Most startup and shutdown operations in advanced boiling water reactors (ABWRs) are automated by an automatic power regulator (APR). Hitachi and Hitachi-GE utilized the three-dimensional transient analysis code TRACG to design and verify the APR control algorithms. To verify the algorithms, an external neutron source model that makes it possible to simulate a sub-critical initial core, a water temperature reactivity model, a startup range neutron monitor (SRNM) model, and the APR system models were developed and coded onto the TRACG code. The improved TRACG code has been tested and verified with ABWR startup test data. In the test, the criticality was achieved 40 min after beginning of control rod (CR) withdrawal. The code results, for example, CR operation timing, CR withdrawal length, and signals of the neutron sensors agreed well with the test data. In the heat-up control mode, the measured increasing rate of the reactor water temperature was well simulated for a period longer than six hours.
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18th International Conference on Nuclear Engineering
May 17–21, 2010
Xi’an, China
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-4930-9
PROCEEDINGS PAPER
Analysis of ABWR Critical Control and Heat-Up Control Operation by TRACG Code Available to Purchase
Yoshihiko Ishii,
Yoshihiko Ishii
Hitachi, Ltd., Hitachi, Ibaraki, Japan
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Kazuaki Kitou,
Kazuaki Kitou
Hitachi, Ltd., Hitachi, Ibaraki, Japan
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Tomohiko Ikegawa,
Tomohiko Ikegawa
Hitachi, Ltd., Hitachi, Ibaraki, Japan
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Shin Hasegawa,
Shin Hasegawa
Hitachi-GE Nuclear Energy, Ltd., Hitachi, Ibaraki, Japan
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Hitoshi Ochi
Hitoshi Ochi
Hitachi-GE Nuclear Energy, Ltd., Hitachi, Ibaraki, Japan
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Yoshihiko Ishii
Hitachi, Ltd., Hitachi, Ibaraki, Japan
Kazuaki Kitou
Hitachi, Ltd., Hitachi, Ibaraki, Japan
Tomohiko Ikegawa
Hitachi, Ltd., Hitachi, Ibaraki, Japan
Shin Hasegawa
Hitachi-GE Nuclear Energy, Ltd., Hitachi, Ibaraki, Japan
Hitoshi Ochi
Hitachi-GE Nuclear Energy, Ltd., Hitachi, Ibaraki, Japan
Paper No:
ICONE18-29285, pp. 55-62; 8 pages
Published Online:
April 8, 2011
Citation
Ishii, Y, Kitou, K, Ikegawa, T, Hasegawa, S, & Ochi, H. "Analysis of ABWR Critical Control and Heat-Up Control Operation by TRACG Code." Proceedings of the 18th International Conference on Nuclear Engineering. 18th International Conference on Nuclear Engineering: Volume 2. Xi’an, China. May 17–21, 2010. pp. 55-62. ASME. https://doi.org/10.1115/ICONE18-29285
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