-
1
-
-
0003524797
-
"SIMMER-II: A Computer Program for LMFBR Disrupted Core Analysis"
-
LA-11415-MS, Los Alamos National Laboratory
-
W. R. BOHL and L. B. LUCK, "SIMMER-II: A Computer Program for LMFBR Disrupted Core Analysis," LA-11415-MS, Los Alamos National Laboratory (1990).
-
(1990)
-
-
Bohl, W.R.1
Luck, L.B.2
-
2
-
-
0002114128
-
"The SIMMER Program: Its Accomplishments"
-
Knoxville, Tennessee, April 21-25, 1985, U.S. Department of Energy
-
L. L. SMITH, C. R. BELL, W. R. BOHL, L. B. LUCK, T. R. WEHNER, G. P. DEVAULT, and F. R. PARKER, "The SIMMER Program: Its Accomplishments," Proc. Int. Topl. Mtg. Fast Reactor Safety, Knoxville, Tennessee, April 21-25, 1985, p. 977, U.S. Department of Energy (1985).
-
(1985)
Proc. Int. Topl. Mtg. Fast Reactor Safety
, pp. 977
-
-
Smith, L.L.1
Bell, C.R.2
Bohl, W.R.3
Luck, L.B.4
Wehner, T.R.5
Devault, G.P.6
Parker, F.R.7
-
3
-
-
0000767912
-
"Status and Achievement of Assessment Program for SIMMER-III, A Multiphase, Multicomponent Code for LMFR Safety Analysis"
-
Kyoto, Japan, September 30-October 4, (1997)
-
SA. KONDO, D. J. BREAR, Y. TOBITA, K. MORITA, W. MASCHEK, P. COSTE, and D. WILHELM, "Status and Achievement of Assessment Program for SIMMER-III, A Multiphase, Multicomponent Code for LMFR Safety Analysis," Proc. 8th Int. Topl. Mtg. Nuclear Reactor Thermal Hydraulics (NURETH-8), Kyoto, Japan, September 30-October 4, 1997, Vol. 3, p. 1340 (1997).
-
(1997)
Proc. 8th Int. Topl. Mtg. Nuclear Reactor Thermal Hydraulics (NURETH-8)
, vol.3
, pp. 1340
-
-
Kondo, S.A.1
Brear, D.J.2
Tobita, Y.3
Morita, K.4
Maschek, W.5
Coste, P.6
Wilhelm, D.7
-
4
-
-
0003716396
-
"Phase 2 Code Assessment of SIMMER-III, A Computer Program for LMFR Core Disruptive Accident Analysis"
-
JNC TN9400 2000-105, Japan Nuclear Cycle Development Institute
-
SA. KONDO, H. YAMANO, Y. TOBITA, S. FUJITA, K. KAMIYAMA, W. MASCHEK, P. COSTE, S. PIGNY, and J. LOUVET, "Phase 2 Code Assessment of SIMMER-III, A Computer Program for LMFR Core Disruptive Accident Analysis," JNC TN9400 2000-105, Japan Nuclear Cycle Development Institute (2000).
-
(2000)
-
-
Kondo, S.A.1
Yamano, H.2
Tobita, Y.3
Fujita, S.4
Kamiyama, K.5
Maschek, W.6
Coste, P.7
Pigny, S.8
Louvet, J.9
-
5
-
-
49449129017
-
"Towards the Ultimate Conservative Difference Scheme: IV. A New Approach to Numerical Convection"
-
B. VAN LEER, "Towards the Ultimate Conservative Difference Scheme: IV. A New Approach to Numerical Convection," J. Comput. Phys., 23, 276 (1977).
-
(1977)
J. Comput. Phys.
, vol.23
, pp. 276
-
-
Van Leer, B.1
-
6
-
-
33644762088
-
"AFDM: An Advanced Fluid-Dynamics Model, Volume I: Scope, Approach, and Summary"
-
LA-11692-MS, Los Alamos National Laboratory
-
W. R. BOHL, D. WILHELM, F. R. PARKER, J. BERTHIER, L. GOUTAGNY, and H. NINOKATA, "AFDM: An Advanced Fluid-Dynamics Model, Volume I: Scope, Approach, and Summary," LA-11692-MS, Vol. I, Los Alamos National Laboratory (1990).
-
(1990)
, vol.1
-
-
Bohl, W.R.1
Wilhelm, D.2
Parker, F.R.3
Berthier, J.4
Goutagny, L.5
Ninokata, H.6
-
7
-
-
33645036965
-
"Two-Phase Flow Averaged Codes: Criteria for Numerical Methods"
-
Cargese, France, September 26-28
-
S. PIGNY and P. COSTE, "Two-Phase Flow Averaged Codes: Criteria for Numerical Methods," Proc. Workshop Trends in Numerical and Physical Modeling for Industrial Multiphase Flows, Cargese, France, September 26-28, 2001.
-
(2001)
Proc. Workshop Trends in Numerical and Physical Modeling for Industrial Multiphase Flows
-
-
Pigny, S.1
Coste, P.2
-
8
-
-
0001666036
-
"Interfacial Area Modeling for a Multiphase, Multicomponent Fluid-Dynamics Code"
-
Tsukuba, Japan, September 24-27
-
Y. TOBITA, K. MORITA, SA. KONDO, N. SHIRAKAWA, W. R. BOHL, and F. R. PARKER, "Interfacial Area Modeling for a Multiphase, Multicomponent Fluid-Dynamics Code," Proc. Int. Conf. Multiphase Flow, Tsukuba, Japan, September 24-27, 1991.
-
(1991)
Proc. Int. Conf. Multiphase Flow
-
-
Tobita, Y.1
Morita, K.2
Kondo, S.A.3
Shirakawa, N.4
Bohl, W.R.5
Parker, F.R.6
-
9
-
-
0013170126
-
"Thermodynamic Properties and Equations of State for Fast Reactor Safety Analysis, Part I: Analytic Equation-of-State Model"
-
K. MORITA and E. A. FISCHER, "Thermodynamic Properties and Equations of State for Fast Reactor Safety Analysis, Part I: Analytic Equation-of-State Model," Nucl. Eng. Des., 183, 177 (1998).
-
(1998)
Nucl. Eng. Des.
, vol.183
, pp. 177
-
-
Morita, K.1
Fischer, E.A.2
-
10
-
-
0013082192
-
"Thermodynamic Properties and Equations of State for Fast Reactor Safety Analysis, Part II: Properties of Fast Reactor Materials"
-
K. MORITA, E. A. FISCHER, and K. TURNEY, "Thermodynamic Properties and Equations of State for Fast Reactor Safety Analysis, Part II: Properties of Fast Reactor Materials," Nucl. Eng. Des., 183, 193 (1998).
-
(1998)
Nucl. Eng. Des.
, vol.183
, pp. 193
-
-
Morita, K.1
Fischer, E.A.2
Turney, K.3
-
11
-
-
0344488404
-
"Fuel Equation of State Data for Use in Fast Reactor Accident Analysis Codes"
-
KfK4889, Kernforschungszentrum Karlsruhe (May)
-
E. A. FISCHER, "Fuel Equation of State Data for Use in Fast Reactor Accident Analysis Codes," KfK4889, Kernforschungszentrum Karlsruhe (May 1992).
-
(1992)
-
-
Fischer, E.A.1
-
12
-
-
2642585322
-
"A New SIMMER-III Version with Improved Neutronics Solution Algorithms"
-
FZKA 6290
-
G. BUCKEL, E. HESSELSCHWERDT, E. KIEFHABER, S. KLEINHEINS, and W. MASCHEK, "A New SIMMER-III Version with Improved Neutronics Solution Algorithms," FZKA 6290 (1999).
-
(1999)
-
-
Buckel, G.1
Hesselschwerdt, E.2
Kiefhaber, E.3
Kleinheins, S.4
Maschek, W.5
-
13
-
-
2642578799
-
"SIMMER-III, A Code for Analyzing Transients and Accidents in ADS"
-
Washington D.C., November 12-15, 2000, American Nuclear Society
-
W. MASCHEK, A. RINEISKI, K. MORITA, E. KIEFHABER, G. BUCKEL, M. FLAD, P. COSTE, S. PIGNY, G. RIMPAULT, J. LOUVET, T. CADIOU, SA. KONDO, Y. TOBITA, T. SUZUKI, H. YAMANO, and S. FUJITA, "SIMMER-III, A Code for Analyzing Transients and Accidents in ADS," Proc. Int. Topl. Mtg. Nuclear Applications of Accelerator Technology (AccApp'00), Washington D.C., November 12-15, 2000, American Nuclear Society (2000).
-
(2000)
Proc. Int. Topl. Mtg. Nuclear Applications of Accelerator Technology (AccApp'00)
-
-
Maschek, W.1
Rineiski, A.2
Morita, K.3
Kiefhaber, E.4
Buckel, G.5
Flad, M.6
Coste, P.7
Pigny, S.8
Rimpault, G.9
Louvet, J.10
Cadiou, T.11
Kondo, S.A.12
Tobita, Y.13
Suzuki, T.14
Yamano, H.15
Fujita, S.16
-
14
-
-
0018553695
-
"Some Recriticality Studies with SIMMER-II"
-
Seattle, Washington, August 19-23, (1979)
-
W. R. BOHL, "Some Recriticality Studies with SIMMER-II," Proc. Int. Mtg. Fast Reactor Safety Technology, Seattle, Washington, August 19-23, 1979, p. 1415 (1979).
-
(1979)
Proc. Int. Mtg. Fast Reactor Safety Technology
, pp. 1415
-
-
Bohl, W.R.1
-
15
-
-
0010707887
-
"Evaluation of CDA Energetics in the Proto-type LMFBR with Latest Knowledge and Tools"
-
Tokyo, Japan, April 19-23, 1999, Japan Society of Mechanical Engineers/ American Society of Mechanical Engineers/French Nuclear Energy Society
-
Y. TOBITA, K. MORITA, K. KAWADA, H. NIWA, and N. NONAKA, "Evaluation of CDA Energetics in the Proto-type LMFBR with Latest Knowledge and Tools," Proc. 7th Int. Conf. Nuclear Engineering (ICONE-7), Tokyo, Japan, April 19-23, 1999, Japan Society of Mechanical Engineers/American Society of Mechanical Engineers/French Nuclear Energy Society (1999).
-
(1999)
Proc. 7th Int. Conf. Nuclear Engineering (ICONE-7)
-
-
Tobita, Y.1
Morita, K.2
Kawada, K.3
Niwa, H.4
Nonaka, N.5
-
16
-
-
33645017816
-
"SIMMER-II Application and Validation Studies in Japan for Energetics Accommodation of Severe LMFBR Accidents"
-
Knoxville, Tennessee, April 21-25, U.S. Department of Energy (1985)
-
SA. KONDO, A. FURUTANI, and M. ISHIKAWA, "SIMMER-II Application and Validation Studies in Japan for Energetics Accommodation of Severe LMFBR Accidents," Proc. Int. Topl. Mtg. Fast Reactor Safety, Knoxville, Tennessee, April 21-25, 1985, p. 481, U.S. Department of Energy (1985).
-
(1985)
Proc. Int. Topl. Mtg. Fast Reactor Safety
, pp. 481
-
-
Kondo, S.A.1
Furutani, A.2
Ishikawa, M.3
-
17
-
-
0026851157
-
"Investigations of Sloshing Fluid Motions in Pools Related to Recriticalities in Liquid-Metal Fast Breeder Reactor Core Meltdown Accidents"
-
W. MASCHEK, C. D. MUNZ, and L. MEYER, "Investigations of Sloshing Fluid Motions in Pools Related to Recriticalities in Liquid-Metal Fast Breeder Reactor Core Meltdown Accidents," Nucl. Technol., 98, 27 (1992).
-
(1992)
Nucl. Technol.
, Issue.98
, pp. 27
-
-
Maschek, W.1
Munz, C.D.2
Meyer, L.3
-
18
-
-
5644227549
-
"SIMMER-III Analyses of Enhanced Fuel Removal Processes Under Core Disruptive Accident Conditions"
-
San Diego, California, May 10-15, 1998
-
W. MASCHEK, K. MORITA, and M. FLAD, "SIMMER-III Analyses of Enhanced Fuel Removal Processes Under Core Disruptive Accident Conditions," Proc. 6th Int. Conf. Nuclear Engineering (ICONE-6), San Diego, California, May 10-15, 1998 (1998).
-
(1998)
Proc. 6th Int. Conf. Nuclear Engineering (ICONE-6)
-
-
Maschek, W.1
Morita, K.2
Flad, M.3
-
19
-
-
33645025501
-
"Elimination of Recriticality Potential for the Self-Consistent Nuclear Energy System"
-
presented at Int. Seminar Advanced Nuclear Energy Systems Toward Zero Release of Radioactive Waste, Susono Seminar, Shizuoka, Japan
-
H. ENDO, "Elimination of Recriticality Potential for the Self-Consistent Nuclear Energy System," presented at Int. Seminar Advanced Nuclear Energy Systems Toward Zero Release of Radioactive Waste, Susono Seminar, Shizuoka, Japan, 2000.
-
(2000)
-
-
Endo, H.1
-
20
-
-
0034475528
-
"Accident Analyses and Passive Measures Reducing the Consequences of a Core-Melt in CAPRA/CADRA Reactor Cores"
-
W. MASCHEK and D. STRUWE, "Accident Analyses and Passive Measures Reducing the Consequences of a Core-Melt in CAPRA/CADRA Reactor Cores," Nucl. Eng. Des., 202, 311 (2000).
-
(2000)
Nucl. Eng. Des.
, vol.202
, pp. 311
-
-
Maschek, W.1
Struwe, D.2
-
21
-
-
0013170129
-
"An Analysis of Boiling Fuel Pool Experiment by SIMMER-III"
-
Kyoto, Japan, September 30-October 4, (1997)
-
Y. TOBITA, "An Analysis of Boiling Fuel Pool Experiment by SIMMER-III," Proc. 8th Int. Topl. Mtg. Nuclear Reactor Thermal-Hydraulics (NURETH-8), Kyoto, Japan, September 30-October 4, 1997, Vol. 3, p. 1357 (1997).
-
(1997)
Proc. 8th Int. Topl. Mtg. Nuclear Reactor Thermal-Hydraulics (NURETH-8)
, vol.3
, pp. 1357
-
-
Tobita, Y.1
-
22
-
-
33645016681
-
"Current Status of Thermohydraulic Validation Studies at CEA-Grenoble for the SIMMER-III Code"
-
presented at International Atomic Energy Agency/International Working Group on Fast Reactors Technical Committee Mtg. Methods and Codes for Calculations of Thermohydraulic Parameters for LMFRs, Obninsk, Russia, August
-
P. COSTE, S. PIGNY, and R. MEIGNEN, "Current Status of Thermohydraulic Validation Studies at CEA-Grenoble for the SIMMER-III Code," presented at International Atomic Energy Agency/ International Working Group on Fast Reactors Technical Committee Mtg. Methods and Codes for Calculations of Thermohydraulic Parameters for LMFRs, Obninsk, Russia, August 1998.
-
(1998)
-
-
Coste, P.1
Pigny, S.2
Meignen, R.3
-
23
-
-
33645034283
-
"SIMMER-III Applications to Fuel-Coolant Interactions"
-
Kyoto, Japan, September 30-October 4, (1997)
-
K. MORITA, Y. TOBITA, SA. KONDO, and N. NONAKA, "SIMMER-III Applications to Fuel-Coolant Interactions," Proc. 8th Int. Topl. Mtg. Nuclear Reactor Thermal-Hydraulics (NURETH-8), Kyoto, Japan, September 30-October 4, 1997, Vol. 3, p. 1340 (1997).
-
(1997)
Proc. 8th Int. Topl. Mtg. Nuclear Reactor Thermal-Hydraulics (NURETH-8)
, vol.3
, pp. 1340
-
-
Morita, K.1
Tobita, Y.2
Kondo, S.A.3
Nonaka, N.4
-
24
-
-
5644227549
-
"SIMMER-III Analysis of Enhanced Fuel Removal Processes Under Core Disruptive Accident Conditions"
-
San Diego, California, May 10-15, 1998, American Society of Mechanical Engineers
-
W. MASCHEK and K. MORITA, "SIMMER-III Analysis of Enhanced Fuel Removal Processes Under Core Disruptive Accident Conditions," Proc. 6th Int. Conf. Nuclear Engineering (ICONE-6), San Diego, California, May 10-15, 1998, American Society of Mechanical Engineers (1998).
-
(1998)
Proc. 6th Int. Conf. Nuclear Engineering (ICONE-6)
-
-
Maschek, W.1
Morita, K.2
-
25
-
-
0345350767
-
"Experiments on the Behaviour of Thermite Melt Injected into Sodium - Final Report on the THINA Tests Results"
-
O-arai, Ibaraki, Japan, June 6-9, International Atomic Energy Agency/ International Working Group on Fast Reactors (1994)
-
F. HUBER and A. KEISER, "Experiments on the Behaviour of Thermite Melt Injected into Sodium - Final Report on the THINA Tests Results," Proc. Technical Committee Mtg. Material-Coolant Interactions and Material Movement and Relocation in LMFRs, O-arai, Ibaraki, Japan, June 6-9, 1994, p. 167, International Atomic Energy Agency/International Working Group on Fast Reactors (1994).
-
(1994)
Proc. Technical Committee Mtg. Material-Coolant Interactions and Material Movement and Relocation in LMFRs
, pp. 167
-
-
Huber, F.1
Keiser, A.2
-
26
-
-
33645017029
-
"Results of Recent Reactor Materials Tests on Dispersal of Oxide Fuel from a Disrupted Core"
-
Knoxville, Tennessee, April 21-25, U.S. Department of Energy (1985)
-
B. W. SPENCER, R. J. WILSON, D. L. VETTER, E. G. ERIKSON, and G. DEWEY, "Results of Recent Reactor Materials Tests on Dispersal of Oxide Fuel from a Disrupted Core," Proc. Int. Topl. Mtg. Fast Reactor Safety, Knoxville, Tennessee, April 21-25, 1985, p. 877, U.S. Department of Energy (1985).
-
(1985)
Proc. Int. Topl. Mtg. Fast Reactor Safety
, pp. 877
-
-
Spencer, B.W.1
Wilson, R.J.2
Vetter, D.L.3
Erikson, E.G.4
Dewey, G.5
|