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Non-Destructive Determination of Reactor Fuel Element Burnup by Measurement of Fission Neutrons

机译：通过测量裂变中子的非破坏性测定反应器燃料元件燃烧

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Chia-Shi LIN; Jensan TSAI;
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年度 1971
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1. Non-Destructive Determination of Reactor Fuel Element Burnup by Measurement of Fission Neutrons [J] . Chia-Shi LIN, Jensan TSAI Journal of nuclear science and technology . 1971,第5期

机译：通过裂变中子的测量无损确定反应堆燃料元件的燃耗
2. Burnup-dependent core neutronics analysis and calculation of actinide and fission product inventories in discharged fuel of a material test research reactor [J] . Siraj-ul-Islam Ahmad, Nasir Ahmad Progress in Nuclear Energy . 2006,第6期

机译：材料试验研究堆排放燃料中燃耗相关的堆芯中子学分析和act系元素和裂变产物库存的计算
3. Non-Destructive and Destructive Measurements on Burnup Characteristics of Japan Power Demonstration Reactor-I Full-Core Fuel Assemblies [J] . Takenori SUZAKI, Shuji OKAZAKI, Hiroshi OKASHITA, Journal of nuclear science and technology . 1986,第1期

机译：日本动力演示反应堆-I全核燃料组件燃耗特性的无损测量
4. Experimental Fission Gas Release Determination at High Burnup by Means of Gamma Measurements on Fuel Rods in OL2 [C] . Scott Holcombe, Christofer Willman, Arttu Knuutila, WRFPM Top Fuel . 2009

机译：通过OL2的燃料棒对高燃烧的实验裂变气体释放测定
5. AN EXPERIMENTAL STUDY OF THE NEUTRON SPECTRUM AND THE RADIAL POWER DISTRIBUTION IN A FUEL ELEMENT IN THE ILLINOIS ADVANCED TRIGA REACTOR [D] . WEAVER, WALTER LESLIE, III. 1975

机译：伊利诺伊州高级TRIGA反应器中燃料中子谱和径向功率分布的实验研究
6. Determination of element composition and extraterrestrial material occurrence in moss and lichen samples from King George Island (Antarctica) using reactor neutron activation analysis and SEM microscopy [O] . Tomasz Mróz, Katarzyna Szufa, Marina V. Frontasyeva, -1

机译：使用反应堆中子活化分析和SEM显微镜确定来自南极国王乔治岛的苔藓和地衣样品中元素的组成和地球外物质的存在
7. Non-destructive and destructive measurements on burnup characteristics of japan power demonstration reactor-I full-core fuel assemblies. [O] . Takenori SUZAKI, Shuji OKAZAKI, Hiroshi OKASHITA, 1986

机译：日本电力示范反应堆 - 我全核燃料组件的无损和破坏性测量。
8. Non-Destructive Determination of Burnup by gamma-Scanning: An Assessment of Cesium-134/Cesium-137 Activity Ratio as a Fission Monitor in CANDU Fuels [R] . Chen, J. D., Lypka, R. B., Zetaruk, D. G., 1978

机译：通过γ扫描非破坏性地确定燃耗：CaNDU燃料中铯-134 /铯-137活度比作为裂变监测器的评估

Non-Destructive Determination of Reactor Fuel Element Burnup by Measurement of Fission Neutrons

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