astm and tmsr irradiation program
DESCRIPTION
ASTM and TMSR irradiation program. Derek Tsang SINAP. 20 .09.2013. Introduction. SINAP has a irradiation program to get i -data for material used in molten sal t reactors. Metal and graphite ASTM standards will be used in all the material properties measurement. - PowerPoint PPT PresentationTRANSCRIPT
钍基熔盐核能系统
ASTM and TMSR irradiation program
Derek TsangSINAP
20.09.2013
Introduction SINAP has a irradiation program to get i-data for
material used in molten salt reactors. Metal and graphite ASTM standards will be used in all the material
properties measurement. Irradiation temperature is 650℃ Max dose for metal is 2.5×1019 n/cm2( E >
0.1MeV) Max dose for graphite is 5×1020 n/cm2( E >
0.1MeV)
Metal irradiation program Total samples = 136 Samples for irradiation = 46
Properties ASTMHardness ASTM E18-12, E10-12Fatigue ASTM E606/E606M-12
Charpy impact test ASTM E23-12Modulus and Poisson's ratio ASTM E111-04, ASTM E132-04
Tensile test ASTM E8/E8M-09, ASTM E21-09
Alloy System
Corrosion Evaluation
Property Evaluation
Forming and Welding process
High cycle fatigue life
Low cycle fatigue life & Fracture toughness
Creep & Rupture & Impact
Oxidation evaluation
Thermal Stability & Thermal fatigue
Neutron irradiation properties
Corrosion specification
Corrosion verification
Corrosion performance of weldment
Corrosion calculation
Gas tungsten arc welding process
High energy beam welding process
Makeup and Repair & Stress evaluation
Pipe and Fittings process
Elbow and Drum process
Bending and Stamping process
Technical specification
Corrosion evaluation
Zhijun li
Guojun Yu
Jianping Liang
Li jiang
Bomou Zhou
Guangzhou Yuan
Yanling Lu
Fenfen Han
Li & Yan
Guojun Yu
Jingfeng Yang
Hua Sun
Juan Hou
Hua Ai
Shuangjian Chen
Kun Yu
Chaowen Li
Jianping Liang
Yongfeng Zhou
Xiaoke Li
Ye Zhang
Zhijun li
Tension and Impact Lab Creep and Rupture Lab
Fatigue Lab
Heat Treatment Lab
Metallographic Preparation Lab
Hardness Tester and Microscope
Mechanical Properties Platform
Lab Introduction-1
Other Analytical Instrument
Lab Introduction-2
Corrosion Lab
6
Thermal Properties Lab Microscope and Photometer
TEM石墨样品制备实验室
Welding Lab
Graphite irradiation program Total samples = 312 Samples for irradiation = 94 + 94
Properties ASTM no. of samplesThermal diffusivity ASTM C714 16+16
Specific heat capacity ASTM E1269 16+16Bulk Density ASTM C559 16+16
Young's modulus ASTMC769 16+16Flexural strength ASTM C651 16+16Tensile strength ASTM D3967 30+30
Compressive strength ASTM C695 16+16CTE ASTM E228 16+16
Tensile strength Tensile strength sample size in ASTM is
too big for our irradiation program D3967 is for rock tensile strength Underestimate graphite tensile strength More experiment and
analytical/numerical studies. New ASTM standard for graphite tensile
strength?
DYM or SYM Gas cooled reactor: gas has no
mechanical effect on graphite. May not be true for molten salt reactor. 3 ways to do graphite irradiation
experiment for molten salt reactorsA. Not consider molten salt at allB. Graphite samples in a container with molten
salt and irradiate together.C. Force molten salt into graphite samples
before irradiation experiment.
Standard requires no liquid inside the samples!
After irradiation experiment to measure DYM at what temperature? High DYM at room temperature Virgin DYM at high temperature
Virgin graphite with molten salt
Virgin graphite without molten salt
Some thoughts ASTM Standards mainly for nuclear
graphite in gas cooled reactor. Nuclear graphite in molten salt reactor
may need NEW ASTM standards???
Thank you!