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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2017.1
- 수록면
- 1,326 - 1,338 (13page)
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초록· 키워드
오류제보하기
The continuous energy Monte Carlo neutron transport code, MC21, was coupled to the CTF subchannelthermal-hydraulics code using a combination of Consortium for Advanced Simulation of Light WaterReactors (CASL) tools and in-house Python scripts. An MC21/CTF solution for VERA Core PhysicsBenchmark Progression Problem 6 demonstrated good agreement with MC21/COBRA-IE and VERA solutions.
The MC21/CTF solution for VERA Core Physics Benchmark Progression Problem 7, Watts Bar Unit1 at beginning of cycle hot full power equilibrium xenon conditions, is the first published coupled MonteCarlo neutronics/subchannel T-H solution for this problem. MC21/CTF predicted a critical boron concentrationof 854.5 ppm, yielding a critical eigenvalue of 0.99994 ± 6.8E-6 (95% confidence interval).
Excellent agreement with a VERA solution of Problem 7 was also demonstrated for integral and localpower and temperature parameters.
목차
등록된 정보가 없습니다.
참고문헌 (23)
참고문헌 신청
A. Bennett / 2016 / Coupled MCNP6/CTF code: Development, testing, and application / Annals of Nuclear Energy 96 : 1 ~ 11
A. Godfrey / 2014 / VERA Core Physics Benchmark Progression Problem Specifications, Revision 4
A. Ivanov / 2015 / Large-scale Monte Carlo neutron transport calculations with thermal-hydraulic feedback / Ann. Nucl. Energy 84 : 204 ~ 219
B. Kochunas / 2015 / VERA Core Simulator Methodology for PWR Cycle Depletion
Brian N. Aviles / 2017 / MC21/COBRA-IE and VERA-CS multiphysics solutions to VERA core physics benchmark problem #6 / Progress in Nuclear Energy 101 : 338 ~ 351
A. Godfrey / 2014 / VERA Core Physics Benchmark Progression Problem Specifications, Revision 4
A. Ivanov / 2015 / Large-scale Monte Carlo neutron transport calculations with thermal-hydraulic feedback / Ann. Nucl. Energy 84 : 204 ~ 219
B. Kochunas / 2015 / VERA Core Simulator Methodology for PWR Cycle Depletion
Brian N. Aviles / 2017 / MC21/COBRA-IE and VERA-CS multiphysics solutions to VERA core physics benchmark problem #6 / Progress in Nuclear Energy 101 : 338 ~ 351
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