Jun, J. Thermalhydraulic evaluations for a canflex bundle with natural or recycled uranium fuel in the uncrept and crept channels of a candu-6 reactor.
シカゴスタイル引用形Jun, Ji-Su. Thermalhydraulic Evaluations for a Canflex Bundle With Natural or Recycled Uranium Fuel in the Uncrept and Crept Channels of a Candu-6 Reactor.
MLA引用形式Jun, Ji-Su. Thermalhydraulic Evaluations for a Canflex Bundle With Natural or Recycled Uranium Fuel in the Uncrept and Crept Channels of a Candu-6 Reactor.
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