Critical review of data and correlations describing key clad thermo-mechanical processes under SFR transient conditions: Alternative modelling-Reference-Cited by-同舟云学术

Critical review of data and correlations describing key clad thermo-mechanical processes under SFR transient conditions: Alternative modelling

Published:2017-05 Issue: Volume:97 Page:90-98
ISSN:0149-1970
Container-title:Progress in Nuclear Energy
language:en
Short-container-title:Progress in Nuclear Energy

Author:

Feria F.,Herranz L.E.

Funder

European Commission via the JASMIN project

Publisher

Elsevier BV

Subject

Waste Management and Disposal,Energy Engineering and Power Technology,Safety, Risk, Reliability and Quality,Nuclear Energy and Engineering

Reference17 articles.

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3. The SAS4A/SASSYS-1 Safety Analysis Code System. ANL/NE-12/4, Nuclear Engineering Division;Fanning,2012

4. Tensile properties of annealed type 316 stainless steel after EBR-II irradiation;Fish;J. Nucl. Mater.,1973

5. The European JASMIN Project for the Development of a New Safety Simulation Code, ASTEC-na, for Na-cooled Fast Neutron Reactors. ICAPP, Jeju Island, Korea;Girault,2013

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3. Development and assessment of ASTEC-Na fuel pin thermo-mechanical models performed in the European JASMIN project;Annals of Nuclear Energy;2018-09