Regular Article

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

¹ JAEA, Japan Atomic Energy Agency, 4002, Narita, Oarai, Ibaraki, 311-1393, Japan
² MFBR, Mitsubishi FBR Systems Inc., 34-17, Jingumae 2, Shibuya, Tokyo, 150-0001, Japan
³ MHI, Mitsubishi Heavy Industries, 1-1, Wadasaki 1, Hyogo, Kobe, 652-8585, Japan
⁴ CEA, French Atomic Comission, Cadarache DEN/DER/CPA, 13108 Saint-Paul lez Durance Cedex, France
⁵ FRAMATOME, 10 Rue Juliette Récamier, 69006 Lyon, France

^* e-mail: takano.kazuya@jaea.go.jp

Received: 1 December 2021
Received in final form: 2 August 2022
Accepted: 20 October 2022
Published online: 2 December 2022

Abstract

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.