Quenching degradation in-pile experiment on an oxidized fuel rod in the temperature range of 1000 to 1260°C-Reference-Cited by-同舟云学术

Quenching degradation in-pile experiment on an oxidized fuel rod in the temperature range of 1000 to 1260°C

Published:1991-12 Issue:2 Volume:132 Page:239-251
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Katanishi Shoji,Sobajima Makoto,Fujishiro Toshio

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

Reference10 articles.

1. PHEBUS program main results and status for severe fuel damage studies;Duco;CEA-CONF-8659,1986

2. Out-of-pile bundle experiments on severe fuel damage (CORA-Program);Hagen;KfK-3677,1986

3. Embrittlement criteria for zircaloy fuel cladding applicable to accident situations in light-water reactors: summary report;Chung;NUREG/CR-1344,1980

4. Failure-bearing capability of oxidized Zircaloy-4 cladding under simulated loss-of-coolant condition;Uetsuka;J. Nucl. Sci. Technol.,1983

5. SCDAP/RELAP5/MOD2 code Manual;Allison;NUREG/CR-5273,1989

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