Scale-4 analysis of pressurized water reactor critical configurations: Volume 5, North Anna Unit 1 Cycle 5
- Oak Ridge National Lab., TN (United States)
- Power Reactor and Nuclear Fuel Development Corp., Tokyo (Japan)
ANSI/ANS 8.1 requires that calculational methods for away-from- reactor (AFR) criticality safety analyses be validated against experiment. This report summarizes part of the ongoing effort to benchmark AFR criticality analysis methods using selected critical configurations from commercial PWRs. Codes and data in the SCALE-4 code system were used. This volume documents the SCALE system analysis of one reactor critical configuration for North Anna Unit 1 Cycle 5. The KENO V.a criticality calculations for the North Anna 1 Cycle 5 beginning-of-cycle model yielded a value for k{sub eff} of 1. 0040{+-}0.0005.
- Research Organization:
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- Sponsoring Organization:
- USDOE Office of Civilian Radioactive Waste Management, Washington, DC (United States)
- DOE Contract Number:
- AC05-96OR22464
- OSTI ID:
- 409924
- Report Number(s):
- ORNL/TM-12294/V5; ON: DE97050435; TRN: 97:001269
- Resource Relation:
- Other Information: PBD: Oct 1996
- Country of Publication:
- United States
- Language:
- English
Similar Records
Scale-4 Analysis of Pressurized Water Reactor Critical Configurations: Volume 5 - North Anna Unit 1 Cycle 5
Scale-4 Analysis of Pressurized Water Reactor Critical Configurations: Volume 1-Summary
Scale-4 Analysis of Pressurized Water Reactor Critical Configurations: Volume 4-Three Mile Island Unit 1 Cycle 5
Technical Report
·
Fri Jan 01 00:00:00 EST 1993
·
OSTI ID:409924
Scale-4 Analysis of Pressurized Water Reactor Critical Configurations: Volume 1-Summary
Technical Report
·
Sun Jan 01 00:00:00 EST 1995
·
OSTI ID:409924
Scale-4 Analysis of Pressurized Water Reactor Critical Configurations: Volume 4-Three Mile Island Unit 1 Cycle 5
Technical Report
·
Sun Jan 01 00:00:00 EST 1995
·
OSTI ID:409924