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.
| Original language | English |
|---|---|
| Pages (from-to) | 629-640 |
| Number of pages | 12 |
| Journal | Journal of Nuclear Science and Technology |
| Volume | 32 |
| Issue number | 7 |
| DOIs | |
| Publication status | Published - 1995 |
| Externally published | Yes |
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Keywords
- accuracy
- BWR type reactors
- comparative analysis
- experimental data
- fuel assemblies
- subchannel analysis code
- two-phase flow
- void fraction
- X-ray CT scanner
ASJC Scopus subject areas
- Nuclear and High Energy Physics
- Nuclear Energy and Engineering
Cite this
Void Fraction Distribution in BWR Fuel Assembly and Evaluation of Subchannel Code. / Inoue, Akira; Kurosu, Tatsuo; Aoki, Toshimasa; Yagi, Makoto; Mitsutake, Toru; Morooka, Shinichi.
In: Journal of Nuclear Science and Technology, Vol. 32, No. 7, 1995, p. 629-640.Research output: Contribution to journal › Article
}
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
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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
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 -