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RADIAL THERMAL AND FAST NEUTRON FLUX DISTRIBUTIONS IN THE SODIUM REACTOR EXPERIMENT (SRE) AND IN THE TITLE I CONFIGURATION OF THE HALLAM NUCLEAR FACILITY (HNPF)

机译：在钠反应堆实验（sRE）和HaLLam核设施（HNpF）的配置中的径向热和快中子通量分布

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年度 1959
页码 1-33
总页数 33
原文格式 PDF
正文语种 eng
中图分类工业技术;
关键词
REACTOR TECHNOLOGY; DISTRIBUTION; EQUATIONS; HEATING; HNPF; LIQUID METAL COOLANT; NEUTRON FLUX; POWER PLANTS; REACTORS; SHIELDING; SODIUM; SRE; THERMAL NEUTRONS;

机译：反应堆技术;分配;方程;加热; HNpF;液态金属冷却剂;中子通量;发电厂; REaCTORs;屏蔽;钠; sRE;热中子;

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2. Study on Detailed Calculation and Experiment Methods of Neutronics, Fuel Materials, and Thermal Hydraulics for a Commercial Type Japanese Sodium-Cooled Fast Reactor [J] . Toshikazu Takeda, W. F. G. van Rooijen, Katsuhisa Yamaguchi, Science and technology of nuclear installation . 2012,第PTa1期

机译：商用日式钠冷快堆中子学，燃料材料和热工水力的详细计算和实验方法的研究
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4. NEUTRONIC ANALYSIS OF A LIQUID SODIUM FAST REACTOR EXPERIMENT FOR THE LARGE-I POSITION OF THE ADVANCED TEST REACTOR [C] . B. Lilley, T. Palmer, D. LaBrier, International Nuclear Fuel Cycle Conference . 2019

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5. Scaling approach and thermal-hydraulic analysis in the reactor cavity cooling system of a high temperature gas -cooled reactor and thermal-jet mixing in a sodium fast reactor. [D] . Omotowa, Olumuyiwa A. 2014

机译：高温气冷反应堆的反应堆腔冷却系统中的结垢方法和热工水力分析，以及钠快速反应堆中的热喷射混合。
6. RADIAL THERMAL AND FAST NEUTRON FLUX DISTRIBUTIONS IN THE SODIUM REACTOR EXPERIMENT (SRE) AND IN THE TITLE I CONFIGURATION OF THE HALLAM NUCLEAR FACILITY (HNPF) [O] . Legendre, P.J. 1959

机译：在钠反应堆实验（sRE）和HaLLam核设施（HNpF）的配置中的径向热和快中子通量分布

RADIAL THERMAL AND FAST NEUTRON FLUX DISTRIBUTIONS IN THE SODIUM REACTOR EXPERIMENT (SRE) AND IN THE TITLE I CONFIGURATION OF THE HALLAM NUCLEAR FACILITY (HNPF)

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