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Title: Total evaluation of in bundle void fraction measurement test of PWR fuel assembly

Abstract

Nuclear Power Engineering Corporation is performing the various proof or verification tests on safety and reliability of nuclear power plants under the sponsorship of the Ministry of International Trade and Industry. As one program of these Japanese national projects, an in bundle void fraction measurement test of a pressurized water reactor (PWR) fuel assembly was started in 1987 and finished at the end of 1994. The experiments were performed using the 5 x 5 square array rod bundle test sections. The rod bundle test section simulates the partial section and full length of a 17 x 17 type Japanese PWR fuel assembly. A distribution of subchannel averaged void fraction in a rod bundle test section was measured by the gamma-ray attenuation method using the stationary multi beam systems. The additional single channel test was performed to obtain the required information for the calibration of the rod bundle test data and the assessment of the void prediction method. Three test rod bundles were prepared to analyze an axial power distribution effect, an unheated rod effect, and a grid spacer effect. And, the obtained data were used for the assessment of the void prediction method relevant to the subchannel averaged void fractionmore » of PWR fuel assemblies. This paper describes the outline of the experiments, the evaluation of the experimental data and the assessment of void prediction method.« less

Authors:
 [1];  [2];  [3]; ;  [4]
  1. Mitsubishi Heavy Industries, Ltd., Takasago, Hyogo (Japan). Takasago R and D Center
  2. Osaka Univ. (Japan)
  3. Mitsubishi Heavy Industries, Ltd., Yokohama (Japan). Nuclear Energy System Engineering Center
  4. Nuclear Engineering Corp., Tokyo (Japan)
Publication Date:
OSTI Identifier:
271918
Report Number(s):
CONF-960306-
ISBN 0-7918-1226-X; TRN: 96:017226
Resource Type:
Book
Resource Relation:
Conference: ICONE 4: ASME/JSME international conference on nuclear engineering, New Orleans, LA (United States), 10-13 Mar 1996; Other Information: PBD: 1996; Related Information: Is Part Of ICONE-4: Proceedings. Volume 1 -- Part B: Basic technological advances; Rao, A.S. [ed.] [General Electric Nuclear Energy, San Jose, CA (United States)]; Duffey, R.B. [ed.] [Brookhaven National Lab., Upton, NY (United States)]; Elias, D. [ed.] [Commonwealth Edison, Downers Grove, IL (United States)]; PB: 564 p.
Country of Publication:
United States
Language:
English
Subject:
22 NUCLEAR REACTOR TECHNOLOGY; 21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS; PWR TYPE REACTORS; FUEL ASSEMBLIES; SAFETY ANALYSIS; VOID FRACTION; TRANSIENTS; REACTOR ACCIDENTS; POWER DISTRIBUTION; TEST FACILITIES; EXPERIMENTAL DATA

Citation Formats

Hori, Keiichi, Miyazaki, Keiji, Akiyama, Yoshiei, Nishioka, Hiromasa, and Takeda, Naoki. Total evaluation of in bundle void fraction measurement test of PWR fuel assembly. United States: N. p., 1996. Web.
Hori, Keiichi, Miyazaki, Keiji, Akiyama, Yoshiei, Nishioka, Hiromasa, & Takeda, Naoki. Total evaluation of in bundle void fraction measurement test of PWR fuel assembly. United States.
Hori, Keiichi, Miyazaki, Keiji, Akiyama, Yoshiei, Nishioka, Hiromasa, and Takeda, Naoki. 1996. "Total evaluation of in bundle void fraction measurement test of PWR fuel assembly". United States.
@article{osti_271918,
title = {Total evaluation of in bundle void fraction measurement test of PWR fuel assembly},
author = {Hori, Keiichi and Miyazaki, Keiji and Akiyama, Yoshiei and Nishioka, Hiromasa and Takeda, Naoki},
abstractNote = {Nuclear Power Engineering Corporation is performing the various proof or verification tests on safety and reliability of nuclear power plants under the sponsorship of the Ministry of International Trade and Industry. As one program of these Japanese national projects, an in bundle void fraction measurement test of a pressurized water reactor (PWR) fuel assembly was started in 1987 and finished at the end of 1994. The experiments were performed using the 5 x 5 square array rod bundle test sections. The rod bundle test section simulates the partial section and full length of a 17 x 17 type Japanese PWR fuel assembly. A distribution of subchannel averaged void fraction in a rod bundle test section was measured by the gamma-ray attenuation method using the stationary multi beam systems. The additional single channel test was performed to obtain the required information for the calibration of the rod bundle test data and the assessment of the void prediction method. Three test rod bundles were prepared to analyze an axial power distribution effect, an unheated rod effect, and a grid spacer effect. And, the obtained data were used for the assessment of the void prediction method relevant to the subchannel averaged void fraction of PWR fuel assemblies. This paper describes the outline of the experiments, the evaluation of the experimental data and the assessment of void prediction method.},
doi = {},
url = {https://www.osti.gov/biblio/271918}, journal = {},
number = ,
volume = ,
place = {United States},
year = {Thu Aug 01 00:00:00 EDT 1996},
month = {Thu Aug 01 00:00:00 EDT 1996}
}

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