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INTERIM DESCRIPTION OF A COMPUTER PROGRAM (STP-1) FOR ESTIMATING THE DISTRIBUTION OF FISSION AND CORROSION PRODUCT RADIOACTIVITY IN A LIQUID METAL-COOLED FAST BREEDER REACTOR,

机译：用于估算液体金属冷却快速育种反应堆中裂变和腐蚀产物放射性分布的计算机程序（sTp-1）的临时描述，

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作者
zwetzig, g. b. rose, p. f.;
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年度 1969
页码 1-41
总页数 41
原文格式 PDF
正文语种 eng
中图分类工业技术;
关键词
liquid metal cooled reactors; radioactivityfission product activity; reactor materials; corrosion; radioactive isotopes; reactor system components; programming(computers);

机译：液态金属冷却反应堆;放射性裂变产物活性;反应堆材料;腐蚀;放射性同位素;反应堆系统组件;编程（计算机）;

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专利

1. Flow distribution in spherical header of a liquid metal-cooled fast breeder reactor [J] . K Natesan, K Velusamy, P Selvaraj Indian journal of engineering and materials sciences . 2002,第6期

机译：液态金属冷却快中子增殖反应堆球形集管中的流量分布
2. Development of a simple model for estimating the design limit of core void reactivity to prevent re-criticality of MOX-fueled cores in liquid metal-cooled fast reactors [J] . Ishizu Tomoko, Fujita Satoshi, Sonoda Hiroki, Nuclear Engineering and Design . 2021,第Apra期

机译：一种简单模型，用于估算核心空隙反应性的核心无效反应性的设计限制，防止液态金属冷却快速反应器中的MOX燃料芯的重态性
3. Delayed neutron measurements with a natural uranium fission product source in Fast Breeder Test Reactor [J] . G. Srinivasan, R.S. Keshavamurthy, D.V. Subramanian, Annals of nuclear energy . 2014,第mara期

机译：在快速增殖试验反应堆中使用天然铀裂变产物源进行中子延迟测量
4. DEVELOPMENT OF EVALUATION METHODS FOR THE TRANSFER BEHAVIOR OF CORROSION PRODUCT IN THE PRIMARY COOLING SYSTEM OF FAST BREEDER REACTOR [C] . Youichirou MATUO, Shinya MIYAHARA, Yoshinobu IZUMI International conference on nuclear engineering;ASME power conference . 2012

机译：快堆反应器初冷系统腐蚀产物传递行为评价方法的建立。
5. Safety and core design of large liquid-metal cooled fast breeder reactors [D] . Qvist, Staffan Alexander 2013

机译：大型液态金属冷却快中子增殖堆的安全性和核心设计
6. Publisher Correction: Method to Reduce Long-lived Fission Products by Nuclear Transmutations with Fast Spectrum Reactors [O] . Satoshi Chiba, Toshio Wakabayashi, Yoshiaki Tachi, -1

机译：出版商更正：通过快速光谱反应堆通过核Trans变减少长寿命裂变产物的方法
7. USER'S MANUAL FOR THE SOURCE TERM PROGRAM (STP-1) FOR COMPUTING THE DISTRIBUTION OF CORROSION AND FISSION PRODUCTS IN LMFBR'S. [O] . Zwetzig, G.B. 1970

机译：用户手册用于计算LmFBR中腐蚀和裂变产物分布的源程序（sTp-1）。

INTERIM DESCRIPTION OF A COMPUTER PROGRAM (STP-1) FOR ESTIMATING THE DISTRIBUTION OF FISSION AND CORROSION PRODUCT RADIOACTIVITY IN A LIQUID METAL-COOLED FAST BREEDER REACTOR,

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