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Keywords: LOCA
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Journal Articles
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. July 2021, 7(3): 034503.
Paper No: NERS-20-1012
Published Online: March 16, 2021
... thermal systems. The numerical study discussed in the paper is oriented on the effect of thermal hydraulic parameters on critical leak flow from a high energy liquid carrying loop analogous to LOCA in nuclear power plants. While subjected to rapid depressurization from such piping systems, subcooled...
Journal Articles
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2019, 5(3): 030917.
Paper No: NERS-18-1017
Published Online: May 3, 2019
... fuel rods. The integrity of claddings is always a critical issue during the reactor operation, storage, or loss of coolant accidents (LOCA). After Fukushima disaster, cladding materials are widely studied, as the neutron transparent zirconium (Zr)-based alloys or accident tolerant fuel claddings, which...
Journal Articles
Journal Articles
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2016, 2(2): 021024.
Paper No: NERS-15-1027
Published Online: February 29, 2016
...Alexander Vasiliev; Juri Stuckert This study aims to (1) use the thermal hydraulic and severe fuel damage (SFD) best-estimate computer modeling code SOCRAT/V3 for post-test calculation of QUENCH-LOCA-1 experiment and (2) estimate the SOCRAT code quality of modeling. The new QUENCH-LOCA bundle tests...