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STDY-3, A PROGRAM FOR THE THERMAL ANALYSIS OF A PRESSURIZED WATER NUCLEAR REACTOR DURING STEADY-STATE OPERATION

机译：sTDY-3，一种加压水核反应堆在稳态运行过程中的热分析程序

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Pyle, R.S.;
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年度 1960
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机译：中国集成式压水堆的稳态运行和热损失分析
2. Analysis on Steady-State Operation and Heat Loss of Chinese Integrated Pressurized Water Reactor [J] . Fan Zhang, Dao-Gang Lu, Dan-Ting Sui, Science and technology of nuclear installation . 2014,第3期

机译：中国集成式压水堆的稳态运行及热损失分析
3. Probabilistic fracture mechanics analysis of thermally aged nuclear piping in a pressurized water reactor [J] . Shuxiao Li, Hailong Zhang, Shilei Li, Nuclear Engineering and Design . 2013,第deca期

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4. An application of Charpy V testing: the pressure vessel surveillance program of nuclear pressurized water reactor in operation [C] . Nathalie Rupa, Astrid Bache, Josseline Bourgoin, Charpy Centernary Conference . 2002

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5. Nuclear-coupled thermal-hydraulic stability analysis of boiling water reactors. [D] . Karve, Atul A. 1998

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6. Pressurized water reactor spent nuclear fuel data library produced with the Serpent2 code [O] . Zsolt Elter, Li Pöder Balkeståhl, Erik Branger, 2020

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7. Analysis on Steady-State Operation and Heat Loss of Chinese Integrated Pressurized Water Reactor [O] . Zhang Fan, Lu Dao-Gang, Sui Dan-Ting, 2014

机译：中国综合加压水反应堆稳态运行和热损失分析
8. STDY-3, A PROGRAM FOR THE THERMAL ANALYSIS OF A PRESSURIZED WATER NUCLEAR REACTOR DURING STEADY-STATE OPERATION [R] . R. S. Pyle 1960

机译：sTDY-3，一种加压水核反应堆在稳态运行过程中的热分析程序

STDY-3, A PROGRAM FOR THE THERMAL ANALYSIS OF A PRESSURIZED WATER NUCLEAR REACTOR DURING STEADY-STATE OPERATION

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