The result of a wall failure in-pile experiment under the EAGLE project |
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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 |
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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 |
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Abstract: | The WF (wall failure) test of the EAGLE program, in which 2 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. |
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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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