Examination of safety design guideline; Safety objective and elimination of re-criticality issues

; ; *;

JNC TN9400 2000-043, 23 Pages, 2000/03

JNC-TN9400-2000-043.pdf:1.1MB

ln the feasibility study on commercialized fast breeder reactor (FBR) cycle systems conducted in JNC, it is required for candidate FBR plants that the level of safety should be enhanced so as to assure: (1)Comparative or superior safety level to that of light water reactors (LWRs), and (2)releaf of the public from anxiety about potential nuclear hazard. Adopting Passive safety characteristics is one of the measures. To attain the above safety objective, we considered implication of the basic safety principles for nuclear power plants that were created by the international nuclear safety advisory group of IAEA. The way to relieve from the anxiety was also taken into account. Then a definite safety objective was set from the standpoint of prevention of core disruptive accident (CDA). Furthermore, as a definite safety goal relating to reactor coresafety, elimination of re-criticality issues under CDA was set by considering characteristics of FBR in comparison with those of LWR. To examine measures for elimination of re-criticality issues, we developed a quick method to estimate possibility of re-criticality under CDA, by drawing a map about criticality characteristics under CDA in various degraded cores. Then hopeful measures were proposed for elimination of re-criticality issues in sodium-cooled FBR with mixed-oxide fuel. Molten fuel discharge behavior of their measures was preliminarily analyzed. We concluded that discharge capability of "a subassembly with an internal duct" was effective, and that "partial removal of axial blanket" was also effective as one of the measures though it has small effect on core performance.

Thermal stress ratcheting analysis of time-hardening structure

Hada, Kazuhiko

Nihon Kikai Gakkai Rombunshu, A, 65(636), p.108 - 115, 1999/08

no abstracts in English

Activity report of Nuclear Fuel Cycle Facility Severe Accident Working Group

Abe, Hitoshi; Yoshida, Kazuo; Fukasawa, Tetsuo*; Muramatsu, Ken*; Ikeda, Yasuhisa*

no journal, , 

On the basis of Fukushima Dai-ichi Nuclear Power Plant accident, evaluation of risk of severe accident (SA) for nuclear fuel cycle facility and investigation of ensuring and improving of safety on the evaluation became urgent problem. In Reprocessing and Recycle Technology Division of Atomic Energy Society of Japan, procedure of selection of the SA on the scientific technological viewpoints for the nuclear fuel cycle facility has been investigated at Nuclear Fuel Cycle facility Severe Accident Working Group (SAWG). In this session, procedure of selection of the SA which should be considered, criterion for judgment for the selection and application example to evaluation of risk as the investigation results in SAWG will be presented.