Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Takano, Kazuya; Oki, Shigeo; Ozawa, Takayuki; Yamano, Hidemasa; Kubo, Shigenobu; Ogura, Masashi*; Yamada, Yumi*; Koyama, Kazuya*; Kurita, Koichi*; Costes, L.*; et al.
EPJ Nuclear Sciences & Technologies (Internet), 8, p.35_1 - 35_9, 2022/12
The France and Japan teams have carried out collaborative works to have common technical views regarding a sodium-cooled fast reactor concept. 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. Regarding passive shutdown capabilities, Japan team has performed a preliminary numerical analysis for ASTRID 600 using a complementary safety device, called a self-actuated shutdown system (SASS), one of the safety approaches of Japan. The mitigation measures of ASTRID 600 against a severe accident, such as a core catcher, molten corium discharge assembly, and the sodium void reactivity features of the CFV core, are promising to achieve in-vessel retention for both countries. The common design concept based on ASTRID 600 is feasible to demonstrate the SFR core and safety technologies for both countries.
Tani, Akihiro*; Kan, Taro*; Okano, Yasushi
no journal, ,
Focal points on reactor core systems of the Safety Design Guidelines are presented based on next generation SFR designs, specifically on "Fuel", "Reactor core cooling ability", "Active shutdown system", "Reactor shutdown utilizing passive system or inherent feedbacks", "Recriticality-free and in-vessel retention approaches".
Saito, Hiroyuki*; Yamada, Yumi*; Oyama, Kazuhiro*; Matsunaga, Shoko*; Kubo, Shigenobu; Yamano, Hidemasa
no journal, ,
The effectiveness of self-actuated shutdown structure (SASS) for representative LOF-type ATWS event in a low-power operation was confirmed after the definition of a response time by three-dimensional thermal hydraulics analysis for its modified structure in order to improve the response characteristics of SASS.
Hiyama, Tomoyuki; Aizawa, Kosuke; Kobayashi, Jun; Kurihara, Akikazu; Nagasawa, Kazuyoshi*; Onuma, Hideyoshi*
no journal, ,
The self-actuated shutdown system (SASS) is a device that passively detach the control rod in response to a temperature rise at the reactor core outlet by utilizing the property that the magnetism of a temperature sensing part disappears as the temperature rises. It is adopted in the advanced sodium-cooled fast reactor designed in Japan. In order to function the SASS effectively, it is important to efficiently guide high temperature fluid from the fuel assembly to the temperature sensing part, so the circumstance of temperature sensing part has a complicated shape such as fins. In order to improve the SASS performance evaluation method, we plan to carry out the full-scale experiment to understand phenomena and acquire data for code validation. In this report, the water experiment was performed on the full-scale model that simulates from the outlets of the fuel assemblies to the SASS flow collector, and flow phenomena around the temperature sensing part was analyzed from the data obtained by PIV measurement.
Shimada, Ren*; Matsunaga, Shoko*; Kajitani, Fumito*; Yoshida, Yoshihiko*; Inuzuka, Taisuke*; Yoshida, Keisuke*; Futagami, Satoshi; Kameyama, Masatoshi*
no journal, ,
no abstracts in English
