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Title: Scale-4 analysis of pressurized water reactor critical configurations: Volume 5, North Anna Unit 1 Cycle 5

Abstract

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.

Authors:
 [1];  [2]
  1. Oak Ridge National Lab., TN (United States)
  2. Power Reactor and Nuclear Fuel Development Corp., Tokyo (Japan)
Publication Date:
Research Org.:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Sponsoring Org.:
USDOE Office of Civilian Radioactive Waste Management, Washington, DC (United States)
OSTI Identifier:
409924
Report Number(s):
ORNL/TM-12294/V5
ON: DE97050435; TRN: 97:001269
DOE Contract Number:  
AC05-96OR22464
Resource Type:
Technical Report
Resource Relation:
Other Information: PBD: Oct 1996
Country of Publication:
United States
Language:
English
Subject:
21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS; 05 NUCLEAR FUELS; NORTH ANNA-1 REACTOR; REACTOR CORES; CRITICALITY; SPENT FUELS; REACTOR PHYSICS; CALCULATION METHODS; MULTIPLICATION FACTORS

Citation Formats

Bowman, S M, Suto, T, and Oak Ridge National Lab., TN. Scale-4 analysis of pressurized water reactor critical configurations: Volume 5, North Anna Unit 1 Cycle 5. United States: N. p., 1996. Web. doi:10.2172/409924.
Bowman, S M, Suto, T, & Oak Ridge National Lab., TN. Scale-4 analysis of pressurized water reactor critical configurations: Volume 5, North Anna Unit 1 Cycle 5. United States. https://doi.org/10.2172/409924
Bowman, S M, Suto, T, and Oak Ridge National Lab., TN. 1996. "Scale-4 analysis of pressurized water reactor critical configurations: Volume 5, North Anna Unit 1 Cycle 5". United States. https://doi.org/10.2172/409924. https://www.osti.gov/servlets/purl/409924.
@article{osti_409924,
title = {Scale-4 analysis of pressurized water reactor critical configurations: Volume 5, North Anna Unit 1 Cycle 5},
author = {Bowman, S M and Suto, T and Oak Ridge National Lab., TN},
abstractNote = {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.},
doi = {10.2172/409924},
url = {https://www.osti.gov/biblio/409924}, journal = {},
number = ,
volume = ,
place = {United States},
year = {Tue Oct 01 00:00:00 EDT 1996},
month = {Tue Oct 01 00:00:00 EDT 1996}
}