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Oxide Particle Size Distribution from Shearing Irradiated and Unirradiated LWR Fuels in Zircaloy and Stainless Steel Cladding: Significance for Risk Assessment

机译：Zircaloy和不锈钢熔覆中剪切辐照和未辐照LWR燃料的氧化物粒度分布：风险评估的意义

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The purpose of this report is to present data from sieve fractionation of both unirradiated and irradiated fuels and to describe their analysis in terms of the lognormal distribution function. The unirradiated fuels have been described previously, but the sieve-fractionation data have been summarized only briefly. Irradiated shearing and sieve fractionation of fuels from six reactors are presented here.

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作者
Davis, W.; West, G. A.; Stacy, R. G.;
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年度 1979
页码 1-45
总页数 45
原文格式 PDF
正文语种 eng
中图分类工业技术;
关键词
Oxide nuclear fuels ; Thorium dioxide ; Nuclear reactor safety ; Particle size distribution ; Nuclear fuel claddings ; Stainless steels ; Radiation damage ; Subroutines ; Uranium oxides;

机译：氧化物核燃料;二氧化钍;核反应堆安全;粒度分布;核燃料包壳;不锈钢;辐射损伤;子程序;氧化铀;

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1. Hydride reorientation and its impact on ambient temperature mechanical properties of high burn-up irradiated and unirradiated recrystallized Zircaloy-2 nuclear fuel cladding with an inner liner [J] . Q. Auzoux, P. Bouffioux, A. Machiels, Journal of Nuclear Materials: Materials Aspects of Fission and Fusion . 2017,第期

机译：氢化物Reorientation及其对环境温度力学性能的影响，用内衬用内衬照射和未照射的高燃烧和未照射的重结晶锆核燃料包层
2. Threshold stress intensity factor of delayed hydride cracking in irradiated and unirradiated zircaloy-4 cladding [J] . Hong Jong-Dae, Park Myungchul, Holston Anna-Maria Alvarez, Journal of Nuclear Materials: Materials Aspects of Fission and Fusion . 2021,第1期

机译：辐照和未照射锆型锆型渗透液裂解的阈值应力强度因子
3. THERMOCHEMICAL PREDICTION OF CHEMICAL FORM DISTRIBUTIONS OF FISSION PRODUCTS IN LWR OXIDE FUELS IRRADIATED TO HIGH BURNUP [J] . Moriyama K., Furuya H. Journal of Nuclear Science and Technology . 1997,第9期

机译：LBU氧化物辐照至高比重燃烧中的裂变产物化学形态分布的热化学预测
4. Behavior of Lithium and Boron in Irradiated and Unirradiated Oxides Formed on Zircaloy-4 Claddings [C] . T.Kido, S.Wada, T.Takahashi, International symposium on zirconium in the nuclear industry . 2000

机译：在锆洛伊-4封闭上形成辐射和未照射氧化物的锂和硼的行为
5. Concentration and Size Distributions of Nanoparticle Emissions during Low Temperature Combustion using Fuels for Advanced Combustion Engines (FACE). [D] . Bonsack, Peter. 2012

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6. Evaluation of the Shear Bond Strength and Adhesive Remnant Index in Debonding of Stainless Steel Brackets Assisted with Nd:YAG Laser Irradiation [O] . Maryam Nasiri, Amir Hossein Mirhashemi, Ardavan Etemadi, 2019

机译：Nd：YAG激光辅助不锈钢支架脱胶时的剪切粘结强度和粘合残余指数的评估
7. Oxide particle size distribution from shearing irradiated and unirradiated LWR fuels in Zircaloy and stainless steel cladding: significance for risk assessment [O] . W. Jr. Davis, G.A. West, R.G. Stacy 1979

机译：氧化物颗粒尺寸分布在锆瓦罗伊和不锈钢包层中剪切和未照射的LWR燃料：风险评估的重要性

Oxide Particle Size Distribution from Shearing Irradiated and Unirradiated LWR Fuels in Zircaloy and Stainless Steel Cladding: Significance for Risk Assessment

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