Trích dẫn APA

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.

Trích dẫn kiểu Chicago

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.

Trích dẫn MLA

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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