논문상세정보
-
- 저자 장준경 이호철 이현철
- 제어번호 105907112
- 학술지명 Nuclear Engineering and Technology
- 권호사항 Vol. 50 No. 7 [ 2018 ]
- 발행처 한국원자력학회
- 발행처 URL http://www.kns.org
- 자료유형 학술저널
- 수록면 1024-1036
- 언어 English
- 출판년도 2018
- 등재정보 KCI등재
- 판매처
유사주제 논문( 0)
Criticality benchmark of McCARD Monte Carlo code for light-water-reactor fuel in transportation and storage packages
' Criticality benchmark of McCARD Monte Carlo code for light-water-reactor fuel in transportation and storage packages' 의 참고문헌
-
Verification of the procedure to generate the homogenized multi-group cross section for VHTR fuel block using McCARDHan, Tae Young [2012]
-
Validation of the Apollo-Moret Neutronic Codes on Critical Experimental Configurations Simulating the Shipping Casks for Light Water FuelsD. Haon [1980]
-
Urania-gadolinia: Nuclear Model Development and Critical Experiment BenchmarkL.W. Newman [1984]
-
Spectral Shift Control Reactor Basic Physics Program, Critical Experiments on Lattices Moderated by D2O-H2O MixturesT.C. Engelder [1961]
-
SCALE: a Comprehensive Modeling and Simulation Suite for Nuclear Safety Analysis and Design
-
Monte Carlo few-group constant generation for CANDU 6 core analysisYoo Seung Yeol [2015]
-
McCARD User's Manual ver 1.1H.J. Shim [2016]
-
Criticality Benchmark Guide for Light-water-reactor Fuel in Transportation and Storage PackagesJ.J. Lichtenwalter [1997]
-
Assembly depletion with critical spectrum in McCARD Monte Carlo calculations and comparison with HELIOSPark [2010]