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Ono, Ayako; Kobayashi, Jun; Kamide, Hideki; Watanabe, Osamu*
no journal, ,
Fully natural circulation system is adopted in a decay heat removal system (DHRS) of Japan Sodium Cooled Fast Reactor (JSFR). Removal of decay heat by natural circulation is very significant for passive safety while station blackout. The DHRS of JSFR consists of one unit of DRACS (direct auxiliary cooling system), which has a dipped heat exchanger in the reactor vessel and two units of PRACS, which has a heat exchanger in a primary-side inlet plenum of IHX in each loop. In this study, first the characteristics of heat transfer of PRACS heat exchanger in JSFR and then transient experiments simulated some events in operating reactor in order to confirm the robustness of DHRS using natural circulation. The sodium experiments showed that the DHRS has the high self-regulating characteristics for some disturbances.
Nabeshima, Kunihiko; Doda, Norihiro; Ishikawa, Nobuyuki; Amano, Katsunori; Ohshima, Hiroyuki
no journal, ,
AtheNa-SA project in JAEA is planned to evaluate the availability of cooling system in the reactor vessel under the severe accident of loop-type or pool-type sodium-cooled fast reactor. This report describes the design study of large scale sodium test facility AtheNa-RV, which could simulate natural circulation decay heat removal system in normal or damaged core.
Tanaka, Masaaki; Amano, Katsunori*; Ishikawa, Nobuyuki; Nabeshima, Kunihiko; Ohshima, Hiroyuki; Oyama, Kazuhiro*; Nakamura, Hironori*; Ichihara, Takashi*
no journal, ,
In the investigation of measures to enhance safety of a sodium cooled fast reactor, conceptual design of a test apparatus for sodium experiment named AtheNa-RV/DHRS has been conducted at JAEA in corporation with MFBR for feasibility study of the diverse systems for decay heat removal under various operating conditions including the sever accident. Important thermal-hydraulic problems to be studied using AtheNa-RV/DHRS and significant points in the design of it were investigated based on knowledge from the existing investigations regarding decay heat removal systems and results of the preliminary numerical simulation of AtheNa-RV/DHRS in temporal design.
Tanaka, Masaaki; Ezure, Toshiki; Ishikawa, Nobuyuki; Nabeshima, Kunihiko; Oyama, Kazuhiro*; Nakamura, Hironori*; Ichihara, Takashi*
no journal, ,
In the investigation of measures to enhance safety of a sodium cooled fast reactor, conceptual design of a test apparatus for sodium experiment named AtheNa-RV/DHRS has been conducted for feasibility study of the diverse systems for decay heat removal under various operating conditions including the sever accident. According to the knowledges of important thermal-hydraulic problems to be studied using AtheNa-RV/DHRS and significant points in the design of it, major components consisting of the simulated core and the direct heat exchanger (DHX) was preliminary designed.
Tanaka, Masaaki; Ezure, Toshiki; Ishikawa, Nobuyuki; Miyakoshi, Hiroyuki; Shimizu, Ryo*; Nakamura, Hironori*; Oyama, Kazuhiro*
no journal, ,
Conceptual design of a sodium test facility AtheNa-RV/DHRS has been conducted for feasibility study of the diverse systems in decay heat removal under various operating conditions including severe accident. In accordance with the requirements for an integrated effect test facility, sodium test loop layout and the reactor vessel with in-vessel direct heat exchangers are proposed.