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Axisymmetric whole pin life modelling of advanced gas-cooled reactor nuclear fuel

机译：先进气冷堆核燃料的轴对称整体寿命模型

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Mella R; Wenman MR;
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年度 2013
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1. Axisymmetric whole pin life modelling of advanced gas-cooled reactor nuclear fuel [J] . Mella R., Wenman M.R. Journal of Nuclear Materials: Materials Aspects of Fission and Fusion . 2013,第1a3期

机译：先进气冷堆核燃料的轴对称全销寿命模型
2. Simulation of a gas-cooled fluidized bed nuclear reactor - Part II: Stability of a fluidized bed reactor with mixed oxide fuels [J] . B.E. Miles, C.C. Pain, J.LM.A. Gomes Annals of nuclear energy . 2010,第7期

机译：气冷流化床核反应堆的模拟-第二部分：混合氧化物燃料流化床反应堆的稳定性
3. Performance Analysis of Silicon Carbide Composite Clad Uranium Carbide Fuel for a Long-Life Gas-Cooled Fast Reactor Under Normal Operation-Part Ⅱ: Modeling and Simulation [J] . Hangbok Choi, John Bolin Nuclear Technology . 2020,第7期

机译：正常运行中长寿命气冷式快速反应器碳化硅复合铀碳化物燃料的性能分析 - Ⅱ：建模与仿真
4. 3-D ADVANCED GAS-COOLED NUCLEAR REACTOR FUEL CHANNEL RECONSTRUCTION USING STRUCTURE-FROM-MOTION [C] . Kristofer Law, Graeme West, Paul Murray, International topical meeting on nuclear plant instrumentation, control, and human-machine interface technologies . 2017

机译：基于结构运动的3-D先进气冷核反应堆燃料通道重构
5. Enabling CTF for Thermal Expansion Analysis of Metallic Fuels in Advanced Nuclear Reactors [D] . Godbole, Chaitee Milind. 2019

机译：在先进的核反应堆中启用CTF用于金属燃料的热膨胀分析
6. Detection of alpha particle emitters originating from nuclear fuel inside reactor building of Fukushima Daiichi Nuclear Power Plant [O] . Yuki Morishita, Tatsuo Torii, Hiroshi Usami, -1

机译：在福岛第一核电站反应堆厂房内检测源自核燃料的α粒子发射器
7. Figure 2 from: Bulakh OI, Kostylev OK, Nesterov VN, Cherdizov EK (2019) 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. Nuclear Energy and Technology 5(4): 289-295. https://doi.org/10.3897/nucet.5.48391 [O] . Olga I. Bulakh, Oleg K. Kostylev, Vladimir N. Nesterov, 2019

机译：图2来自：Bulakh Oi，Kostyyh OK，Nesterov VN，Cherdizov Ek（2019）延长高温气体冷却反应堆燃料块中石墨的寿命，作为确保核燃料燃烧的设计价值的资源。核能和技术5（4）：289-295。 https://doi.org/10.3897/nucet.5.48391
8. Development of a CVD Silica Coating for UK Advanced Gas-Cooled Nuclear Reactor Fuel Pins [R] . Bennett, M. J., Houlton, M. R., Moore, D. A., 1983

机译：开发用于英国先进气冷核反应堆燃料引脚的CVD二氧化硅涂层

Axisymmetric whole pin life modelling of advanced gas-cooled reactor nuclear fuel

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