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NEUTRON TEMPERATURE IN REACTORS HAVING MODERATOR CLOSELY ASSOCIATED WITH FUEL ELEMENTS

机译：具有与燃料元件紧密相关的调节器的反应器中的中子温度

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摘要

Experiments are described to measure the neutron temperature in graphite moderator with air channels containing heated graphite sleeves.

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作者
R.G. Freemantle; J. S. Harper;
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年度 1960
页码 1-16
总页数 16
原文格式 PDF
正文语种 eng
中图分类工业技术;
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1. Effect of the fuel element bundle statistical characteristics on the evaluation of temperature in the sodium-cooled fast-neutron reactor core [J] . B.B. Tikhomirov, V.M. Poplavsky Nuclear Energy and Technology . 2015,第1期

机译：燃料元件束统计特性对钠冷快中子反应堆堆芯温度评估的影响
2. Effect of the fuel element bundle statistical characteristics on the evaluation of temperature in the sodium-cooled fast-neutron reactor core [J] . B.B. Tikhomirov, V.M. Poplavsky Nuclear Energy and Technology . 2015,第1期

机译：燃料元件束统计特性对钠冷快中子反应堆堆芯温度评估的影响
3. Characterization of a Neutron Beam Following Reconfiguration of the Neutron Radiography Reactor (NRAD) Core and Addition of New Fuel Elements [J] . Craft Aaron E., Hilton Bruce A., Papaioannou Glen C. Nuclear engineering and technology . 2016,第1期

机译：中子射线照相反应堆（NRAD）堆芯重新配置并添加新的燃料元件后中子束的表征
4. NEUTRONIC ASSESSMENT OF TRISO PARTICLE FUELS IN A SMALL FLUORIDE SALT-COOLED HIGH-TEMPERATURE REACTOR [C] . Hassan Mohamed, Benjamin A. Lindley, Geoffrey Parks, Conference on physics of reactors . 2016

机译：小氟化物盐冷高温反应器中TRISO颗粒燃料的中性评估
5. Neutronic analysis stochastic distribution of fuel particles in Very High Temperature Gas-Cooled Reactors. [D] . Ji, Wei. 2008

机译：中子学分析超高温气冷堆中燃料颗粒的随机分布。
6. Neutron and hard X-ray diffraction studies of the isothermal transformation kinetics in the research reactor fuel candidate U–8 wtMo [O] . Steffen Säubert, Rainer Jungwirth, Tobias Zweifel, -1

机译：研究堆燃料候选U-8 wt％Mo中的等温转变动力学的中子和硬X射线衍射研究
7. Effect of Moderator Density Distribution of Annular Flow on Fuel Assembly Neutronic Characteristics in Boiling Water Reactor Cores. [O] . Tsuyoshi AMA, Hideaki IKEDA, Shinya KOSAKA, 2002

机译：沸水反应器芯燃料组装中子流量对燃料组件中子特性的主持人密度分布的影响。
8. Effect of Lattice Deformation on Field Temperatures and Heat Transfer of Fuel Elements Characteristic Zones in a Model of a Fast Reactor Fuel Element Cassette. [R] . Zhukov, A. V., Matyukhin, N. M., Sviridenko, E. Y. 1982

机译：快速反应堆燃料元件盒模型中晶格变形对燃料元件特征区域温度和传热的影响。

NEUTRON TEMPERATURE IN REACTORS HAVING MODERATOR CLOSELY ASSOCIATED WITH FUEL ELEMENTS

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