Criticality Safety and Sensitivity Analyses of PWR Spent Nuclear Fuel Repository Facilities-Reference-Cited by-同舟云学术

Criticality Safety and Sensitivity Analyses of PWR Spent Nuclear Fuel Repository Facilities

Published:2005-01 Issue:1 Volume:149 Page:1-13
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Maučec Marko¹,Glumac Bogdan²

Affiliation:

1. Jožef Stefan Institute, Reactor Physics Division Jamova 39, 1000 Ljubljana, Slovenia, and Rijksuniversiteit Groningen Kernfysisch Versneller Instituut, Nuclear Geophysics Division Zernikelaan 25, 9747 AA Groningen, The Netherlands

2. Jožef Stefan Institute, Reactor Physics Division Jamova 39, 1000 Ljubljana, Slovenia

Publisher

Informa UK Limited

Subject

Condensed Matter Physics,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Link

https://www.tandfonline.com/doi/pdf/10.13182/NT05-A3575

Reference16 articles.

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

2. AMERICAN NUCLEAR SAFETY STANDARDS COMMITTEE, Working Group ANS-57.2-1983, “American National Standard Design Objectives for Light Water Reactor Spent-Fuel Storage Facilities at Nuclear Power Stations,” American Nuclear Society (1983).

3. M. MAUCEC, “Criticality Safety Analyses of Spent-Fuel Storage Facilities,” MS Thesis, Faculty of Civil Engineering, University of Maribor, Slovenia (in Slovenian) (1996).

4. The Effect of Pitch, Burnup, and Absorbers on a TRIGA Spent-Fuel Pool Criticality Safety

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