CRIEPI has been exploring to realize a small-sized nuclear reactor for the needs of dispersed energy source and multi-purpose reactor. And a conceptual design of 4S (Super-Safe, Small and Simple) reactor was proposed to meet the following design requirements: (1) All temperature feedback reactivity coefficients including whole core sodium void coefficient are negative; (2) The core integrity is secured against all anticipated transient without reactor scram; (3) No emergency power nor active mitigating system is required; (4) The reactivity core life time is more than 10 years; (5) Its construction, maintenance and operation are expected to be very simple by eliminating active components from inside of a reactor vessel. The 4S reactor is a sodium cooled fast reactor and its reactivity is not controlled by neutron absorber rods but by neutron reflectors. An electrical output is 50 MW. This paper describes a design modification to enhance the feasibility from the previous 4S design. A core active height can be shortened to 1.5 m from 4.0m to keep the reactivity characteristics. An averaged fuel burn-up is up to 70 GWD/ton and a pressure drop at the core region is less than 0.1 MPa. A reactivity control system is modified according with the core design change. As for the steam generator design, sodium-water reaction accidents must be taken into account as a design basis event for the utilization of the secondary sodium coolant. Therefore, a modified plate type heat exchanger is proposed as a steam generator. It may be possible to develop a compact steam generator, which is free from sodium-water reaction accidents and to eliminate the secondary sodium systems. The 4S reactor without secondary system has been proposed as a candidate design.
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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
Current Design Status of 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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T. Yokoyama,
T. Yokoyama
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
T. Yokoyama
Toshiba Corporation, Yokohama, Japan
Y. Nishiguchi
Toshiba Corporation, Yokohama, Japan
Paper No:
ICONE10-22353, pp. 733-739; 7 pages
Published Online:
March 4, 2009
Citation
Ueda, N, Kinoshita, I, Nishi, Y, Minato, A, Yokoyama, T, & Nishiguchi, Y. "Current Design Status of 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. 733-739. ASME. https://doi.org/10.1115/ICONE10-22353
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