-
2
-
-
0141946798
-
APOLLO2 twelve years later
-
Madrid, Spain
-
S. LOUBIERE, R. SANCHEZ, M. COSTE, A. HEBERT, and Z. STANKOVSKI, "APOLLO2 Twelve Years Later," Proc. M&C'99, Madrid, Spain (1999).
-
(1999)
Proc. M&C'99
-
-
Loubiere, S.1
Sanchez, R.2
Coste, M.3
Hebert, A.4
Stankovski, Z.5
-
3
-
-
24744459899
-
System 80+ plutonium disposition capability
-
September 12-17, Seattle, Washington
-
M. W. CRUMP and E. P. FLYNN, "System 80+ Plutonium Disposition Capability," presented at GLOBAL'93, September 12-17, 1993, Seattle, Washington.
-
(1993)
GLOBAL'93
-
-
Crump, M.W.1
Flynn, E.P.2
-
4
-
-
4444275107
-
100% MOX cores? Nearly no problem
-
Sep.
-
J. NEDDERMAN, "100% MOX Cores? Nearly No Problem," Nucl. Eng. Int., 41 (Sep. 1996).
-
(1996)
Nucl. Eng. Int.
, vol.41
-
-
Nedderman, J.1
-
5
-
-
0346039420
-
1300 MWe PWR, A new step in full MOX core design
-
Jackson Hole, Wyoming
-
G. ROUVIÈRE, G. BRUNA, J. L. GUILLET, and J. PELET, "1300 MWe PWR, A New Step in Full MOX Core Design," presented at GLOBAL '99, Jackson Hole, Wyoming, 1999.
-
(1999)
GLOBAL '99
-
-
Rouvière, G.1
Bruna, G.2
Guillet, J.L.3
Pelet, J.4
-
6
-
-
31144453596
-
Plutonium management and multirecycling in LWRs using a U-235 support
-
Jackson Hole, Wyoming
-
G. YOUINOU, M. DELPECH, A. PUILL, S. ANIEL, and J. L. GUILLET, "Plutonium Management and Multirecycling in LWRs Using a U-235 Support," presented at GLOBAL '99, Jackson Hole, Wyoming, 1999.
-
(1999)
GLOBAL '99
-
-
Youinou, G.1
Delpech, M.2
Puill, A.3
Aniel, S.4
Guillet, J.L.5
-
7
-
-
84866722144
-
A 100% MOX core design using a highly moderated concept
-
Yokohama, Japan
-
R. GIRIEUD, B. GUIGON, R. LENAIN, N. BARBET, and E. ROYER, "A 100% MOX Core Design Using a Highly Moderated Concept," presented at GLOBAL '97, Yokohama, Japan, 1997.
-
(1997)
GLOBAL '97
-
-
Girieud, R.1
Guigon, B.2
Lenain, R.3
Barbet, N.4
Royer, E.5
-
8
-
-
0343586611
-
Plutonium recycling in pressurized water reactors: Influence of the moderator-to-fuel ratio
-
J. L. KLOOSTERMAN and E. E. BENDE, "Plutonium Recycling in Pressurized Water Reactors: Influence of the Moderator-to-Fuel Ratio," Nucl. Technol., 130, 227 (2000).
-
(2000)
Nucl. Technol.
, vol.130
, pp. 227
-
-
Kloosterman, J.L.1
Bende, E.E.2
-
9
-
-
24744431894
-
Plutonium and americium multirecycling in a GenIII PWR using MOX-UE fuel assemblies
-
New Orleans, Louisiana
-
G. YOUINOU, F. VARAINE, and A. VASILE, "Plutonium and Americium Multirecycling in a GenIII PWR Using MOX-UE Fuel Assemblies," presented at GLOBAL 2003, New Orleans, Louisiana, 2003.
-
(2003)
GLOBAL 2003
-
-
Youinou, G.1
Varaine, F.2
Vasile, A.3
-
10
-
-
0030085763
-
A plutonium-fueled high-moderated pressurized water reactor for the next century
-
P. BARBRAULT, "A Plutonium-Fueled High-Moderated Pressurized Water Reactor for the Next Century," Nucl. Sci. Eng., 122, 240 (1996).
-
(1996)
Nucl. Sci. Eng.
, vol.122
, pp. 240
-
-
Barbrault, P.1
-
11
-
-
2642515251
-
Plutonium recycling in PWR: The CORAIL concept
-
Baltimore, Maryland
-
S. ANIEL, M. ROHART, A. PUILL, J. BERGERON, and G. ROUVIÈRE, "Plutonium Recycling in PWR: The CORAIL Concept," presented at ICONE 8, Baltimore, Maryland, 2000.
-
(2000)
ICONE 8
-
-
Aniel, S.1
Rohart, M.2
Puill, A.3
Bergeron, J.4
Rouvière, G.5
-
12
-
-
2642580926
-
Assessment of a Hetero-geneous PWR assembly for plutonium and minor actinides recycle
-
New Orleans, Louisiana
-
T. A. TAIWO, T. K. KIM, J. A. STILLMAN, R. N. HILL, M. SALVATORES, and P. J. FINCK, "Assessment of a Hetero-geneous PWR Assembly for Plutonium and Minor Actinides Recycle," presented at GLOBAL 2003, New Orleans, Louisiana, 2003.
-
(2003)
GLOBAL 2003
-
-
Taiwo, T.A.1
Kim, T.K.2
Stillman, J.A.3
Hill, R.N.4
Salvatores, M.5
Finck, P.J.6
-
13
-
-
2642515161
-
Heterogeneous assembly for plutonium multirecycling in PWRs: The CORAIL concept
-
Paris, France
-
G. YOUINOU, A. ZAETTA, A. VASILE, M. DELPECH, M. ROHART, and J. L. GUILLET, "Heterogeneous Assembly for Plutonium Multirecycling in PWRs: The CORAIL Concept," presented at GLOBAL 2001, Paris, France, 2001.
-
(2001)
GLOBAL 2001
-
-
Youinou, G.1
Zaetta, A.2
Vasile, A.3
Delpech, M.4
Rohart, M.5
Guillet, J.L.6
-
14
-
-
2642533739
-
Feasibility studies of the CORAIL subassembly for Pu multirecycling in PWRs
-
New Orleans, Louisiana
-
A. VASILE, G. YOUINOU, L. MANDARD, L. BOUCHER, P. LO PINTO, J. L. NIGON, B. BONIN, and D. GRENECHE, "Feasibility Studies of the CORAIL Subassembly for Pu Multirecycling in PWRs," presented at GLOBAL 2003, New Orleans, Louisiana, 2003.
-
(2003)
GLOBAL 2003
-
-
Vasile, A.1
Youinou, G.2
Mandard, L.3
Boucher, L.4
Pinto, P.L.O.5
Nigon, J.L.6
Bonin, B.7
Greneche, D.8
-
15
-
-
0030083266
-
Plutonium burning in pressurized water reactors via nonfertile matrices
-
C. LOMBARDI and A. MAZZOLA, "Plutonium Burning in Pressurized Water Reactors Via Nonfertile Matrices," Nucl. Sci. Eng., 122, 229 (1996).
-
(1996)
Nucl. Sci. Eng.
, vol.122
, pp. 229
-
-
Lombardi, C.1
Mazzola, A.2
-
16
-
-
0038090409
-
Comparison of pressurized water reactor core characteristics for 100% plutonium-containing loadings
-
U. KASEMEYER, J. M. PARATTE, P. GRIMM, and R. CHAWLA, "Comparison of Pressurized Water Reactor Core Characteristics for 100% Plutonium-Containing Loadings," Nucl. Technol., 122, 52 (1998).
-
(1998)
Nucl. Technol.
, vol.122
, pp. 52
-
-
Kasemeyer, U.1
Paratte, J.M.2
Grimm, P.3
Chawla, R.4
-
17
-
-
0034249253
-
Parametric studies on plutonium transmutation using uranium-free fuels in light water reactors
-
A. SHELLEY, H. AKIE, H. TAKANO, and H. SEKI-MOTO, "Parametric Studies on Plutonium Transmutation Using Uranium-Free Fuels in Light Water Reactors," Nucl. Technol., 131, 197 (2000).
-
(2000)
Nucl. Technol.
, vol.131
, pp. 197
-
-
Shelley, A.1
Akie, H.2
Takano, H.3
Seki-Moto, H.4
-
18
-
-
18144451611
-
Comparisons of cell calculations for uranium-free light water reactor fuels
-
J. M. PARATTE, H. AKIE, R. CHAWLA, M. DELPECH, J. L. KLOOSTERMAN, C. LOMBARDI, A. MAZZOLA, S. PELLONI, Y. PÉNÉLIAU, and H. TAKANO, "Comparisons of Cell Calculations for Uranium-Free Light Water Reactor Fuels," Nucl. Technol., 130, 159 (2000).
-
(2000)
Nucl. Technol.
, vol.130
, pp. 159
-
-
Paratte, J.M.1
Akie, H.2
Chawla, R.3
Delpech, M.4
Kloosterman, J.L.5
Lombardi, C.6
Mazzola, A.7
Pelloni, S.8
Pénéliau, Y.9
Takano, H.10
-
19
-
-
0038019971
-
Comparison of various partial light water reactor core loadings with inert matrix and mixed-oxide fuel
-
U. KASEMEYER, C. HELLWIG, J. LEBENHAFT, and R. CHAWLA, "Comparison of Various Partial Light Water Reactor Core Loadings with Inert Matrix and Mixed-Oxide Fuel," J. Nucl. Mater., 319 (2003).
-
(2003)
J. Nucl. Mater.
, vol.319
-
-
Kasemeyer, U.1
Hellwig, C.2
Lebenhaft, J.3
Chawla, R.4
-
20
-
-
2642582611
-
Feasibility of multi-recycling of Pu and MA in PWRs using combined non-fertile UO2 (CONFU) fuel
-
New Orleans, Louisiana
-
E. SHWAGERAUS, P. HEJZLAR, and M. S. KAZIMI, "Feasibility of Multi-Recycling of Pu and MA in PWRs Using Combined Non-Fertile UO2 (CONFU) Fuel," presented at GLOBAL 2003, New Orleans, Louisiana, 2003.
-
(2003)
GLOBAL 2003
-
-
Shwageraus, E.1
Hejzlar, P.2
Kazimi, M.S.3
-
21
-
-
0031198927
-
Advanced plutonium fuel assembly: An advanced concept for using plutonium in pressurized water reactors
-
A. PUILL and J. BERGERON, "Advanced Plutonium Fuel Assembly: An Advanced Concept for Using Plutonium in Pressurized Water Reactors," Nucl. Technol., 119, 119 (1997).
-
(1997)
Nucl. Technol.
, vol.119
, pp. 119
-
-
Puill, A.1
Bergeron, J.2
-
22
-
-
24744437373
-
Mastery of the plutonium inventory in PWRs: The APA concept
-
Jackson Hole, Wyoming
-
A. PUILL, J. BERGERON, and M. ROHART, "Mastery of the Plutonium Inventory in PWRs: The APA Concept," presented at GLOBAL 99, Jackson Hole, Wyoming, 1999.
-
(1999)
GLOBAL 99
-
-
Puill, A.1
Bergeron, J.2
Rohart, M.3
-
23
-
-
2642560809
-
Plutonium and minor actinides recycling in PWRS with new APA concepts
-
Paris, France
-
H. GOLFIER, M. ROHART, S. ANIEL, J. BERGERON, and J. P. DEFFAIN, "Plutonium and Minor Actinides Recycling in PWRs with New APA Concepts," presented at GLOBAL 2001, Paris, France, 2001.
-
(2001)
GLOBAL 2001
-
-
Golfier, H.1
Rohart, M.2
Aniel, S.3
Bergeron, J.4
Deffain, J.P.5
-
24
-
-
2642516041
-
A code for simulating a system of nuclear power reactor and fuel cycle plants
-
Kyoto, Japan
-
J. P. GROUILLER, "A Code for Simulating a System of Nuclear Power Reactor and Fuel Cycle Plants," presented at Int. Conf. Fast Reactors and Related Fuel Cycle, Kyoto, Japan, 1991.
-
(1991)
Int. Conf. Fast Reactors and Related Fuel Cycle
-
-
Grouiller, J.P.1
|