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The result of a wall failure in-pile experiment under the EAGLE project
Authors:Kensuke Konishi   Jun-Ichi Toyooka   Kenji Kamiyama   Ikken Sato   Shigenobu Kubo   Shoji Kotake   Kazuya Koyama   Alexander D. Vurim   Valery A. Gaidaichuk   Alexander V. Pakhnits  Yuri S. Vassiliev
Affiliation:aJapan Atomic Energy Agency (JAEA), 4002 Narita, Oarai, Ibaraki 319-1393, Japan;bJapan Atomic Power Company (JAPC), 1-1 Kanda-Mitoshiro-machi, Chiyoda, Tokyo 101-0053, Japan;cAdvanced Reactor Technology Co. Ltd. (ARTECH), 2-16-5 Kohnan, Minato-ku, Tokyo 108-0075, Japan;dNational Nuclear Center of Republic of Kazakhstan (NNC/RK), Lenin St., 071100 Kurchatov, EKO, Kazakhstan
Abstract:The WF (wall failure) test of the EAGLE program, in which not, vert, similar2 kg of uranium dioxide fuel-pins were melted by nuclear heating, was successfully conducted in the IGR (Impulse Graphite Reactor) of NNC/Kazakhstan. In this test, a 3 mm-thick stainless steel (SS) wall structure was placed between fuel pins and a 10 mm-thick sodium-filled channel (sodium gap). During the transient, fuel pins were heated, which led to the formation of a fuel-steel mixture pool. Under the transient nuclear heating condition, the SS wall was strongly heated by the molten pool, leading to wall failure. The time needed for fuel penetration into the sodium-filled gap was very short (less than 1 s after the pool formation). The result suggests that molten core materials formed in hypothetical LMFBR core disruptive accidents have a certain potential to destroy SS-wall boundaries early in the accident phase, thereby providing fuel escape paths from the core region. The early establishment of such fuel escape paths is regarded as a favorable characteristic in eliminating the possibility of severe re-criticality events. A preliminary interpretation on the WF test results is presented in this paper.
Keywords:EAGLE, experimental acquisition of generalized logic to eliminate re-criticalities   LMFBR, liquid metal fast breeder reactor   CDA, core disruptive accident   IGR, Impulse Graphite Reactor   NNC, National Nuclear Center   RK, Republic of Kazakhstan   FAIDUS, fuel assembly with inner duct structure   GP, gas pressurization   WF, wall failure   FD, fuel discharge   ID, integral demonstration   FA, fuel assembly   FCI, fuel coolant interaction   SS, stainless steel   CA, chromel-alumel   CF, coupling factor
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