Conclusions from V&V studies on the German codes PANAMA and FRESCO for HTGR fuel performance and fission product release-Reference-Cited by-同舟云学术

Conclusions from V&V studies on the German codes PANAMA and FRESCO for HTGR fuel performance and fission product release

Published:2014-05 Issue: Volume:271 Page:84-91
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Verfondern K.,Cao J.,Liu T.,Allelein H.-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

Reference19 articles.

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3. Störfallsimulationen und Nach-bestrahlungsuntersuchungen an kugelförmigen Brennelementen für Hochtemperaturreaktoren;Freis,2010

4. Results of AVR fuel pebble irradiation at increased temperature and burn-up in the HFR Petten;Fütterer;Nuclear Engineering and Design,2008

5. Fuel Performance and Fission Product Behavior in Gas Cooled Reactors. Report IAEA-TECDOC-978;IAEA,1997

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3. The development of TRIAC-BATAN: a triso fuel performance analysis code;Journal of Physics: Conference Series;2019-04

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