Source term derivation and radiological safety analysis for the TRICO II research reactor in Kinshasa-Reference-Cited by-同舟云学术

Source term derivation and radiological safety analysis for the TRICO II research reactor in Kinshasa

Published:2015-01 Issue: Volume:281 Page:51-57
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Muswema J.L.^ORCID,Ekoko G.B.,Lukanda V.M.,Lobo J.K.-K.,Darko E.O.,Boafo E.K.

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

Reference18 articles.

1. Modified Bateman solution for identical eigenvalues;Dreher;Ann. Nucl. Energy,2013

2. Evaluation and Compilation of Fission Yields, ENDF-349, LA-UR-94-3106, 11 December;England,1994

3. Verbesserte konsistente Berechnung des nuklearen Inventars abgebrannter DWR-Brennstoffe auf der Basis von Zell-Abbrand-Verfahren mit KORIGEN, KfK 3014 (1983). ORNL-tr-5043;Fischer,1983

4. Credible Accident Analyses for TRIGA and TRIGA-Fueled Reactors. Report;Hawley,1982

5. HotSpot Health Physics Code, Version 2.07.2, User's Guide, LLNL-SM-483991;Homann,2011

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