Japanese national project of next generation light water reactor (LWR) development started in 2008. As one of its development items, the thermal-hydraulic test of spectral shift rod (SSR) is planned. A new component called SSR, which replaces conventional water rod (WR) of boiling water reactor (BWR) fuel bundle, was invented to enhance the BWR’s merit, spectral shift effect for uranium saving. In SSR, water boils by neutron and gamma-ray direct heating and water level is formed as a boundary of the upper steam region and the lower water region. This SSR water level can be controlled by core flow rate, which amplifies core void fraction change, resulting in the amplified spectral shift effect. In this paper, its test plan overview and pre-test analysis by TRACG code is presented. The test plan was developed with the purpose of evaluating SSR thermal-hydraulic characteristics at the actual BWR operating condition (7MPa), such as the controllability of SSR water level, and obtaining data for the validation of calculation method. In the test plan, several types of SSR simulation which covers SSR design in both next generation BWR and conventional BWR were designed. Also test operating conditions such as thermal-hydraulic parameters are determined. In order to evaluate these test specifications, pre-test analysis by TRACG code was conducted. Analysis results of each parameter’s effect on SSR characteristics are consistent with SSR mechanism, which shows that the actual operating condition for SSR fuel is simulated well.
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18th International Conference on Nuclear Engineering
May 17–21, 2010
Xi’an, China
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-4934-7
PROCEEDINGS PAPER
Thermal Hydraulic Test of Advanced BWR Fuel Bundle With Spectral Shift Rod (SSR): Overview and Pre-Test Analysis by TRACG Code
Takao Kondo,
Takao Kondo
Hitachi-GE Nuclear Energy, Ltd., Hitachi, Ibaraki, Japan
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Masao Chaki,
Masao Chaki
Hitachi-GE Nuclear Energy, Ltd., Hitachi, Ibaraki, Japan
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Yukiharu Ohga,
Yukiharu Ohga
The Institute of Applied Energy, Tokyo, Japan
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Moriyasu Abe
Moriyasu Abe
Tokyo Electric Power Company, Tokyo, Japan
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Takao Kondo
Hitachi-GE Nuclear Energy, Ltd., Hitachi, Ibaraki, Japan
Masao Chaki
Hitachi-GE Nuclear Energy, Ltd., Hitachi, Ibaraki, Japan
Yukiharu Ohga
The Institute of Applied Energy, Tokyo, Japan
Moriyasu Abe
Tokyo Electric Power Company, Tokyo, Japan
Paper No:
ICONE18-29967, pp. 251-258; 8 pages
Published Online:
April 8, 2011
Citation
Kondo, T, Chaki, M, Ohga, Y, & Abe, M. "Thermal Hydraulic Test of Advanced BWR Fuel Bundle With Spectral Shift Rod (SSR): Overview and Pre-Test Analysis by TRACG Code." Proceedings of the 18th International Conference on Nuclear Engineering. 18th International Conference on Nuclear Engineering: Volume 6. Xi’an, China. May 17–21, 2010. pp. 251-258. ASME. https://doi.org/10.1115/ICONE18-29967
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