Development program of LOCA licensing calculation capability with RELAP5-3D in accordance with appendix K of 10 CFR 50.46

Citation
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
Citations number
5
Categorie Soggetti
Nuclear Emgineering
Journal title
NUCLEAR TECHNOLOGY
ISSN journal
00295450 → ACNP
Volume
133
Issue
3
Year of publication
2001
Pages
355 - 358
Database
ISI
SICI code
0029-5450(200103)133:3<355:DPOLLC>2.0.ZU;2-8
Abstract
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.