-
1
-
-
0036872797
-
Japanese Evaluated Nuclear Data Library Version 3 Revision-3: JENDL-3.3
-
K. Shibata, T. Kawano, T. Nakagawa et al., “Japanese Evaluated Nuclear Data Library Version 3 Revision-3: JENDL-3.3,” J. Nucl. Sci. Technol., 39, 1125 (2002).
-
(2002)
J. Nucl. Sci. Technol.
, vol.39
, pp. 1125
-
-
Shibata, K.1
Kawano, T.2
Nakagawa, T.3
-
4
-
-
0029546870
-
Japanese Evaluated Nuclear Data Library Version 3 Revision-2: JENDL-3.2
-
T. Nakagawa, K. Shibata, S. Chiba et al., “Japanese Evaluated Nuclear Data Library Version 3 Revision-2: JENDL-3.2,” J. Nucl. Sci. Technol., 32, 1259 (1995).
-
(1995)
J. Nucl. Sci. Technol.
, vol.32
, pp. 1259
-
-
Nakagawa, T.1
Shibata, K.2
Chiba, S.3
-
5
-
-
33947156628
-
ENDF/B-VII.0: Next generation evaluated nuclear data library for nuclear science and technology
-
M. B. Chadwick, P. ObloZinsky, M. Herman 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
Oblozinsky, P.2
Herman, M.3
-
6
-
-
14844353977
-
Uncertainty analyses of neutron cross sections for 235U in the resonance region
-
235U in the resonance region,” J. Nucl. Sci. Technol., 42, 130 (2005).
-
(2005)
J. Nucl. Sci. Technol.
, vol.42
, pp. 130
-
-
Shibata, K.1
-
7
-
-
0039309659
-
Data Interpretation, Objective Evaluation Procedures and Mathematical Techniques for the Evaluation of Energy-Dependent Ratio, Shape and Cross Section Data
-
W. P. Poenitz, Data Interpretation, Objective Evaluation Procedures and Mathematical Techniques for the Evaluation of Energy-Dependent Ratio, Shape and Cross Section Data, INDC(USA)-85, 249 (1981).
-
(1981)
INDC(USA)-85
, pp. 249
-
-
Poenitz, W.P.1
-
8
-
-
1542527149
-
A Suggested Procedure for Resolving an Anomaly in Least-squares Data Analysis Know as Peelle's Pertinent Puzzle and the General Implications for Nuclear Data Evaluation
-
S. Chiba, D. L. Smith, A Suggested Procedure for Resolving an Anomaly in Least-squares Data Analysis Know as Peelle's Pertinent Puzzle and the General Implications for Nuclear Data Evaluation, ANL/NDM-121 (1991).
-
(1991)
ANL/NDM-121
-
-
Chiba, S.1
Smith, D.L.2
-
10
-
-
34547281767
-
A measurement of the capture-to-fission cross section ratios of uranium-235 and plutonium-239
-
R. E. Bandl, H. Miessner, F. H. Frohner, “A measurement of the capture-to-fission cross section ratios of uranium-235 and plutonium-239,” Nucl. Sci. Eng., 48, 324 (1972).
-
(1972)
Nucl. Sci. Eng.
, vol.48
, pp. 324
-
-
Bandl, R.E.1
Miessner, H.2
Frohner, F.H.3
-
11
-
-
0016468888
-
Measurement of a and the 235U and 239Pu fission and capture cross sections for 10-80keV neutrons
-
239Pu fission and capture cross sections for 10-80keV neutrons,” Sov. At. Energy, 38, 105 (1975).
-
(1975)
Sov. At. Energy
, vol.38
, pp. 105
-
-
Kononov, V.N.1
Poletaev, E.D.2
Yurlov, B.D.3
-
12
-
-
0016944305
-
Measurement of a in the resonance region
-
Yu. V. Ryabov, “Measurement of a in the resonance region,” Sov. At. Energy, 40, 414 (1976).
-
(1976)
Sov. At. Energy
, vol.40
, pp. 414
-
-
Ryabov, Y.V.1
-
13
-
-
34547359685
-
Capture-to-fission ratio of 235U in the neutron energy range from 10 to 500keV
-
235U in the neutron energy range from 10 to 500keV,” Phys. Rev. C, 20, 201 (1979).
-
(1979)
Phys. Rev.C
, vol.20
, pp. 201
-
-
Beer, H.1
Kappeler, F.2
-
14
-
-
85009807781
-
-
INDC(CCP)-169
-
V. P. Vertebnyy, N. L. Gnidak, A. V. Grebnev et al., Determination of Total Cross-Section and Scattering Cross-Section of Uranium-235 for Neutron Energies 2 and 24.4 keV, INDC(CCP)-169, 2, 254 (1980).
-
(1980)
Determination of Total Cross-Section and Scattering Cross-Section of Uranium-235 for Neutron Energies 2 and 24.4 Kev
, vol.2
, pp. 254
-
-
Vertebnyy, V.P.1
Gnidak, N.L.2
Grebnev, A.V.3
-
15
-
-
85010632210
-
-
INDC(CCP)-169
-
G. V. Muradyan, Yu. G. Shchepkin, Yu. V. Adamchuk et al., Measurement of the Absolute Value of the Alpha for Uranium-235 in the Neutron Energy Region 0.1-30keV, INDC(CCP)-169, 2, 119 (1980).
-
(1980)
Measurement of the Absolute Value of the Alpha for Uranium-235 in the Neutron Energy Region 0.1-30Kev
, vol.2
, pp. 119
-
-
Muradyan, G.V.1
Shchepkin, Y.G.2
Adamchuk, Y.V.3
-
20
-
-
34547381525
-
Measurement of the neutron capture and fission cross sections and of their ratio, alpha, for 233U, 235U, and 239Pu
-
Paris, France, Oct. 17-21, 1966
-
239Pu,” Proc. Conf. Nuclear Data, Microscopic Cross Sections, and Other Data Basic for Reactors, Paris, France, Oct. 17-21, 1966, 2, 233 (1966).
-
(1966)
Proc. Conf. Nuclear Data, Microscopic Cross Sections, and Other Data Basic for Reactors
, vol.2
, pp. 233
-
-
De Saussure, G.1
Weston, L.W.2
Gwin, R.3
-
21
-
-
85010544628
-
-
compiled by the Nuclear Reaction Data Centres Network (NRDC)
-
EXFOR (Experimental Nuclear Reaction Database), compiled by the Nuclear Reaction Data Centres Network (NRDC), retrieved at http://www.jcprg.org/exfor/.
-
-
-
-
22
-
-
0015665689
-
Simultaneous measurements of the neutron fission and capture cross sections for uranium-235 for neutron energies from 8eV to 10keV
-
R. B. Perez, G. de Saussure, E. G. Silver et al., “Simultaneous measurements of the neutron fission and capture cross sections for uranium-235 for neutron energies from 8eV to 10keV,” Nucl. Sci. Eng., 52, 46 (1973).
-
(1973)
Nucl. Sci. Eng.
, vol.52
, pp. 46
-
-
Perez, R.B.1
De Saussure, G.2
Silver, E.G.3
-
23
-
-
13244268377
-
Verification of a nuclear analysis system for fast reactors using BFS-62 critical experiment
-
T. Hazama, A. Shono, K. Sugino, “Verification of a nuclear analysis system for fast reactors using BFS-62 critical experiment,” J. Nucl. Sci. Technol., 41, 1145 (2004).
-
(2004)
J. Nucl. Sci. Technol.
, vol.41
, pp. 1145
-
-
Hazama, T.1
Shono, A.2
Sugino, K.3
-
24
-
-
4243610319
-
SAGEP: Two-dimensional Sensitivity Analysis Code Based on Generalized Perturbation Theory
-
A. Hara, T. Takeda, Y. Kikuchi, SAGEP: Two-dimensional Sensitivity Analysis Code Based on Generalized Perturbation Theory, JAERI-M 84-027 (1984).
-
(1984)
JAERI-M
, pp. 84
-
-
Hara, A.1
Takeda, T.2
Kikuchi, Y.3
-
25
-
-
85010580206
-
-
Private communication
-
T. Hazama, Private communication (2006).
-
(2006)
-
-
Hazama, T.1
-
27
-
-
0033079754
-
R-matrix analysis of 235U neutron transmission and cross-section measurements in the 0- to 225-eV energy range
-
235U neutron transmission and cross-section measurements in the 0- to 225-eV energy range,” Nucl. Sci. Eng., 131, 230 (1999).
-
(1999)
Nucl. Sci. Eng.
, vol.131
, pp. 230
-
-
Leal, L.C.1
Demen, H.2
Larson, N.M.3
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