Tks. Liang et Rr. Schultz, Development program of LOCA licensing calculation capability with RELAP5-3D in accordance with appendix K of 10 CFR 50.46, NUCL TECH, 133(3), 2001, pp. 355-358
In light water reactors, particularly the pressurized water reactors, the s
everity of loss-of-coolant accidents (LOCAs) will limit how high the reacto
r power can extend. Although the best estimate LOCA methodology can provide
the greatest margin on the peak cladding temperature (PCT) evaluation duri
ng LOCA, it will take many more resources to develop and to get final appro
val from the licensing authority. Instead implementation of evaluation mode
ls required by Appendix K of the Code of Federal Regulations, Title 10, par
t 50 (10 CFR 50), upon an advanced ther mal-hydraulic platform can also gai
n significant margin on the PCT calculation. A program to modify RELAP5-3D
in accordance with Appendix K of 10 CFR 50 was launched by the Institute of
Nuclear Energy Research, Taiwan, and it consists of six sequential phases
of work. The compliance of the current RELAP5-3D with Appendix K of 10 CFR
50 has been evaluated, and it was found that there are II areas where the c
ode modifications are required to satisfy the requirements set forth in App
endix K of 10 CFR 50. To verify and assess the development of the Appendix
K version of RELAP5-3D, nine kinds of separate-effect experiments and six s
ets of integral-effect experiments will be adopted. Through the assessments
program, all the model changes will be verified.