Void Fraction Distribution in BWR Fuel Assembly and Evaluation of Subchannel Code

Akira Inoue, Tatsuo Kurosu, Toshimasa Aoki, Makoto Yagi, Toru Mitsutake, Shinichi Morooka

研究成果: Article

4 引用 (Scopus)

抄録

Void fraction measurement tests for BWR fuel assemblies have been conducted as part of a Japanese national project. The aim was to verify the current BWR void fraction prediction method. Void fraction was measured using an X-ray CT scanner. This paper describes typical results of void fraction distribution measurements and compares subchannel-averaged void fraction data with current subchannel analysis codes. The subchannel analysis codes COBRA/BWR and THERMIT-2 were used in this comparison. The agreement between data for an actual BWR fuel assembly with two unheated rods was good, but in the case of many unheated rods, the codes were unable to predict well large void fraction gradient in the radial direction observed in the measured data over the unheated rod region. The prediction errors of COBRA/BWR and THERMIT-2 for the subchannel-averaged void fraction were ¼A¾ (average of difference between measurement and calculation)=-1.1%, σ (standard deviation)=5.3% and ¼A¾=-2.2%, σ= 6.3%, respectively.

元の言語English
ページ(範囲)629-640
ページ数12
ジャーナルJournal of Nuclear Science and Technology
32
発行部数7
DOI
出版物ステータスPublished - 1995
外部発表Yes

Fingerprint

Void fraction
voids
assembly
evaluation
rods
predictions
assemblies
scanners
standard deviation
X rays
gradients

ASJC Scopus subject areas

  • Nuclear and High Energy Physics
  • Nuclear Energy and Engineering

これを引用

Void Fraction Distribution in BWR Fuel Assembly and Evaluation of Subchannel Code. / Inoue, Akira; Kurosu, Tatsuo; Aoki, Toshimasa; Yagi, Makoto; Mitsutake, Toru; Morooka, Shinichi.

:: Journal of Nuclear Science and Technology, 巻 32, 番号 7, 1995, p. 629-640.

研究成果: Article

Inoue, Akira ; Kurosu, Tatsuo ; Aoki, Toshimasa ; Yagi, Makoto ; Mitsutake, Toru ; Morooka, Shinichi. / Void Fraction Distribution in BWR Fuel Assembly and Evaluation of Subchannel Code. :: Journal of Nuclear Science and Technology. 1995 ; 巻 32, 番号 7. pp. 629-640.
@article{a74e929b593e4edc87eb2c0af6e84804,
title = "Void Fraction Distribution in BWR Fuel Assembly and Evaluation of Subchannel Code",
abstract = "Void fraction measurement tests for BWR fuel assemblies have been conducted as part of a Japanese national project. The aim was to verify the current BWR void fraction prediction method. Void fraction was measured using an X-ray CT scanner. This paper describes typical results of void fraction distribution measurements and compares subchannel-averaged void fraction data with current subchannel analysis codes. The subchannel analysis codes COBRA/BWR and THERMIT-2 were used in this comparison. The agreement between data for an actual BWR fuel assembly with two unheated rods was good, but in the case of many unheated rods, the codes were unable to predict well large void fraction gradient in the radial direction observed in the measured data over the unheated rod region. The prediction errors of COBRA/BWR and THERMIT-2 for the subchannel-averaged void fraction were ¼A¾ (average of difference between measurement and calculation)=-1.1{\%}, σ (standard deviation)=5.3{\%} and ¼A¾=-2.2{\%}, σ= 6.3{\%}, respectively.",
keywords = "accuracy, BWR type reactors, comparative analysis, experimental data, fuel assemblies, subchannel analysis code, two-phase flow, void fraction, X-ray CT scanner",
author = "Akira Inoue and Tatsuo Kurosu and Toshimasa Aoki and Makoto Yagi and Toru Mitsutake and Shinichi Morooka",
year = "1995",
doi = "10.3327/jnst.32.629",
language = "English",
volume = "32",
pages = "629--640",
journal = "Journal of Nuclear Science and Technology",
issn = "0022-3131",
publisher = "Atomic Energy Society of Japan",
number = "7",

}

TY - JOUR

T1 - Void Fraction Distribution in BWR Fuel Assembly and Evaluation of Subchannel Code

AU - Inoue, Akira

AU - Kurosu, Tatsuo

AU - Aoki, Toshimasa

AU - Yagi, Makoto

AU - Mitsutake, Toru

AU - Morooka, Shinichi

PY - 1995

Y1 - 1995

N2 - Void fraction measurement tests for BWR fuel assemblies have been conducted as part of a Japanese national project. The aim was to verify the current BWR void fraction prediction method. Void fraction was measured using an X-ray CT scanner. This paper describes typical results of void fraction distribution measurements and compares subchannel-averaged void fraction data with current subchannel analysis codes. The subchannel analysis codes COBRA/BWR and THERMIT-2 were used in this comparison. The agreement between data for an actual BWR fuel assembly with two unheated rods was good, but in the case of many unheated rods, the codes were unable to predict well large void fraction gradient in the radial direction observed in the measured data over the unheated rod region. The prediction errors of COBRA/BWR and THERMIT-2 for the subchannel-averaged void fraction were ¼A¾ (average of difference between measurement and calculation)=-1.1%, σ (standard deviation)=5.3% and ¼A¾=-2.2%, σ= 6.3%, respectively.

AB - Void fraction measurement tests for BWR fuel assemblies have been conducted as part of a Japanese national project. The aim was to verify the current BWR void fraction prediction method. Void fraction was measured using an X-ray CT scanner. This paper describes typical results of void fraction distribution measurements and compares subchannel-averaged void fraction data with current subchannel analysis codes. The subchannel analysis codes COBRA/BWR and THERMIT-2 were used in this comparison. The agreement between data for an actual BWR fuel assembly with two unheated rods was good, but in the case of many unheated rods, the codes were unable to predict well large void fraction gradient in the radial direction observed in the measured data over the unheated rod region. The prediction errors of COBRA/BWR and THERMIT-2 for the subchannel-averaged void fraction were ¼A¾ (average of difference between measurement and calculation)=-1.1%, σ (standard deviation)=5.3% and ¼A¾=-2.2%, σ= 6.3%, respectively.

KW - accuracy

KW - BWR type reactors

KW - comparative analysis

KW - experimental data

KW - fuel assemblies

KW - subchannel analysis code

KW - two-phase flow

KW - void fraction

KW - X-ray CT scanner

UR - http://www.scopus.com/inward/record.url?scp=85007815882&partnerID=8YFLogxK

UR - http://www.scopus.com/inward/citedby.url?scp=85007815882&partnerID=8YFLogxK

U2 - 10.3327/jnst.32.629

DO - 10.3327/jnst.32.629

M3 - Article

AN - SCOPUS:85007815882

VL - 32

SP - 629

EP - 640

JO - Journal of Nuclear Science and Technology

JF - Journal of Nuclear Science and Technology

SN - 0022-3131

IS - 7

ER -