Monte Carlo burnup and its uncertainty propagation analyses for VERA depletion benchmarks by McCARD
-
-
저자
박호진
이동혁
전병규
심형진
-
제어번호
105907110
-
학술지명
Nuclear Engineering and Technology
-
권호사항
Vol.
50
No.
7
[
2018
]
-
발행처
한국원자력학회
-
발행처 URL
http://www.kns.org
-
자료유형
학술저널
-
수록면
1043-1050
-
언어
English
-
출판년도
2018
-
등재정보
KCI등재
-
판매처
'
Monte Carlo burnup and its uncertainty propagation analyses for VERA depletion benchmarks by McCARD' 의 참고문헌
-
Validation of a continuousenergy Monte Carlo burn-up code MVP-BURN and its application to analysis of post irradiation experiment
-
Users Manual, Version 1.00 for MONTEBURNS, Version 3.01
-
Uncertainty propagation in Monte Carlo depletion analysis
-
Specifications for the VERA Depletion Benchmark Suite
-
Serpentea Continuous-energy Monte Carlo Reactor Physics Burnup Calculation Code
-
Quadratic depletion method for gadolinium isotopes in CASMO-5
-
ORIGEN2: a versatile computer code for calculating the nuclide compositions and characteristics of nuclear materials
-
Monte Carlo depletion analysis of a PWR with the MCNAP
-
MCNP6TM User's Manual Version 1.0, Rev. 0
-
-
Jordan Research & Training Reactor Final Safety Analysis Report
[2014]
-
Impact of perturbed fission source on the effective multiplication factor in Monte Carlo perturbation calculations
-
Higher order methods for burnup calculations with bateman solutions
-
-
Generalized Monte Carlo perturbation algorithms for correlated sampling and a second-order taylor series approach
-
Development of Gadolinium Quadratic Depletion Module for DeCART
-
Depletion and decay analyses of a KJRR fission moly target
-
Computing the matrix exponential in burnup calculations
-
Comparison of neutronics-depletion coupling schemes for burnup calculations
-
Comparison of MCNPX-C90 and TRIPOLI-4-d for fuel depletion calculations of a gas-cooled fast reactor
'
Monte Carlo burnup and its uncertainty propagation analyses for VERA depletion benchmarks by McCARD'
의 유사주제(
) 논문