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

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.

A Study on the Aging Behavior of Nitrided W18Cr4V Steel in High-Temperature Sodium

“…Throughout the fast reactor history, the sodium coolant has been the highly efficient heat carrier that is applied most commonly. The sodium-cooled fast reactor is the closet to commercialization for nuclear plants amongst the six types of fourth-generation reactors, as announced at the Generation IV International Forum [1][2][3][4][5][6][7]. The high-temperature sodium in the reactor vessel is covered with argon to prevent strong chemical activity.…”