TY - GEN
T1 - Preliminary power transient analysis of the super FR with axially heterogeneous core
AU - Okui, Tsutomu
AU - Yamaji, Akifumi
N1 - Funding Information:
Part of this work was conducted under “Understanding Mechanisms of Severe Accidents and Improving Safety of Nuclear Reactors by Computer Science” of Institute for Advanced Theoretical and Experimental Physics and Waseda Research Institute for Science and Engineering.
Publisher Copyright:
© The Authors, published by EDP Sciences. This is an open access article distributed under the terms of the Creative Commons Attribution License 4.0 (http://creativecommons.org/licenses/by/4.0/).
PY - 2020
Y1 - 2020
N2 - The Super FR is one of the SuperCritical Water cooled Reactor (SCWR) concepts with once-through direct cycle plant system. Recently, new design concept of axially heterogeneous core has been proposed, which consists of multiple layers of MOX and blanket fuels. To clarify the safety performance during power transient, safety analyses have been conducted for uncontrolled control rod (CR) withdrawal and CR ejection at full power. RELAP/SCDAPSIM code was used for the safety analysis. The results show that the peak cladding surface temperature (PCST) is high in the upper MOX fuel layer. It is also shown that axial temperature gradient of cladding greatly increases in a short period. Suppressing such large temperature gradient may be a design issue for the axially heterogeneous core from the viewpoint of ensuring fuel integrity.
AB - The Super FR is one of the SuperCritical Water cooled Reactor (SCWR) concepts with once-through direct cycle plant system. Recently, new design concept of axially heterogeneous core has been proposed, which consists of multiple layers of MOX and blanket fuels. To clarify the safety performance during power transient, safety analyses have been conducted for uncontrolled control rod (CR) withdrawal and CR ejection at full power. RELAP/SCDAPSIM code was used for the safety analysis. The results show that the peak cladding surface temperature (PCST) is high in the upper MOX fuel layer. It is also shown that axial temperature gradient of cladding greatly increases in a short period. Suppressing such large temperature gradient may be a design issue for the axially heterogeneous core from the viewpoint of ensuring fuel integrity.
KW - Axially heterogeneous core
KW - Power transient
KW - RELAP/SCDAPSIM
KW - Super FR
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U2 - 10.1051/epjconf/202124707002
DO - 10.1051/epjconf/202124707002
M3 - Conference contribution
AN - SCOPUS:85108408916
T3 - International Conference on Physics of Reactors: Transition to a Scalable Nuclear Future, PHYSOR 2020
SP - 1419
EP - 1426
BT - International Conference on Physics of Reactors
A2 - Margulis, Marat
A2 - Blaise, Partrick
PB - EDP Sciences - Web of Conferences
T2 - 2020 International Conference on Physics of Reactors: Transition to a Scalable Nuclear Future, PHYSOR 2020
Y2 - 28 March 2020 through 2 April 2020
ER -