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Title: Verification of the CASMO-4 transport method based on BWR high-burnup 9 x 9 fuel critical experiments

Abstract

Fuel designs for boiling water reactors (BWRs) have become far more heterogeneous owing to the high-burnup design and the improvements in the thermal hydraulics. The current generation of BWR fuel designs may contain complicated geometries; for instance, GE-11-type fuel design contains several partial length rods and a large island of water in the center of the 9 x 9 assembly. The characteristics method that has been introduced to CASMO-4 as a new transport method is expected to offer very accurate solutions of the neutron flux distributions for heterogeneous geometries. Although some numerical tests for BWR lattices, containing the 9 x 9 lattice, were performed against Monte Carlo results and advantages of the new method have been indicated, the straightforward verification test of this method to the 9 x 9 lattice based on the critical experiments is desirable. This paper presents the CASMO-4 benchmarking results for pin powers against critical experiments using BWR 9 x 9 (A-type fuel).

Authors:
;  [1];  [2]
  1. Toden Software Inc., Tokyo (Japan)
  2. Tokyo Electric Power Company, Tokyo (Japan)
Publication Date:
OSTI Identifier:
411755
Report Number(s):
CONF-951006-
Journal ID: TANSAO; ISSN 0003-018X; TRN: 97:001000
Resource Type:
Journal Article
Journal Name:
Transactions of the American Nuclear Society
Additional Journal Information:
Journal Volume: 73; Conference: Winter meeting of the American Nuclear Society (ANS), San Francisco, CA (United States), 29 Oct - 1 Nov 1995; Other Information: PBD: 1995
Country of Publication:
United States
Language:
English
Subject:
21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS; BWR TYPE REACTORS; FUEL ASSEMBLIES; REACTOR LATTICES; C CODES; DESIGN; BURNUP; HYDRAULICS; NEUTRON FLUX; BENCHMARKS

Citation Formats

Terazu, Kuninobu, Saji, Etsuro, and Arai, Shiro. Verification of the CASMO-4 transport method based on BWR high-burnup 9 x 9 fuel critical experiments. United States: N. p., 1995. Web.
Terazu, Kuninobu, Saji, Etsuro, & Arai, Shiro. Verification of the CASMO-4 transport method based on BWR high-burnup 9 x 9 fuel critical experiments. United States.
Terazu, Kuninobu, Saji, Etsuro, and Arai, Shiro. Sun . "Verification of the CASMO-4 transport method based on BWR high-burnup 9 x 9 fuel critical experiments". United States.
@article{osti_411755,
title = {Verification of the CASMO-4 transport method based on BWR high-burnup 9 x 9 fuel critical experiments},
author = {Terazu, Kuninobu and Saji, Etsuro and Arai, Shiro},
abstractNote = {Fuel designs for boiling water reactors (BWRs) have become far more heterogeneous owing to the high-burnup design and the improvements in the thermal hydraulics. The current generation of BWR fuel designs may contain complicated geometries; for instance, GE-11-type fuel design contains several partial length rods and a large island of water in the center of the 9 x 9 assembly. The characteristics method that has been introduced to CASMO-4 as a new transport method is expected to offer very accurate solutions of the neutron flux distributions for heterogeneous geometries. Although some numerical tests for BWR lattices, containing the 9 x 9 lattice, were performed against Monte Carlo results and advantages of the new method have been indicated, the straightforward verification test of this method to the 9 x 9 lattice based on the critical experiments is desirable. This paper presents the CASMO-4 benchmarking results for pin powers against critical experiments using BWR 9 x 9 (A-type fuel).},
doi = {},
journal = {Transactions of the American Nuclear Society},
number = ,
volume = 73,
place = {United States},
year = {1995},
month = {12}
}