Recriticality of the HTR-Module Power Reactor after hypothetical accidents-Reference-Cited by-同舟云学术

Recriticality of the HTR-Module Power Reactor after hypothetical accidents

Published:1992-09 Issue:1 Volume:137 Page:107-114
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Kindt T.,Haque H.

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

Reference9 articles.

1. Technical design features and essential safety-related properties of the HTR-Module;Lohnert;Nucl. Engrg. Des.,1990

2. Sicherheitstechnische Konzeptbeurteilung der HTR-2-Modul-Kraftwerksanlage;Helmers,1990

3. Maximale Brennelementtemperatur beim Druckentlastungsstörfall unter Berücksichtigung von ungünstigen Ausgangszuständen und Unsicherheit der Eingangsdaten;Kohtz,1990

4. The HTR-Module, a power reactor with no reactivity excursions of severe consequences;Lohnert,1988

5. Analysis of reactivity and temperature transient experiments at the AVR High-Temperature Reactor;Scherer;Nuc. Sci. Eng.,1987

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