Basic verification of THACS for sodium-cooled fast reactor system analysis

Author:

Ma Zaiyong,Yue Nina,Zheng Meiyin,Hu Benxue,Su Guanghui,Qiu Suizheng

Funder

Shanghai Nuclear Engineering Research and Design Institute

International Atomic Energy Agency

International Science & Technology Cooperation Program of China

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference32 articles.

1. Primary pipe rupture accident analysis for Clinch River Breeder Reactor;Albright;Nucl. Technol.,1978

2. Experimental and numerical investigations of sodium boiling experiments in pin bundle geometry;Bottoni;Nucl. Technol.,1990

3. Analysis of the OPERA-15 Two-dimensional Voiding Experiment using the SAS4A Code;Briggs,1984

4. Cahalan J.E., Tentner A.M., Morris E.E., 1994. Advanced LMR safety analysis capabilities in the SASSYS-1 and SAS4A computer codes. Argonne National Lab., IL (United States). Funding organisation: USDOE, Washington, DC (United States).

5. Modeling Developments for the SAS4A and SASSYS Computer Codes;Cahalan,1990

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