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Fuel retention improvement at high temperatures in tungsten-uranium dioxide dispersion fuel elements by plasma-spray cladding

机译：通过等离子喷涂包覆在钨 - 二氧化铀分散燃料元件中在高温下的燃料保持率提高

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作者
Grisaffe, S. J.; Caves, R. M.;
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年度 1964
页码 1-11
总页数 11
原文格式 PDF
正文语种 eng
中图分类工业技术;
关键词
CLADDING; NUCLEAR FUELS; URANIUM OXIDES; DISPERSING; HIGH TEMPERATURE; TUNGSTEN;

机译：熔覆;核燃料;铀氧化物;分散;高温;钨;

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专利

1. SWELLING OF URANIUM DIOXIDE-SILUMIN DISPERSION FUEL COMPOSITION IN EXPERIMENTAL FUEL ELEMENTS OF THE SM REACTOR [J] . Gilmutdinov I. F., Shishin V. Yu., Kryukov F. N., Atomic Energy . 2018,第1期

机译：SM反应器中实验燃料元素中二氧化铀-硅胺分散燃料组合物的溶胀
2. PARTICULARS OF THE BEHAVIOR UNDER IRRADIATION OF DISPERSION FUEL ELEMENTS WITH THE URANIUM DIOXIDE plus ALUMINUM ALLOY FUEL COMPOSITION [J] . Kulakov G. V., Vatulin A. V., Ershov S. A., Atomic Energy . 2015,第4期

机译：二氧化铀加铝合金燃料组合物辐照分散燃料元素时的特性
3. Investigation of the Effect of Radiation-Induced Shape Change of Fuel Assemblies on the Temperature Regime and Stress-Strain State of Fuel-Element Cladding [J] . Sorokin A. P., Bogoslovskaya G. P., Trufanov A. A., Atomic Energy . 2016,第6期

机译：辐射诱导的燃料组件形状变化对燃料元件包壳的温度状态和应力应变状态的影响研究
4. Study of High-Temperature Oxidation of the Claddings of Tolerant Fuel Elements of VVER-type Reactor [C] . K K Polunin, A A Urusov, S S Bazyuk, International Conference on Fusion Energy and Plasma Technologies . 2020

机译：VVER型反应器耐腐蚀燃料元件熔接高温氧化研究
5. Geometrically-accurate and homogenized fuel region models to predict fuel cladding temperatures within a truck cask under normal and fire accident conditions. [D] . Kamichetty, Krishna Kumar. 2010

机译：具有几何精度和均质化的燃料区域模型，可预测正常和火灾事故情况下卡车酒桶内的燃料包壳温度。
6. Fiber Laser Welding of Fuel Cladding and End Plug Made of La2O3 Dispersion-Strengthened Molybdenum Alloy [O] . Geng An, Jun Sun, Yuanjun Sun, 2018

机译：La2O3弥散强化钼合金制成的燃料包壳和端塞的光纤激光焊接
7. FURTHER DEVELOPMENT OF GAS-PRESSURE BONDING OF ZIRCALOY-CLAD FLAT-PLATE URANIUM DIOXIDE FUEL ELEMENTS [O] . Paprocki, S.J., Hodge, E.S., Layer, E.H., 1960

机译：ZIRCaLOY-CLaD平板二氧化铀燃料元件气体压力粘合的进一步发展

Fuel retention improvement at high temperatures in tungsten-uranium dioxide dispersion fuel elements by plasma-spray cladding

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