-
1
-
-
79952435457
-
-
LA-UR-05-4983, Los Alamos National Laboratory
-
F. B. BROWN, "Monte Carlo Lectures," LA-UR-05-4983, Los Alamos National Laboratory (2005).
-
(2005)
Monte Carlo Lectures
-
-
Brown, F.B.1
-
2
-
-
75649141018
-
Monte Carlo - Advances and challenges
-
presented at Workshop at, Interlaken, Switzerland; see also LA-UR-08-05891, Los Alamos National Laboratory
-
F. B. BROWN, W. R. MARTIN, and R. D. MOSTELLER, "Monte Carlo - Advances and Challenges," presented at Workshop at Proc. Int. Conf. Physics of Reactors (PHYSOR 2008), Interlaken, Switzerland (2008); see also LA-UR-08-05891, Los Alamos National Laboratory.
-
(2008)
Proc. Int. Conf. Physics of Reactors (PHYSOR 2008)
-
-
Brown, F.B.1
Martin, W.R.2
Mosteller, R.D.3
-
6
-
-
33144474940
-
Naval reactors
-
A. RADKOWSKY, Ed., U.S. Atomic Energy Commission
-
H. HURWITZ, "Naval Reactors," Naval Reactor Physics Handbook, Vol. 1, p. 864, A. RADKOWSKY, Ed., U.S. Atomic Energy Commission (1964).
-
(1964)
Naval Reactor Physics Handbook
, vol.1
, pp. 864
-
-
Hurwitz, H.1
-
7
-
-
0037319549
-
Methodology of continuous-energy adjoint Monte Carlo for neutron, photon, and coupled neutron-photon transport
-
J. E. HOOGENBOOM, "Methodology of Continuous-Energy Adjoint Monte Carlo for Neutron, Photon, and Coupled Neutron-Photon Transport," Nucl. Sci. Eng., 143, 99 (2003).
-
(2003)
Nucl. Sci. Eng.
, vol.143
, pp. 99
-
-
Hoogenboom, J.E.1
-
9
-
-
85038509983
-
Eigenvalue contribution estimator for sensitivity calculations with Tsunami-3D
-
presented at, St. Petersburg, Russia, May 28-June 1
-
B. T. REARDEN and M. L. WILLIAMS, "Eigenvalue Contribution Estimator for Sensitivity Calculations with TSUNAMI-3D," presented at Proc. 8th Int. Conf. Nuclear Criticality Safety, St. Petersburg, Russia, May 28-June 1, 2007.
-
(2007)
Proc. 8th Int. Conf. Nuclear Criticality Safety
-
-
Rearden, B.T.1
Williams, M.L.2
-
10
-
-
23744462433
-
eff and Λ based on continuous-energy Monte Carlo method
-
eff and Λ Based on Continuous-Energy Monte Carlo Method," J. Nucl. Sci. Technol., 42, 6, 503 (2005).
-
(2005)
J. Nucl. Sci. Technol.
, vol.42
, Issue.6
, pp. 503
-
-
Nauchi, Y.1
Kameyama, T.2
-
11
-
-
33144487610
-
Calculating effective delayed neutron fraction with Monte Carlo
-
R. MEULEKAMP and S. C. VAN DER MARCK, "Calculating Effective Delayed Neutron Fraction with Monte Carlo," Nucl. Sci. Eng., 152, 142 (2006).
-
(2006)
Nucl. Sci. Eng.
, vol.152
, pp. 142
-
-
Meulekamp, R.1
Van Der Marck, S.C.2
-
13
-
-
34248597159
-
Calculation of neutron importance function in fissionable assemblies using Monte Carlo method
-
S. A. H. FEGHHI, M. SHAHRIARI, and H. AFARIDEH, "Calculation of Neutron Importance Function in Fissionable Assemblies Using Monte Carlo Method," Ann. Nucl. Energy, 34, 514 (2007).
-
(2007)
Ann. Nucl. Energy
, vol.34
, pp. 514
-
-
Feghhi, S.A.H.1
Shahriari, M.2
Afarideh, H.3
-
14
-
-
45449084611
-
Calculation of the importance-weighted neutron generation time using MCNIC method
-
S. A. H. FEGHHI, M. SHAHRIARI, and H. AFARIDEH, "Calculation of the Importance-Weighted Neutron Generation Time Using MCNIC Method," Ann. Nucl. Energy, 35, 1397 (2008).
-
(2008)
Ann. Nucl. Energy
, vol.35
, pp. 1397
-
-
Feghhi, S.A.H.1
Shahriari, M.2
Afarideh, H.3
-
15
-
-
79952377810
-
Calculating kinetics parameters and reactivity changes using continuous-energy Monte Carlo
-
Pittsburgh, Pennsylvania, May 14-19, 2010
-
B. C. KIEDROWSKI, F. B. BROWN, and P. P. H. WILSON, "Calculating Kinetics Parameters and Reactivity Changes using Continuous-Energy Monte Carlo," Proc. PHYSOR 2010: Advances in Reactor Physics to Power the Nuclear Renaissance, Pittsburgh, Pennsylvania, May 14-19, 2010 (2010).
-
Proc. PHYSOR 2010: Advances in Reactor Physics to Power the Nuclear Renaissance
, pp. 2010
-
-
Kiedrowski, B.C.1
Brown, F.B.2
Wilson, P.P.H.3
-
16
-
-
0006277155
-
The time-dependent importance of neutrons and precursors
-
J. D. LEWINS, "The Time-Dependent Importance of Neutrons and Precursors," Nucl. Sci. Eng., 7, 268 (1960).
-
(1960)
Nucl. Sci. Eng.
, vol.7
, pp. 268
-
-
Lewins, J.D.1
-
17
-
-
77951582136
-
A review of best practices for Monte Carlo criticality calculations
-
Robustness, and the Nuclear Renaissance, Richland, Washington, September 13-17, 2009, American Nuclear Society, (CD-ROM)
-
F. B. BROWN, "A Review of Best Practices for Monte Carlo Criticality Calculations," Proc. 2009 Nuclear Criticality Safety Division Topi. Mtg. Realism, Robustness, and the Nuclear Renaissance, Richland, Washington, September 13-17, 2009, American Nuclear Society (2009) (CD-ROM).
-
(2009)
Proc. 2009 Nuclear Criticality Safety Division Topi. Mtg. Realism
-
-
Brown, F.B.1
-
18
-
-
33746229118
-
-
LA-UR-08-7258, Los Alamos National Laboratory
-
R. E. ALCOUFFE, R. S. BAKER, J. A. DAHL, S. A. TURNER, and R. C. WARD, "Partisn: A Time-Dependent, Parallel Neutral Particle Transport Code System," LA-UR-08-7258, Los Alamos National Laboratory (2008).
-
(2008)
Partisn: A Time-dependent, Parallel Neutral Particle Transport Code System
-
-
Alcouffe, R.E.1
Baker, R.S.2
Dahl, J.A.3
Turner, S.A.4
Ward, R.C.5
-
19
-
-
33746323294
-
Monte Carlo calculation of effective neutron generation time
-
W. B. VERBOOMEN, "Monte Carlo Calculation of Effective Neutron Generation Time," Ann. Nucl. Energy, 33, 911 (2006).
-
(2006)
Ann. Nucl. Energy
, vol.33
, pp. 911
-
-
Verboomen, W.B.1
-
20
-
-
79960764366
-
Monte Carlo methods and applications in neutronics
-
Springer-Verlag, Berlin
-
D. BROCKWAY, P. SORAN, and P. WHALEN, in Monte Carlo Methods and Applications in Neutronics, Photonics and Statistical Physics, p. 378, Springer-Verlag, Berlin (1985).
-
(1985)
Photonics and Statistical Physics
, pp. 378
-
-
Brockway, D.1
Soran, P.2
Whalen, P.3
-
22
-
-
79960774927
-
-
LA-UR-10-01700, Los Alamos National Laboratory
-
B. C. KIEDROWSKI, "Theory, Interface, Verification, Validation, and Performance of the the Adjoint-Weighted Point Reactor Kinetics Parameter Calculations in MCNP," LA-UR-10-01700, Los Alamos National Laboratory (2010).
-
(2010)
Theory, Interface, Verification, Validation, and Performance of the the Adjoint-weighted Point Reactor Kinetics Parameter Calculations in MCNP
-
-
Kiedrowski, B.C.1
-
23
-
-
0027624756
-
Whole core calculations of power reactors by use of Monte Carlo method
-
M. NAKAGAWA and T. MORI, "Whole Core Calculations of Power Reactors by use of Monte Carlo Method," J. Nucl. Sci. Technol., 30, 7, 692 (1993).
-
(1993)
J. Nucl. Sci. Technol.
, vol.30
, Issue.7
, pp. 692
-
-
Nakagawa, M.1
Mori, T.2
-
24
-
-
33947156628
-
ENDF/B-VII.0: Next generation evaluated nuclear data library for nuclear science and technology
-
M. B. CHADWICK et al., "ENDF/B-VII.0: Next Generation Evaluated Nuclear Data Library for Nuclear Science and Technology," Nucl. Data Sheets, 107, 2931 (2006).
-
(2006)
Nucl. Data Sheets
, vol.107
, pp. 2931
-
-
Chadwick, M.B.1
-
26
-
-
22344443506
-
Validation suites for MCNP
-
Santa Fe, New Mexico, April 14-18, 2002, American Nuclear Society, (CD-ROM)
-
R. D. MOSTELLER, "Validation Suites for MCNP," Proc. 12th Biennial Topl. Mtg. Radiation Protection and Shielding Division, Santa Fe, New Mexico, April 14-18, 2002, American Nuclear Society (2002) (CD-ROM).
-
(2002)
Proc. 12th Biennial Topl. Mtg. Radiation Protection and Shielding Division
-
-
Mosteller, R.D.1
-
27
-
-
0021313821
-
Generalized Monte Carlo perturbation algorithms for correlated sampling and a second-order taylor series approach
-
H. RIEF, "Generalized Monte Carlo Perturbation Algorithms for Correlated Sampling and a Second-Order Taylor Series Approach," Ann. Nucl. Energy, 11, 455 (1984).
-
(1984)
Ann. Nucl. Energy
, vol.11
, pp. 455
-
-
Rief, H.1
-
28
-
-
85038515766
-
Estimation in the change of k-effective due to perturbed fission source distribution in MCNP
-
Gatlinburg, Tennessee, April 6-10, 2003, American Nuclear Society, (CD-ROM)
-
Y. NAGAYA and F. B. BROWN, "Estimation in the Change of k-effective due to Perturbed Fission Source Distribution in MCNP," Proc. Mtg. Nuclear Mathematical and Computational Sciences (M & C2003), Gatlinburg, Tennessee, April 6-10, 2003, American Nuclear Society (2003) (CD-ROM).
-
(2003)
Proc. Mtg. Nuclear Mathematical and Computational Sciences (M & C2003)
-
-
Nagaya, Y.1
Brown, F.B.2
-
30
-
-
79953907332
-
Second-order reactivity worth estimates using an Off-the-shelf multigroup discrete ordinates transport code
-
presented at, Interlaken, Switzerland, September 14-19
-
J. A. FAVORITE, "Second-Order Reactivity Worth Estimates Using an Off-the-Shelf Multigroup Discrete Ordinates Transport Code," presented at Proc. Int. Conf. Physics of Reactors (PHYSOR 2008), Interlaken, Switzerland, September 14-19, 2008.
-
(2008)
Proc. Int. Conf. Physics of Reactors (PHYSOR 2008)
-
-
Favorite, J.A.1
-
31
-
-
22344453452
-
ENDF66: A continuous-energy neutron data library for MCNP4C
-
Santa Fe, New Mexico, April 14-18, 2002, American Nuclear Society (CD-ROM)
-
J. M. CAMPBELL, S. C. FRANKLE, and R. C. LITTLE, "ENDF66: A Continuous-Energy Neutron Data Library for MCNP4C," Proc. 12th Biennial Topl. Mtg. Radiation Protection and Shielding Division, Santa Fe, New Mexico, April 14-18, 2002, American Nuclear Society (2002) (CD-ROM).
-
(2002)
Proc. 12th Biennial Topl. Mtg. Radiation Protection and Shielding Division
-
-
Campbell, J.M.1
Frankle, S.C.2
Little, R.C.3
-
32
-
-
0347823536
-
Developments in perturbation theory
-
E. J. HENLEY and J. D. LEWINS, Eds., Academic Press, New York
-
E. GREENSPAN, "Developments in Perturbation Theory," in Advances in Nuclear Science and Technology, Vol. 9, p. 181, E. J. HENLEY and J. D. LEWINS, Eds., Academic Press, New York (1976).
-
(1976)
Advances in Nuclear Science and Technology
, vol.9
, pp. 181
-
-
Greenspan, E.1
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