-
2
-
-
22344456016
-
-
Chicago, Illinois, USA, Apr. 25-29, 2004
-
T. Yamamoto, K. Kawashima, “Verification of lattice analysis method through BWR UO2 PIE data analysis,” Proc. Int. Conf on PHYSOR 2004, Chicago, Illinois, USA, Apr. 25-29, 2004 (2004).
-
(2004)
Verification of Lattice Analysis Method through BWR UO2 PIE Data Analysis
-
-
Yamamoto, T.1
Kawashima, K.2
-
3
-
-
33847239551
-
-
Vancouver, Canada, Sep. 10-14
-
T. Yamamoto, S. Kikuchi, K. Kawashima, K. Kamimura, “Experimental results and analysis of core physics experiments, FUBILA, for high burnup BWR full MOX cores,” Proc. Int. Conf. On PHYSOR 2006, Vancouver, Canada, Sep. 10-14, 2006 (2006).
-
(2006)
Experimental Results and Analysis of Core Physics Experiments, FUBILA, for High Burnup BWR Full MOX Cores
-
-
Yamamoto, T.1
Kikuchi, S.2
Kawashima, K.3
Kamimura, K.4
-
4
-
-
33845739804
-
Analysis of reactor physics experiment for the irradiated LWR MOX fuels
-
Reno, NV, USA, Jun. 4-8, 2006, Paper 6077
-
K. Kawashima, T. Yamamoto, K. Kamimura, “Analysis of reactor physics experiment for the irradiated LWR MOX fuels,” Proc. Int. Conf. On ICAPP’06, Reno, NV, USA, Jun. 4-8, 2006, Paper 6077 (2006).
-
(2006)
Proc. Int. Conf. On ICAPP’06
-
-
Kawashima, K.1
Yamamoto, T.2
Kamimura, K.3
-
5
-
-
44949106121
-
Irradiation characteristics of BWR high burn up 9 x9 lead use assemblies
-
Kyoto, Japan, Oct. 2-6, 2005
-
Y. Hirano et al., “Irradiation characteristics of BWR high burn up 9 x9 lead use assemblies,” Proc. Int. Conf. On International Topical Meeting on Light Water Reactor Fuel Performance, Kyoto, Japan, Oct. 2-6, 2005 (2005).
-
(2005)
Proc. Int. Conf. On International Topical Meeting on Light Water Reactor Fuel Performance
-
-
Hirano, Y.1
-
7
-
-
0036468668
-
Nuclide composition benchmark data set for verifying burnup codes on spent light water reactor fuel
-
Y. Nakahara, K. Suyama, J. Inagawa et al., “Nuclide composition benchmark data set for verifying burnup codes on spent light water reactor fuel,” Nucl. Technol., 137, 111 (2002).
-
(2002)
Nucl. Technol.
, vol.137
, pp. 111
-
-
Nakahara, Y.1
Suyama, K.2
Inagawa, J.3
-
9
-
-
0033878248
-
Validation of a continuous-energy monte carlo burn-up code MVP-BURN and its application to analysis of post irradiation experiment
-
K. Okumura, T. Mori, M. Nakagawa et al., “Validation of a continuous-energy monte carlo burn-up code MVP-BURN and its application to analysis of post irradiation experiment,” J. Nucl. Sci. Technol., 37[2], 128 (2000).
-
(2000)
J. Nucl. Sci. Technol.
, vol.37
, Issue.2
, pp. 128
-
-
Okumura, K.1
Mori, T.2
Nakagawa, M.3
-
11
-
-
0036872797
-
Japanese evaluated nuclear data library version 3 revision-3: JENDL3.3
-
K. Shibata, T. Kawano, T. Nakagawa et al., “Japanese evaluated nuclear data library version 3 revision-3: JENDL3.3,” J. Nucl. Sci. Technol., 39[11], 1125 (2002).
-
(2002)
J. Nucl. Sci. Technol.
, vol.39
, Issue.11
, pp. 1125
-
-
Shibata, K.1
Kawano, T.2
Nakagawa, T.3
-
12
-
-
24944551409
-
Effect of neutron induced reactions of neodymium-147 and 148 on burnup evaluation
-
K. Suyama, H. Mochizuki, “Effect of neutron induced reactions of neodymium-147 and 148 on burnup evaluation,” J. Nucl. Sci. Technol., 42[7], 661 (2005).
-
(2005)
J. Nucl. Sci. Technol.
, vol.42
, Issue.7
, pp. 661
-
-
Suyama, K.1
Mochizuki, H.2
-
14
-
-
0343326446
-
MOX fuel core physics experiments and analysis-aiming for Plutonium effective use
-
[in Japanese]
-
K. Kanda, T. Yamamoto, H. Matuura et al., “MOX fuel core physics experiments and analysis-aiming for Plutonium effective use-,” Nihon-Genshiryoku-Gakkai Shi (J. At. Energy Soc. Jpn.), 40[11], 834 (1998), [in Japanese].
-
(1998)
Nihon-Genshiryoku-Gakkai Shi (J. At. Energy Soc. Jpn.)
, vol.40
, Issue.11
, pp. 834
-
-
Kanda, K.1
Yamamoto, T.2
Matuura, H.3
-
16
-
-
44849133596
-
“Prediction of spent MOX and LEU fuel composition and comparison with measurements
-
Pittsburgh, Pennsylvania, USA, May 7-12, 2000
-
B. D. Murphy, R. T. Primm III, “Prediction of spent MOX and LEU fuel composition and comparison with measurements, Proc. Physor 2000, Pittsburgh, Pennsylvania, USA, May 7-12, 2000 (2000).
-
(2000)
Proc. Physor 2000
-
-
Murphy, B.D.1
Primm, R.T.2
-
17
-
-
44849144762
-
“Validation of lattice analysis method through PIE data of high burn-up BWR UO2 fuel
-
Prague, Czech Republic, May 11 and 12, 2006
-
T. Yamamoto, K. Kawashima, K. Kamimura, “Validation of lattice analysis method through PIE data of high burn-up BWR UO2 fuel, Proc. Workshop on the Need for Postirradiation Experiments to Validate Fuel Depletion Calculation Methodologies, Prague, Czech Republic, May 11 and 12, 2006 (2006).
-
(2006)
Proc. Workshop on the Need for Postirradiation Experiments to Validate Fuel Depletion Calculation Methodologies
-
-
Yamamoto, T.1
Kawashima, K.2
Kamimura, K.3
-
18
-
-
85010548558
-
Development and verification of Monte Carlo burnup calculation system
-
Tokai, Japan, Oct. 20-24, 2003
-
Y. Ando, K. Yoshioka, I. Mitsuhashi et al., “Development and verification of Monte Carlo burnup calculation system,” Proc. Int. Conf. on the ICNC2003, Tokai, Japan, Oct. 20-24, 2003 (2003).
-
(2003)
Proc. Int. Conf. On the ICNC2003
-
-
Ando, Y.1
Yoshioka, K.2
Mitsuhashi, I.3
-
19
-
-
84951328342
-
“Experimental validation of the code system “DARWIN for spent fuel isotopic predictions in fuel cycle applications
-
Seoul, Korea, Oct. 7-10, 2002
-
B. Roque, N. Thiollay, P. Marimbeau et al., “Experimental validation of the code system “DARWIN for spent fuel isotopic predictions in fuel cycle applications, Proc. Int. Conf on the PHYSOR 2002, Seoul, Korea, Oct. 7-10, 2002 (2002).
-
(2002)
Proc. Int. Conf on the PHYSOR 2002
-
-
Roque, B.1
Thiollay, N.2
Marimbeau, P.3
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