This paper describes the passive safety features utilized in the updated sodium cooled Super-Safe, Small and Simple fast reactor, which is the improved 4S reactor. This reactor can operate up to ten years without refueling and neutron reflector regulates the reactivity. One of the design requirements is to secure the core against all anticipated transients without reactor scram. Therefore, the reactor concept is to design to enhance the passive safety features. All temperature reactivity feedback coefficients including whole core sodium void worth are negative. Also, introducing of RVACS (Reactor Vessel Auxiliary Cooling System) can enhance the passive decay heat removal capability. Safety analyses are carried out to simulate various transient sequences, which are loss of flow events, transient overpower events and loss of heat sink events, in order to evaluate the passive safety capabilities. A calculation tool for plant dynamics analyses for fast reactors has been modified to model the 4S including the unique plant system, which are reflector control system, circulation pumps and RVACS. The analytical results predict that the designed passive features improve the safety in which temperature variation in transients are satisfied with the safety criteria for the fuel element and the structure of the primary coolant boundary.
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10th International Conference on Nuclear Engineering
April 14–18, 2002
Arlington, Virginia, USA
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
0-7918-3596-0
PROCEEDINGS PAPER
Passive Safety Features in Sodium Cooled Super-Safe, Small and Simple Reactor
N. Ueda,
N. Ueda
Central Research Institute of Electric Power Industry, Komae, Tokyo, Japan
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I. Kinoshita,
I. Kinoshita
Central Research Institute of Electric Power Industry, Komae, Tokyo, Japan
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Y. Nishi,
Y. Nishi
Central Research Institute of Electric Power Industry, Komae, Tokyo, Japan
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A. Minato,
A. Minato
Central Research Institute of Electric Power Industry, Komae, Tokyo, Japan
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H. Matsumiya,
H. Matsumiya
Toshiba Corporation, Yokohama, Japan
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Y. Nishiguchi
Y. Nishiguchi
Toshiba Corporation, Yokohama, Japan
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N. Ueda
Central Research Institute of Electric Power Industry, Komae, Tokyo, Japan
I. Kinoshita
Central Research Institute of Electric Power Industry, Komae, Tokyo, Japan
Y. Nishi
Central Research Institute of Electric Power Industry, Komae, Tokyo, Japan
A. Minato
Central Research Institute of Electric Power Industry, Komae, Tokyo, Japan
H. Matsumiya
Toshiba Corporation, Yokohama, Japan
Y. Nishiguchi
Toshiba Corporation, Yokohama, Japan
Paper No:
ICONE10-22354, pp. 741-748; 8 pages
Published Online:
March 4, 2009
Citation
Ueda, N, Kinoshita, I, Nishi, Y, Minato, A, Matsumiya, H, & Nishiguchi, Y. "Passive Safety Features in Sodium Cooled Super-Safe, Small and Simple Reactor." Proceedings of the 10th International Conference on Nuclear Engineering. 10th International Conference on Nuclear Engineering, Volume 2. Arlington, Virginia, USA. April 14–18, 2002. pp. 741-748. ASME. https://doi.org/10.1115/ICONE10-22354
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