1 |
B.L. Sjenitzer, J.E. Hoogenboom, Dynamic Monte Carlo method for nuclear reactor kinetics calculations, Nucl. Sci. Eng. 175 (2013) 94-107.
DOI
|
2 |
B.L. Sjenitzer, J.E. Hoogenboom, J.J. Escalante, V.S. Espinoza, Coupling of dynamic Monte Carlo with thermal-hydraulic feedback, Ann. Nucl. Energy 76 (2015) 27-39.
DOI
|
3 |
Y.G. Jo, B. Cho, N.Z. Cho, Nuclear reactor transient analysis by continuousenergy Monte Carlo calculation based on predictor-corrector quasi-static method, Nucl. Sci. Eng. 183 (2016) 229-246.
DOI
|
4 |
E.L. Kaplan, Monte Carlo Methods for Equilibrium Solutions in Neutron Multiplication, UCRL-5275-T, Lawrence Livermore National Laboratory, 1958.
|
5 |
L.M. Petrie, N.F. Cross, KENO-V.a: an Improved Monte Carlo Criticality Program with Supergrouping, NUREG/CR-0200, Sec. Fll, ORNL/NUREG/CSD-2 vol. 2, Oak Ridge National Laboratory, 1985.
|
6 |
J.F. Briesmeister (Ed.), MCNP-A General Monte Carlo N-Particle Transport Code, Version 4A, LA-12625, Los Alamos National Laboratory, 1993.
|
7 |
J.T. Mihalczo, T.E. Valentine, Calculational verification and process control applications utilizing the high sensitivity of noise measurement parameters to fissile system configuration, Nucl. Sci. Eng. 121 (1995) 286-300.
DOI
|
8 |
T.E. Valentine, J.T. Mihalczo, MCNP-DSP: a neutron and gamma ray Monte Carlo calculation of source-driven noise-measured parameters, Ann. Nucl. Energy 23 (1996) 1271-1287.
DOI
|
9 |
D.E. Cullen, TART 2002: a Coupled Neutron-photon, 3-D, Combinatorial Geometry, Time Dependent Monte Carlo Transport Code, UCRL-ID-126455, Rev. 4, Lawrence Livermore National Laboratory, 2002.
|
10 |
U. Wiacek, E. Krynicka, Decay of the pulsed thermal neutron flux in two-zone hydrogenous systems-Monte Carlo simulations using MCNP standard data libraries, Nucl. Instrum. Methods Phys. Res. B 243 (2006) 92-98.
DOI
|
11 |
C.H. Pyeon, Experimental Benchmarks on Thorium-loaded Accelerator-driven System at Kyoto University Critical Assembly, KURR-TR(CD)-48, Research Reactor Institute, Kyoto University, 2015.
|
12 |
T.E. Booth, A Weight (Charge) Conserving Importance-weighted Comb for Monte Carlo, LA-UR-96-0051, Los Alamos National Laboratory, 1996.
|
13 |
D.E. Cullen, C.J. Clouse, R. Procassini, R.C. Little, Static and Dynamic Criticality: Are They Different? UCRL-TR-201506, Lawrence Livermore National Laboratory, 2003.
|
14 |
D. Brockway, P. Soran, P. Whalen, Monte Carlo Calculation, LA-UR-85-1224, Los Alamos National Laboratory, 1985.
|
15 |
N. Shaukat, H.J. Shim, Alpha eigenvalue estimation from dynamic Monte Carlo calculation for subcritical systems, in: Transactions of the Korean Nuclear Society Spring Meeting, Jeju, Korea, May 11-13, 2016.
|
16 |
H.J. Shim, S.H. Jang, S.M. Kang, Monte Carlo alpha iteration algorithm for a subcritical system analysis, Sci. Technol. Nucl. Ins. 2015 (2015) 859242. http://dx.doi.org/10.1155/2015/859242.
DOI
|
17 |
H.J. Shim, B.S. Han, J.S. Jung, H.J. Park, C.H. Kim, McCARD: Monte Carlo code for advanced reactor design and analysis, Nucl. Eng. Technol. 44 (2012) 161-176.
DOI
|
18 |
V.F. Boyarinov, P.A. Fomichenko, J. Hou, K. Ivanov, A. Aures, W. Zwermann, K. Velkov, Deterministic Time-dependent Neutron Transport Benchmark without Spatial Homogenization (C5G7-TD), Version 1.6, NEA/NSC/DOC(2016), OECD Nuclear Energy Agency, 2016.
|
19 |
M. Aufiero, C. Fiorina, A. Laureau, P. Rubiolo, V. Valtavirta, Serpent-OpenFoam Coupling in transient mode: simulation of a Godiva prompt critical burst, in: Proceedings of ANS MC2015-Joint International Conference on Mathematics and Computation (M&C), Supercomputing in Nuclear Applications (SNA) and the Monte Carlo (MC) Method, Nashville, TN, 2015.
|
20 |
J. Lieberoth, A Monte Carlo technique to solve the static eigenvalue problem of the Boltzmann transport equation, Nukleonik 11 (1968) 213-219.
|
21 |
Y.S. Jung, C.B. Shim, C.H. Lim, H.G. Joo, Practical numerical reactor employing direct whole core neutron transport and subchannel thermal/hydraulic solvers, Ann. Nucl. Energy 62 (2013) 357-374.
DOI
|
22 |
A.F. Henry, The application of reactor kinetics to the analysis of experiments, Nucl. Sci. Eng. 3 (1958) 52-70.
DOI
|
23 |
A.F. Henry, Nuclear-Reactor Analysis, MIT Press, Cambridge, MA, 1975.
|
24 |
E. Lewis, M. Smith, N. Tsoulfanidis, G. Palmiotti, T. Taiwo, R. Blomquist, Benchmark Specification for Deterministic 2-D/3-D MOX Fuel Assembly Transport Calculations without Spatial Homogenization (C5G7 MOX), NEA/NSC, 2001.
|