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Plan for first phase of safety demonstration tests of the High Temperature Engineering Test Reactor (HTTR)
Authors:Yukio Tachibana  Shigeaki Nakagawa  Takeshi Takeda  Akio Saikusa  Takayuki Furusawa  Kuniyoshi Takamatsu  Kazuhiro Sawa  Tatsuo Iyoku
Affiliation:Department of HTTR Project, Oarai Research Establishment, Japan Atomic Energy Research Institute, 3607 Narita-cho, Oarai-machi, Ibaraki 311-1394, Japan
Abstract:Safety demonstration tests using the High Temperature Engineering Test Reactor (HTTR) will be conducted for the purpose of demonstrating inherent safety features of High Temperature Gas-cooled Reactors (HTGRs) as well as providing the core and plant transient data for validation of HTGR safety analysis codes. The first phase safety demonstration test items include the reactivity insertion test and the coolant flow reduction test. In the reactivity insertion test, which is the control rod withdrawal test, one pair out of 16 pairs of control rods is withdrawn, simulating a reactivity insertion event. The coolant flow reduction test consists of the partial loss of coolant flow test and the gas circulators trip test. In the partial loss of coolant flow test, primary coolant flow rate is slightly reduced by control system. In the gas circulators trip test one and two out of three gas circulators are run down, simulating coolant flow reduction events. The gas circulators trip tests, in which position of control rods are kept unchanged, are simulation tests of anticipated transients without scram (ATWS).
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