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NEUTRONIC DESIGN OF A REACTOR CORE CONTAINING HEAT PIPES FOR APPLICATION TO A NUCLEAR AIRPLANE

机译：用于核飞机的含有热管的反应堆芯的中子设计

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A successful design of a nuclear aircraft propulsion system must meet all specifications of performance and safety at a minimum weight. Heat pipes utilized for removing core heat may be able to reduce sys¬tem weight by eliminating the need for heavy pumps and high pressure piping.nA contract was awarded to C. Silverstein for the study of heat pipe applications to nuclear aircraft propulsion systems (ref. 1). This study was limited to the thermal and mechanical design of heat pipes and did not include core criticálity calculations.

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作者
Richard L. Puthoff;
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作者单位

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年度 1969
页码 1-22
总页数 22
原文格式 PDF
正文语种 eng
中图分类工业技术;
关键词
HEAT PIPES; NUCLEAR PROPELLED AIRCRAFT; REACTOR CORES; NUCLEAR FUELS; NUCLEAR PROPULSION; NUCLEAR REACTORS; REACTOR DESIGN;

机译：热管;核武器飞机;反应堆核心;核燃料;核武器推进;核反应堆;反应堆设计;

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专利

1. Spatial Neutronic Decoupling of Large Fast Breeder Reactor Cores: Application to Nuclear Core Design Method [J] . Keisho shirakata, Toshio Sanda, Fumiaki Nakashima Nuclear science and engineering . 1999,第2期

机译：大型快繁反应堆堆芯的空间中子去耦：在核堆芯设计方法中的应用
2. Preliminary Neutronics Analysis for a Compact Heat-Pipe Cooled Fast Reactor Core [J] . Qin Zeng, Yao Zhou, Ying Shi, Transactions of the American nuclear society . 2019,第Juna期

机译：紧凑型热管冷却快堆堆芯的初步中子学分析
3. Nanofluid application for heat transfer, safety, and natural circulation enhancement in the NuScale nuclear reactor as a small modular reactor using computational fluid dynamic (CFD) modeling via neutronic and thermal-hydraulics coupling [J] . Rahnama Z., Ansarifar G. R. Progress in Nuclear Energy . 2021,第Auga期

机译：纳米流体用于传热，安全性和天然循环的核电抗器中的循环增强，其使用计算流体动力学（CFD）通过中子和热液压耦合建模的小模块化反应器
4. NEUTRONIC AND THERMAL-MECHANICAL COUPLING SCHEMES FOR HEAT PIPE COOLED REACTOR DESIGNS [C] . Yugao Ma, Minyun Liu, Wenbin Han, International Conference on Nuclear Engineering . 2020

机译：用于热管冷却反应器设计的中子和热机械耦合方案
5. CALCULATIONAL METHODS FOR NUCLEAR HEATING AND NEUTRONICS AND PHOTONICS DESIGN FOR CTR (CONTROLLED THERMONUCLEAR REACTOR) BLANKETS AND SHIELDS. [D] . ABDOU, MOHAMED ABD EL-AZIZ. 1973

机译：CTR（受控热反应堆）套管和屏蔽层的核加热计算方法，中子学和光子学设计。
6. Stand-off nuclear reactor monitoring with neutron detectors for safeguards and non-proliferation applications [O] . B. M. van der Ende, L. Li, D. Godin, -1

机译：具有中子探测器的防核反应堆监控用于保障和防扩散应用
7. Neutronics methods, models, and applications at the Idaho National Engineering Laboratory for the advanced neutron source reactor three-element core design [O] . Wemple, C.A., Schnitzler, B.G., Ryskamp, J.M. 1995

机译：爱达荷国家工程实验室的中子学方法，模型和应用，用于先进的中子源反应堆三元件核心设计

NEUTRONIC DESIGN OF A REACTOR CORE CONTAINING HEAT PIPES FOR APPLICATION TO A NUCLEAR AIRPLANE

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