-
1
-
-
33847211212
-
International Handbook of Evaluated Reactor Physics Benchmark Experiments
-
NEA/NSC/DOC(2006) 1, Nuclear Energy Agency Nuclear Science Committee Mar
-
"International Handbook of Evaluated Reactor Physics Benchmark Experiments," NEA/NSC/DOC(2006) 1, Nuclear Energy Agency Nuclear Science Committee (Mar. 2006).
-
(2006)
-
-
-
2
-
-
36249007747
-
Reevaluation of Experimental Data and Analysis with The Latest Reactor Physics Calculation Method on Fast Experimental Reactor "JOYO" MK-I Performance Tests
-
Japan Nuclear Cycle Development Institute , in Japanese
-
K. YOKOYAMA et al., "Reevaluation of Experimental Data and Analysis with The Latest Reactor Physics Calculation Method on Fast Experimental Reactor "JOYO" MK-I Performance Tests," JNC TN9400 2005-024, Japan Nuclear Cycle Development Institute (2005) (in Japanese).
-
(2005)
JNC TN9400 2005-024
-
-
YOKOYAMA, K.1
-
4
-
-
36249018195
-
-
PNC SN94179-191, Power Reactor and Nuclear Fuel Development Corporation , in Japanese
-
T. SANDA et al., "JOYO Start-Up Test Report Control Rod Worth," PNC SN94179-191, Power Reactor and Nuclear Fuel Development Corporation (1979) (in Japanese).
-
(1979)
JOYO Start-Up Test Report Control Rod Worth
-
-
SANDA, T.1
-
5
-
-
36248957908
-
Summary of the Initial Criticality and Low Power Tests of JOYO
-
PNC TN94180-171, Power Reactor and Nuclear Fuel Development Corporation , in Japanese
-
K. TERATA et al., "Summary of the Initial Criticality and Low Power Tests of JOYO," PNC TN94180-171, Power Reactor and Nuclear Fuel Development Corporation (1980) (in Japanese).
-
(1980)
-
-
TERATA, K.1
-
6
-
-
36248963000
-
Isothermal Reactivity Coefficient of JOYO Reactor
-
Power Reactor and Nuclear Fuel Development Corporation , in Japanese
-
M. HIROSE et al., "Isothermal Reactivity Coefficient of JOYO Reactor," PNC TN941 79-119, Power Reactor and Nuclear Fuel Development Corporation (1979) (in Japanese).
-
(1979)
PNC TN941
, pp. 79-119
-
-
HIROSE, M.1
-
7
-
-
36249004697
-
SLAROM-UF: Ultra Fine Group Cell Calculation Code for Fast Reactor
-
Japan Nuclear Cycle Development Institute
-
T. HAZAMA et al., "SLAROM-UF: Ultra Fine Group Cell Calculation Code for Fast Reactor," JNC TN9520 2004-001, Japan Nuclear Cycle Development Institute (2004).
-
(2004)
JNC TN9520 2004-001
-
-
HAZAMA, T.1
-
8
-
-
36249026833
-
MK-III Performance Test of Experimental Fast Reactor 'JOYO'-Control Rod Calibration (NT-321)
-
Japan Nuclear Cycle Development Institute
-
G. CHIBA et al. "MK-III Performance Test of Experimental Fast Reactor 'JOYO'-Control Rod Calibration (NT-321)," JNC TN9400 2004-057, Japan Nuclear Cycle Development Institute (2004).
-
(2004)
JNC TN9400 2004-057
-
-
CHIBA, G.1
-
10
-
-
85036976419
-
-
K. OHNISHI et al., Evaluation of Mass Spectrometry Analysis Error by Surface Ionization Type Mass Spectrometer, Statistical Evaluation of Mass Discrimination Effect, PNC TN841-79-47, Power Reactor and Nuclear Fuel Development Corporation (1979) (in Japanese).
-
K. OHNISHI et al., "Evaluation of Mass Spectrometry Analysis Error by Surface Ionization Type Mass Spectrometer, Statistical Evaluation of Mass Discrimination Effect," PNC TN841-79-47, Power Reactor and Nuclear Fuel Development Corporation (1979) (in Japanese).
-
-
-
-
11
-
-
36248959026
-
Re-Evaluation of Hot Spot Factors of JOYO MK-II Core
-
Power Reactor and Nuclear Fuel Development Corporation Apr
-
T. IKEGAMI et al., "Re-Evaluation of Hot Spot Factors of JOYO MK-II Core," PNC TN941 85-74, Power Reactor and Nuclear Fuel Development Corporation (Apr. 1985).
-
(1985)
PNC TN941
, pp. 85-74
-
-
IKEGAMI, T.1
-
12
-
-
85036974300
-
-
T. TAKEDA et al., Study on Neutron Streaming Effect in a Large Fast Critical Assembly (II), PNC TJ265 82-01, Power Reactor and Nuclear Fuel Development Corporation (1982) (in Japanese).
-
T. TAKEDA et al., "Study on Neutron Streaming Effect in a Large Fast Critical Assembly (II)," PNC TJ265 82-01, Power Reactor and Nuclear Fuel Development Corporation (1982) (in Japanese).
-
-
-
-
13
-
-
0029546870
-
Japanese Evaluated Nuclear Data Library Version 3 Revision-2: JENDL-3.2
-
T. NAKAGAWA et al., "Japanese Evaluated Nuclear Data Library Version 3 Revision-2: JENDL-3.2," J. Nucl. Sci. Technol., 32, 12, 1259 (1995).
-
(1995)
J. Nucl. Sci. Technol
, vol.32
, Issue.12
, pp. 1259
-
-
NAKAGAWA, T.1
-
14
-
-
36248940550
-
The Revision of Nuclear Constant Set for Fast Reactor, JFS-3-J3.2
-
4, 335 2002, in Japanese
-
G. CHIBA et al, "The Revision of Nuclear Constant Set for Fast Reactor, JFS-3-J3.2," J. Nucl. Sci. Technol., 1, 4, 335 (2002) (in Japanese).
-
J. Nucl. Sci. Technol
, vol.1
-
-
CHIBA, G.1
-
15
-
-
0036872797
-
Japanese Evaluated Nuclear Data Library Version 3 Revision-3: JENDL-3.3
-
K. SHIBARTA et al., "Japanese Evaluated Nuclear Data Library Version 3 Revision-3: JENDL-3.3," J. Nucl. Sci. Technol., 39, 11, 1125 (2002).
-
(2002)
J. Nucl. Sci. Technol
, vol.39
, Issue.11
, pp. 1125
-
-
SHIBARTA, K.1
-
16
-
-
0037574641
-
The JEF-2.2 Nuclear Data Library
-
OCECD/NEA, Organisation for Economic Co-operation and Development
-
J. BLACHOT et al., "The JEF-2.2 Nuclear Data Library," JEFF Report 17, OCECD/NEA, Organisation for Economic Co-operation and Development (2000).
-
(2000)
JEFF Report
, vol.17
-
-
BLACHOT, J.1
-
17
-
-
36248949967
-
Development of the Unified Cross-Section Set ADJ2000R for Fast Reactor Analysis
-
Japan Nuclear Cycle Development Institute , in Japanese
-
T. HAZAMA et al., "Development of the Unified Cross-Section Set ADJ2000R for Fast Reactor Analysis," JNC TN9400 2002-064, Japan Nuclear Cycle Development Institute (2002) (in Japanese).
-
(2002)
JNC TN9400 2002-064
-
-
HAZAMA, T.1
-
18
-
-
0016538517
-
A Numerical Study of Heterogeneity Effects in Fast Reactor Critical Assemblies
-
T. TONE, "A Numerical Study of Heterogeneity Effects in Fast Reactor Critical Assemblies," J. Nucl. Sci. Technol., 12, 8, 467 (1975).
-
(1975)
J. Nucl. Sci. Technol
, vol.12
, Issue.8
, pp. 467
-
-
TONE, T.1
-
19
-
-
85037002000
-
-
K. SUGINO et al., Advances in Methods of Commercial FBR Core Characteristics Analyses-Investigations of a Treatment of the Double-Heterogeneity and a Method to Calculate Homogenized Control Rod Cross Sections, PNC TN941098-067, Power Reactor and Nuclear Fuel Development Corporation (1998) (in Japanese).
-
K. SUGINO et al., "Advances in Methods of Commercial FBR Core Characteristics Analyses-Investigations of a Treatment of the Double-Heterogeneity and a Method to Calculate Homogenized Control Rod Cross Sections," PNC TN941098-067, Power Reactor and Nuclear Fuel Development Corporation (1998) (in Japanese).
-
-
-
-
20
-
-
0028461431
-
New Control Rod Homogenization Method for Fast Reactors
-
T. KITADA et al., "New Control Rod Homogenization Method for Fast Reactors," J. Nucl. Sci. Technol., 31, 7, 647 (1994).
-
(1994)
J. Nucl. Sci. Technol
, vol.31
, Issue.7
, pp. 647
-
-
KITADA, T.1
-
21
-
-
33748323132
-
Development of a Fine and Ultra-Fine Group Cell Calculation Code SLAROM-UF for Fast Reactor Analyses
-
T. HAZAMA et al., "Development of a Fine and Ultra-Fine Group Cell Calculation Code SLAROM-UF for Fast Reactor Analyses," J. Nucl. Sci. Eng., 43, 8, 908 (2006).
-
(2006)
J. Nucl. Sci. Eng
, vol.43
, Issue.8
, pp. 908
-
-
HAZAMA, T.1
-
22
-
-
85037005600
-
-
M. NAKAGAWA et al., Code System for Fast Reactor Neutronic Analysis, JAERI-M 83-066, Japan Atomic Energy Research Institute (1983) (in Japanese).
-
M. NAKAGAWA et al., "Code System for Fast Reactor Neutronic Analysis," JAERI-M 83-066, Japan Atomic Energy Research Institute (1983) (in Japanese).
-
-
-
-
23
-
-
0001306283
-
Streaming Effects and Collision Probabilities in Lattices
-
P. BENOIST, "Streaming Effects and Collision Probabilities in Lattices," Nucl. Sci. Eng., 34, 285 (1968).
-
(1968)
Nucl. Sci. Eng
, vol.34
, pp. 285
-
-
BENOIST, P.1
-
24
-
-
0022796973
-
Three-Dimensional Transport Correction in Fast Reactor Core Analysis
-
T. YAMAMOTO et al., "Three-Dimensional Transport Correction in Fast Reactor Core Analysis," J. Nucl. Sci. Technol., 23, 10, 849 (1986).
-
(1986)
J. Nucl. Sci. Technol
, vol.23
, Issue.10
, pp. 849
-
-
YAMAMOTO, T.1
-
25
-
-
0041919401
-
A Combined Method to Evaluate the Resonance Self Shielding Effect in Power Fast Reactor Fuel Assembly Calculation
-
G. CHIBA, "A Combined Method to Evaluate the Resonance Self Shielding Effect in Power Fast Reactor Fuel Assembly Calculation," J. Nucl. Sci. Technol., 40, 7, 537 (2003).
-
(2003)
J. Nucl. Sci. Technol
, vol.40
, Issue.7
, pp. 537
-
-
CHIBA, G.1
-
26
-
-
85010505528
-
JUPITER Experimental Analyses Using a New Constant Set Based on JENDL-3.2
-
K. SUGINO, "JUPITER Experimental Analyses Using a New Constant Set Based on JENDL-3.2," J. Nucl. Sci. Technol., Supplement 2, 1002 (2002).
-
(2002)
J. Nucl. Sci. Technol
, Issue.SUPPL.EMENT 2
, pp. 1002
-
-
SUGINO, K.1
-
27
-
-
0343538480
-
VITAMINE-E: A Coupled 174- Neutron, 38-Gamma-Ray Multigroup Cross-Section Library for Deriving Application-Dependent Working Libraries for Radiation Transport Calculations
-
Oak Ridge National Laboratory
-
R. W. ROUSSIN, "VITAMINE-E: A Coupled 174- Neutron, 38-Gamma-Ray Multigroup Cross-Section Library for Deriving Application-Dependent Working Libraries for Radiation Transport Calculations," DLC-113, Oak Ridge National Laboratory (1984).
-
(1984)
DLC-113
-
-
ROUSSIN, R.W.1
-
28
-
-
36148953772
-
MVP/GMVP II: General Purpose Monte Carlo Codes for Neutron and Photon Transport Calculations Based on Continuous Energy and Multigroup Methods
-
Japan Atomic Energy Research Institute
-
Y. NAGAYA et al., "MVP/GMVP II: General Purpose Monte Carlo Codes for Neutron and Photon Transport Calculations Based on Continuous Energy and Multigroup Methods," JAERI 1348, Japan Atomic Energy Research Institute (2005).
-
(2005)
JAERI 1348
-
-
NAGAYA, Y.1
|