Holding Force Tests of Curie Point Electro-Magnet in Hot Gas for Passive Shutdown System

Matsunaga, Shoko; Shinichiro, Matsubara; Katoh, Atsushi; Hidemasa, Yamano; Christoph, DoeDERLEIN; Etienne, Guillemin; Julien, Hirn

doi:10.1299/jsmeicone.2019.27.1265

Cited by 1 publication

(2 citation statements)

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“…Various out-ofpile tests have been carried out to investigate the basic characteristics of the SASS, demonstrating its holding stability under the reactor operation condition [11]. The CPEM is a device that can detach control rods to shut down a reactor after the coolant temperature has excessively increased under an unprotected loss of heat sink (ULOHS), which is typically caused by failures of a secondary coolant system or a tertiary water/steam system [5]. An RBH is a passive shutdown system actuated by a hydraulic suspension mechanism for unprotected loss of flow (ULOF) transients [13].…”

Section: Common Views On Design Approaches and Requirementsmentioning

confidence: 99%

“…A France-Japan collaborative work started in 2014 for plant design and three R&D areas -severe accident, reactor technology, and fuel -for the Advanced Sodium Technological Reactor for Industrial Demonstration (ASTRID) to contribute to future sodium-cooled fast reactor (SFR) development [1][2][3]. With great support from CEA and Framatome, the team of Japan (Japan Atomic Energy Agency (JAEA) partnered with Mitsubishi Heavy Industry (MHI) and Mitsubishi FBR systems (MFBR)) conducted design studies and evaluations for ASTRID 600, including the designs of active decay heat removal system [4], curie-point electro-magnetic shutdown devices [5], and seismic isolation systems [6]; fabricability studies of above core structure (ACS) and polar tables [7]; improvement of core catcher design [8]; plant thermal transient evaluation; design analyses of the main vessel and an inner vessel; and core design evaluation.…”

Section: Introductionmentioning

confidence: 99%

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Core and safety design for France–Japan common concept on sodium-cooled fast reactor

Takano

Ohki

Ozawa

et al. 2022

EPJ Nuclear Sci. Technol.

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France (CEA and FRAMATOME) and Japan (JAEA, MFBR, and MHI) teams have carried out collaborative works to have common technical views regarding a sodium-cooled fast reactor (SFR) concept. This paper mainly describes the capabilities of ASTRID 600 to demonstrate SFR technologies of both countries. Japan has studied the feasibility of an enhanced high burnup low-void effect (CFV) core and fuel using oxide dispersion-strengthened steel cladding in ASTRID 600, considering Japan’s target for core performance. The neutronics design of the core has satisfied most required design targets and conditions. Regarding passive shutdown capabilities, Japan team has performed a preliminary numerical analysis for ASTRID 600 using a complementary safety device (CSD), called a self-actuated shutdown system (SASS), one of the safest approaches in Japan. Japan’s team used the SASS in place of the hydraulically suspended absorber rod, called RBH, one of the safest approaches of France, to investigate the potential of the SASS as a design measure common to the countries. The preliminary analysis has shown that the SASS can satisfy the countries’ main requirements. This study has also revealed that the mitigation measures of ASTRID 600 against a severe accident are promising to achieve in-vessel retention for both countries.

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Section: Common Views On Design Approaches and Requirementsmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%