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Extension of lifespan of graphite in fuel blocks of high-temperature gas-cooled reactors as the resource for ensuring design values of nuclear fuel burn-up

机译：高温气体冷却反应器燃料块中石墨寿命的延伸作为保证核燃料烧伤设计价值的资源

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Olga Igorevna Bulakh; Oleg Konstantinovich Kostylev; Vladimir Nikolaevich Nesterov; Eldar Koshalievich Cherdizov;
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1. Nuclear design study on a small-sized High Temperature Gas-cooled Reactor with high burn-up fuel and axial fuel shuffling [J] . Minoru Goto, Yasuyoshi Seki, Yuji Fukaya, Nuclear Engineering and Design . 2014,第may期

机译：具有高燃耗燃料和轴向燃料改组的小型高温气冷堆的核设计研究
2. Fully ceramic microencapsulated fuel in prismatic high-temperature gas-cooled reactors: Design basis accidents and fuel cycle cost [J] . Lu Cihang, Browns Nicholas R. Nuclear Engineering and Design . 2019,第JUNa期

机译：棱柱形高温气冷堆中的全陶瓷微囊燃料：设计基准事故和燃料循环成本
3. Fully ceramic microencapsulated fuel in prismatic high-temperature gas-cooled reactors: Design basis accidents and fuel cycle cost [J] . Lu Cihang, Browns Nicholas R. Nuclear Engineering and Design . 2019,第Juna期

机译：棱镜高温气体冷却反应堆中的完全陶瓷微胶囊燃料：设计基础事故和燃料循环成本
4. Influence of the Graphite's Lifespan on the Design Value of Fuel Burnup in High Temperature Gas-Cooled Reactors [C] . Denis F. Baybakov, Aleksey V. Golovatsky, Artem G. Naymushin, International Conference on Physical-Technical Problems of Nuclear Science, Energy Generation and Power Industry . 2015

机译：石墨寿命对高温气冷反应器燃料燃烧设计价值的影响
5. ICP-MS analysis of fission product diffusion in graphite for High-Temperature Gas-Cooled Reactors. [D] . Carter, Lukas M. 2015

机译：高温气冷堆石墨中裂变产物扩散的ICP-MS分析。
6. The Treatment of PPCP-Containing Sewage in an Anoxic/Aerobic Reactor Coupled with a Novel Design of Solid Plain Graphite-Plates Microbial Fuel Cell [O] . Yi-Tang Chang, Chu-Wen Yang, Yu-Jie Chang, -1

机译：厌氧/好氧反应器中含PPCP污水的处理与固体平原石墨-平板微生物燃料电池的新型设计
7. Extension of lifespan of graphite in fuel blocks of high-temperature gas-cooled reactors as the resource for ensuring design values of nuclear fuel burn-up [O] . Olga I. Bulakh, Oleg K. Kostylev, Vladimir N. Nesterov, 2019

机译：高温气体冷却反应器燃料块中石墨寿命的延伸作为保证核燃料烧伤设计价值的资源
8. THEHGCR-1, A DESIGN STUDY OF A NUCLEAR POWER STATION EMPLOYING A HIGH-TEMPERATURE GAS-COOLED REACTOR WITH GRAPHITE-UO2 FUEL ELEMENTS [R] . W. B. Cottrell, C. M. Copenhaver, H. N. Culver 1958

机译：THEHGCR-1，采用石墨-UO2燃料元件的高温气体冷却反应堆的核电站设计研究

Extension of lifespan of graphite in fuel blocks of high-temperature gas-cooled reactors as the resource for ensuring design values of nuclear fuel burn-up

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