Icone19-44140 Conceptual Design Study for the Demonstration Reactor of JSFR : (1) Current Status of JSFR Development

Hayafune, Hiroki; Sakamoto, Yoshimitsu; Kotake, Shoji; Aoto, Kazumi; Ohshima, Jun; Ito, Takaya

doi:10.1299/jsmeicone.2011.19._icone1944_46

Cited by 2 publications

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“…Japanese team adopts Rankine steam cycle and mechanical pumps for secondary systems prioritizing higher yields and higher technical readiness levels [10].…”

Section: Introductionmentioning

confidence: 99%

Plant system study of France–Japan common concept on Sodium-cooled Fast Reactor

Kato

Yamamoto

Ando

et al. 2022

EPJ Nuclear Sci. Technol.

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This paper provides an overview of plant system studies to establish a common technical view for Sodium-cooled Fast Reactor (SFR) concept (the common SFR concept) between France and Japan based on ASTRID 600 and the new concept with downsized output (ASTRID150). One of important issues on a reactor structure design is to enhance seismic resistance to be tolerable against strong earthquake such that postulated in Japan. A concept of High Frequency Design (HFD) is shared, in which the natural frequency of the reactor structure should be higher than that of peak acceleration of vertical floor seismic response with a horizontal seismic isolation system. The design options related to HFD have been examined and design recommendations are established. ASTRID 600 adopted a gas power conversion system to strictly eliminate the chemical reaction risks due to the proximity of sodium and water in the steam generator units. On the other hand, a steam generator (SG) is thought to be a concept with high technical readiness level and is a reference option in Japan and a backup option in France. Then, design comparison of the SG with single-walled helical coil tubes was mainly conducted in this study from the viewpoint of safety and so on. A common concept of a decay heat removal system is discussed to achieve practical elimination of loss of decay heat removal function. A fuel handling system studies are performed to eliminate and ex-vessel storage of spent fuels in sodium to reduce a construction cost. An adequate confinement system is investigated to achieve practical mitigation of large radiological release to the environment even under the condition of core destructive accident.

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“…Japanese team adopts Rankine steam cycle and mechanical pumps for secondary systems prioritizing higher yields and higher technical readiness levels [10].…”

Section: Introductionmentioning

confidence: 99%

Plant system study of France–Japan common concept on Sodium-cooled Fast Reactor

Kato

Yamamoto

Ando

et al. 2022

EPJ Nuclear Sci. Technol.

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“…As a result, a loop-type oxide fuel sodium-cooled fast reactor named JSFR was selected as the most promising design concept for commercialization. Later, the Fast Reactor Cycle Technology Development (FaCT) project made progress on the conceptual design of the JSFR and the innovative technologies used in the JSFR (Hayafune et al, 2011). Although the project was suspended in 2011, the design of the JSFR has been progressed by improving maintainability and repairability (Isono et al, 2014) and safety measures based on lessons learned from the Fukushima Daiichi Nuclear Power Plants accident (Kamide et al, 2015).…”

Section: Introductionmentioning

confidence: 99%

A conceptual design study of pool-type sodium-cooled fast reactor with enhanced anti-seismic capability

Kubo

Chikazawa

Ohshima

et al. 2020

Mechanical Engineering Journal

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The authors are developing the design concept of the pool-type sodium-cooled fast reactor (SFR) that addresses Japan's specific siting conditions such as earthquakes and meets safety design criteria (SDC) and safety design guidelines (SDG) for Generation IV SFRs. The development of this concept will broaden not only options for reactor types in Japan but also the range and depth of international cooperation. A design concept of 1,500 MWt (650 MWe) class pool-type SFR was thought up by applying design technology obtained from the design of advanced loop-type SFR, named JSFR, equipped with safety measures that reflect results from the feasibility study on commercialized fast reactor cycle systems and fast reactor cycle technology development, improved maintainability and repairability, and lessons learned from the Fukushima Daiichi Nuclear Power Plants accident. The design concepts of a reactor vessel (RV) and its internal structures have been investigated whether they could withstand severe seismic conditions in Japan and thermal loads. The design adopted enhanced RV support structure, enhanced conical-shaped core support structure, a thickened knuckle part of the RV, and a flat plenum separator with ribs. A three-dimensional steady-state thermal hydraulic analysis of the RV revealed that the temperature difference of the upper and lower surfaces of the flat plenum separator could be effectively reduced by installing layers of thermal insulation plates. The authors have also conducted a transient analysis of loss of flow type anticipated transients without scram events to evaluate the feasibility of a self-actuated shutdown system. Moreover, the configuration of the decay heat removal system has been investigated considering sufficient utilization of natural circulation capability of sodium coolant, heat removal capacity of each cooling system, conformance with design requirements, and recommendations of SDC and SDG such as diversity and redundancy of components.

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Icone19-44140 Conceptual Design Study for the Demonstration Reactor of JSFR : (1) Current Status of JSFR Development

Cited by 2 publications

References 0 publications

Plant system study of France–Japan common concept on Sodium-cooled Fast Reactor

Plant system study of France–Japan common concept on Sodium-cooled Fast Reactor

A conceptual design study of pool-type sodium-cooled fast reactor with enhanced anti-seismic capability

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