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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2020.8
- 수록면
- 1,603 - 1,610 (8page)
- DOI
- 10.1016/j.net.2020.01.024
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초록· 키워드
오류제보하기
Due to ever-growing advancements in computers and relatively easy access to them, many efforts have been made to develop high-?delity, high-performance, multi-physics tools, which play a crucial role in the design and operation of nuclear reactors. For this purpose in this study, the neutronic Monte Carlo and thermal-hydraulic sub-channel codes entitled MCNP and COBRA-EN, respectively, were applied for external coupling with each other. The coupled code was validated by code-to-code comparison with the internal couplings between MCNP5 and SUBCHANFLOW as well as MCNP6 and CTF. The simulation re-sults of all code systems were in good agreement with each other. Then, as the second problem, the core of the VVER-1000 v446 reactor was simulated by the MCNP4C/COBRA-EN coupled code to measure the capability of the developed code to calculate the neutronic and thermohydraulic parameters of real and industrial cases. The simulation results of VVER-1000 core were compared with FSAR and another nu-merical solution of this benchmark. The obtained results showed that the ability of the MCNP4C/COBRA-EN code for estimating the neutronic and thermohydraulic parameters was very satisfactory.
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참고문헌 (10)
참고문헌 신청
M. Daeubler / 2015 / High-fidelity coupled Monte Carlo neutron transport and thermal-hydraulic simulations using Serpent 2/SUBCHANFLOW / Ann. Nucl. Energy 83:352~375
A. Ivanov / 2013 / High fidelity simulation of conventional and innovative LWR with the coupled Monte-Carlo thermal-hydraulic system MCNP-SUBCHANFLOW / Nucl. Eng. Des 262:264~275
A. Bennett / 2016 / Coupled MCNP6/CTF code: development, testing, and application / Ann. Nucl. Energy 96:1~11
C. L. Waata / 2006 / Coupled Neutronics Thermal Hydraulics Analysis of a High-Performance Light-Water Reactor Fuel Assembly / Von der Fakultat für Maschinenbau der Universitat Stuttgart
Miriam Vazquez Antolín / 2014 / Monte Carlo Neutronics and Thermal-hydraulics Coupling Applied to Fast Reactors
A. Ivanov / 2013 / High fidelity simulation of conventional and innovative LWR with the coupled Monte-Carlo thermal-hydraulic system MCNP-SUBCHANFLOW / Nucl. Eng. Des 262:264~275
A. Bennett / 2016 / Coupled MCNP6/CTF code: development, testing, and application / Ann. Nucl. Energy 96:1~11
C. L. Waata / 2006 / Coupled Neutronics Thermal Hydraulics Analysis of a High-Performance Light-Water Reactor Fuel Assembly / Von der Fakultat für Maschinenbau der Universitat Stuttgart
Miriam Vazquez Antolín / 2014 / Monte Carlo Neutronics and Thermal-hydraulics Coupling Applied to Fast Reactors
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