 12-drum dryer

Grouting device

Interim storage

Disposal

Compactable waste

Waste volume reduction effect list

Waste streamVolume reduction ratio of

each step

Total volume reduction

ratio (in-plant package)

Spent resin

dry：1.5

super-compact：1.25

grout：0.75

1.41


evaporate & dry：100

super-compact：1

grout：0.75

75

HAVC filter

extrude & pre-compact：1.4

super-compact：5.7

grout：0.75

6

Compactable waste

sort & pre-compact：1.5

super-compact：4

grout：0.75

4.5


The waste package formed by SRTF has the characteristics of good volume reduction

effect and stable physical and chemical properties. It is suitable for near-surface disposal

and has a very positive effect on reducing the pressure and cost of radioactive waste

disposal in nuclear power plants

Cement

solidification

Super-

compaction

Spent resin processing

capacity（6 units）80m3

Volume increase ratio 约2.5 0.71

Waste package production per year 1000 drums* 285 drums*

Comparison of waste package produced by two resin

treatment processes


Note: * by 200L drum

SRTF adopts waste volume reduction process such as drying and compaction to control

the volume of solid waste generated by a single unit below 50 m3/a, meeting the

requirements of waste minimization according to URD.


Waste stream

Expected amount of

waste generated per year(6 units)

Primary treatment

Secondary treatment

Grout

Expected amount of 200L drums generated per year(6 units)

Volume reduction

ratio

Specific radioactivity of waste package

Spent filter 36Fill in 200L

drum× Y 36 1 2.97E+10Bq/kg

HVAC filter 118（13.3m3）

Pre-shred, pre-compact & fill in 160L

drum

Super-compact

y 19 6 1.94E+04Bq/kg

Compactable waste

780.9m3

Sort, pre-compact & fill in 160L

drum

Super-compact

Y 868 4.5 2.25E+05Bq/kg

Non-compactable

waste40.62 m3 Sort & fill in

200L drum× Y 214 0.95 9.5E+04Bq/kg

Spent resin 80.04 m3 DrySuper-

compactY 285 1.41 4.09E+10Bq/kg


124.46 m3 Evaporate & dry in drum

Super-compact

Y 4 75 1.08E+08Bq/kg

Expected amount of 200L drums generated by 6 units each year is about 1431 with an average of 239 drums per unit.Thus the expected volume of solid waste generated by a single unit is about 48m3/a.

Standards and specifications compliance

Meet all the National StandardsHAF401-1997 放射性废物安全监督管理规定

HAD003/06-1986 核电厂设计中的质量保证

HAD102/12-1990 核电厂辐射防护设计

HAD401/01-1990 核电厂放射性排出流和废物管理

HAD401/02-1997 核电厂放射性废物管理系统的设计

HAD401/04-1998 放射性废物的分类

HAD401/08-2016 核设施放射性废物最小化

GB 6249-2011 核电厂环境辐射防护规定

GB 9132-1988 低中水平放射性固体废物的浅地层处置规定

GB 9133-1995 放射性废物的分类

GB 9134-1988 轻水堆核电厂放射性固体废物处理系统技术规定

GB 9135-1998 轻水堆核电厂放射性废液处理系统技术规定

GB 11806-2004 放射性物质安全运输规程

GB 12711-1991 低、中水平放射性固体废物包装安全标准

GB 14500-2002 放射性废物管理规定

GB 14587-2011 轻水堆核电厂放射性废水排放系统技术规定

GB 14589-1993 核电厂低、中水平放射性固体废物暂时贮存技术规定

GB 16933-1997 放射性废物近地表处置的废物接收准则

GB 18871-2002 电离辐射防护与辐射源安全基本标准

EJ 1042-2014 低、中水平放射性固体废物容器钢桶

EJ 1186-2005 放射性废物体和废物包的特性鉴定

⚫ Waste package meets therequirements of standards andspecifications.

⚫ Final disposal with concrete highintegrity containers of 300-yearservice life .

⚫ Spent resin adopts a hotsuper-compaction process,and the volume reductionratio can reach 1.4.

⚫ Chemical liquid waste adoptsan evaporative drying process,and the volume reductionratio can reach 75.

Disposal（ GB 9132 ,GB 12711）

Waste minimization（ HAD 401/08）

1

3. SRTF Process Maturity & Equipment Development

Up to now SRTF engineering application conditions obtained

Process maturity2


SRTF of built NPPs Sanmen, Tianwan

SRTF of new NPPs Xiapu, Lufeng, Xudapu

The main process of CAP1400 SRTF is widely recognized and applied

in China.

Main Equipment R&D completed and Industry certificated by China National Science and Technology Major Project.


Spent Resin Vacuum Dryer Small-scale heat pump evaporator

Shield Transfer Device In-drum drying device

The goal of minimizing waste is that annual waste

package volume is no more than 50m3/yr.

The volume reduction processes of SRTF based on drying

and compaction have good waste reduction capacity and are

mature and reliable, meeting the requirements of standards

and specifications.

4. Conclusion




Contents


Further

Waste Minimization

Zero Discharge Disposal Safety

Source control

Radwast disposal and decommission

-Dispoal container R&D

-Disposal site design

-Design optimazation for docommission

NI radwaste system design

Site radwaste facility design

Tritium liquid treatment

Non-radwaste treatment(e.g. Boron)

Radwaste

Minimization

1. Liquid Radwaste minimization

2. Gaseous Radwaste minimization

3. Solid radwaste minimization

4. Total radwaste minimization

5. Economical efficiency

6. Dose-rate minimization

7. Automatic control optimization

8. Energy consumption optimization

9. Layout optimization

10. reliability optimization


Further

Waste Minimization

Fluidized bed steam reforming

PVA Fenton

Plasma melting

Wet oxidation

Incinerator

New Technology

In the study


EXAMPLE:

Fluidized bed steam reforming

Investment

SRTF Compared with new Tech (steam reforming)

4亿

3.5亿

SRTF current

SRTF new

Building AreaVR resin

6

1.4

VR DAW

25

4.5

Treat Oil

Yes

No

Waste Vol/un*a

48m3

31.8m3

Disposal Cost

17.5亿

11.5亿

3100m2

3000m2

Note: Based on 6 units & 60 years; disposal rate 100000RMB/m3


Zero Discharge

New Multipurpose nuclear reactor (ex: Heating)• Closer to the city• Lower environmental release

Primary Effluent

DegasHoldup

Tank

Holdup Tank

Floor Drain

Filter+IX+Membrane

Filter+IX+Membrane

CVS Makeup

Primary Loop

Reuse Water Tank

SFP Makeup

Equipment Flush

✓ After treatment reuse water＜ 30Bq/L

✓ 100% water recycle in NPP✓ Zero Liquid Discharge to

environment✓ Tritium impoverishment rate ＞50

Tritiumseparation


Disposal Safety

Longer Life, More Stability and Safer Drop simulation analysis and test

⚫ High performance concrete recipe

⚫ Container shielded surface dose rate ≤ 10mSv/h

as an Off-site container

⚫ Resistance to fall during transportation

⚫ Blocking nuclide diffusion

⚫ 300 year lifetime container provide safer condition and less requirement for disposal

site and engineering structures

⚫ Now Concrete HIC R&D completed and would be applied soon for China near-

surface disposal facility to improve disposal safety

Concrete High Integrity Container（HIC）

谢谢！THANK YOU !

www.snerdi.com.cn

advanced passive pwr radwaste minimization technology€¦ · as an advanced passive pwr, cap1400...

Documents