Nuclear criticality safety considerations for CASTOR casks with spent fuel of the Rossendorf nuclear devices-Reference-Cited by-同舟云学术

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Nuclear criticality safety considerations for CASTOR casks with spent fuel of the Rossendorf nuclear devices

Published:1997-07 Issue:1-3 Volume:170 Page:53-58
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Seifert Eberhard

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference4 articles.

1. MCNPA General Monte Carlo N-Particle Transport Code (Version 4A),1993

2. The Subgroup Method for the Calculation of the Resonance Structures of the Cross Sections for Neutron Calculations;Nikolaev;Part 1: Atomnaja Energija tom 29, vypusk 1, 1970, Part 2: Atomnaja Energija tom 30, vypusk 5, 1971,1970

3. Konditionierung von Brennelementen aus Forschungsreaktoren im CASTOR MTR 2 (Systemlösung für die RFR-Entsorgung);Freiberg;Stand 08.03.1993,1993

4. A PC Version of the Monte Carlo Criticality Code OMEGA;Seifert;VKTA Rossendorf, Report VKTA-31,1996

Cited by 3 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Research on MEMS Based Real-Time Measurement System for the Nuclear Fuel Transport Cask;Key Engineering Materials;2014-04

2. Modeling and criticality evaluation of the voloxidation process;Annals of Nuclear Energy;2011-10

3. Criticality Safety and Sensitivity Analyses of PWR Spent Nuclear Fuel Repository Facilities;Nuclear Technology;2005-01

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