Cladding tube deformation and core emergency cooling in a loss of coolant accident of a pressurized water reactor-Reference-Cited by-同舟云学术

Cladding tube deformation and core emergency cooling in a loss of coolant accident of a pressurized water reactor

Published:1987-08 Issue:1 Volume:103 Page:55-64
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Erbacher F.J.

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. Die COSIMA-Experiments und ihre Nachrechnung, eine Datenbasis zur Überprüfung von Rechenprogrammen für Zweiphasenströmungen;Glass;KfK 4002,1985

2. The development of a burst criterion for Zircaloy fuel cladding under LOCA conditions;Neitzel;KfK 2893, AECL 6420,1980

3. Berstversuche an Zircaloy-Hüllrohren unter kombinierter mechanisch-chemischer Beanspruchung (FABIOLA);Lehning;Reaktortagung,1980

4. LWR fuel rod behavior in the FR-2 in-pile tests simulating the heatup phase of a LOCA;Karb;Final Report, KfK 3346,1983

5. P.D. Parsons, E.D. Hindle and C.A. Mann, The deformation, oxidation and embrittlement of PWR fuel cladding in a loss-of-coolant accident — A state of the art report, to be published as CSNI-Report.

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