-
1
-
-
0000396671
-
The next generation of fast reactors
-
Adamov The next generation of fast reactors Nuclear Engineering and Design 173 1-3 1997 143 150
-
(1997)
Nuclear Engineering and Design
, vol.173
, Issue.13
, pp. 143-150
-
-
Adamov1
-
2
-
-
0036821791
-
Development of fuels and structural materials for fast breeder reactors
-
Baldev, Mannan, Vasudeva, and Mathew Development of fuels and structural materials for fast breeder reactors Sadhana 27 Part 5 2002 527 558
-
(2002)
Sadhana
, vol.27
, Issue.PART 5
, pp. 527-558
-
-
Baldev1
Mannan2
Vasudeva3
Mathew4
-
3
-
-
33947156628
-
ENDF/B-VII.0: Next generation evaluated nuclear data library for nuclear science and technology
-
Carlson ENDF/B-VII.0: next generation evaluated nuclear data library for nuclear science and technology Nuclear Data Sheets 107 2006 2931 3060
-
(2006)
Nuclear Data Sheets
, vol.107
, pp. 2931-3060
-
-
Carlson1
-
6
-
-
84870366933
-
Feasibility of breeding in hard spectrum boiling water reactors with oxide and nitride fuels
-
MIT-NFC-TR-134
-
Feng, Kazimi, and Forget Feasibility of breeding in hard spectrum boiling water reactors with oxide and nitride fuels Nuclear Fuel Cycle Program MIT-NFC-TR-134 2011
-
(2011)
Nuclear Fuel Cycle Program
-
-
Feng1
Kazimi2
Forget3
-
8
-
-
84948815973
-
Current status and plans for development of NPP with BREST reactors
-
Filin RDIPE, Moscow
-
Filin, 2000. Current status and plans for development of NPP with BREST reactors. In: IAEA Advisory Group Meeting, RDIPE, Moscow.
-
(2000)
IAEA Advisory Group Meeting
-
-
-
9
-
-
84862849964
-
Utilization in Fast Systems: Status of Minor Actinide Fuel Development
-
IAEA NF-T-4.6
-
IAEA, 2009. Utilization in Fast Systems: Status of Minor Actinide Fuel Development, IAEA Nuclear Energy Series, No. NF-T-4.6.
-
(2009)
IAEA Nuclear Energy Series
-
-
-
10
-
-
84862877729
-
-
Retrieved 2010
-
INSC Database, Retrieved 2010. < http://www.insc.anl.gov >.
-
INSC Database
-
-
-
11
-
-
0036378496
-
Feasibility study on nitride fuel core and recycling system toward self-consistent nuclear energy system
-
Kawakita, Ikeda, Moro, Saito, and Sekimoto Feasibility study on nitride fuel core and recycling system toward self-consistent nuclear energy system Progress in Nuclear Energy 40 3-4 2002 597 606
-
(2002)
Progress in Nuclear Energy
, vol.40
, Issue.34
, pp. 597-606
-
-
Kawakita1
Ikeda2
Moro3
Saito4
Sekimoto5
-
15
-
-
33644511162
-
-
Pelowitz Los Alamos National Laboratory
-
Pelowitz, 2008. MCNPX USER'S MANUAL, Los Alamos National Laboratory.
-
(2008)
MCNPX User's Manual
-
-
-
16
-
-
84876365164
-
Mononitride U-Pu mixed fuel and its electrochemical reprocessing in molten salts
-
RDIPE, Moscow, October
-
Rogozkin et al., 2000. Mononitride U-Pu mixed fuel and its electrochemical reprocessing in molten salts. In: IAEA Advisory Group Meeting, RDIPE, Moscow, October.
-
(2000)
IAEA Advisory Group Meeting
-
-
Rogozkin1
-
17
-
-
0038323328
-
The physics of transmutation in critical or subcritical reactors
-
Salvatores The physics of transmutation in critical or subcritical reactors Comptes Rendus Physique 3 2002 999 1012
-
(2002)
Comptes Rendus Physique
, vol.3
, pp. 999-1012
-
-
Salvatores1
-
19
-
-
36148992195
-
Hafnium clad fuels for fast spectrum BWRs
-
Wallenius, and Westlén Hafnium clad fuels for fast spectrum BWRs Annals of Nuclear Energy 35 2008 60 67
-
(2008)
Annals of Nuclear Energy
, vol.35
, pp. 60-67
-
-
Wallenius1
Westlén2
-
20
-
-
0342936099
-
Application of burnable absorbers in an accelerator driven system
-
Wallenius, Tucek, Carlsson, and Gudowski Application of burnable absorbers in an accelerator driven system Nuclear Science and Engineering 137 1 2001 96 106
-
(2001)
Nuclear Science and Engineering
, vol.137
, Issue.1
, pp. 96-106
-
-
Wallenius1
Tucek2
Carlsson3
Gudowski4
-
21
-
-
84862858166
-
A Qualitative Assessment of Thorium-Based Fuels in Supercritical Pressure Water Cooled Reactors
-
Weaver, Kevan, D., MacDonald, P.E., 2002. A Qualitative Assessment of Thorium-Based Fuels in Supercritical Pressure Water Cooled Reactors, PHYSOR 2002.
-
(2002)
PHYSOR 2002
-
-
Weaver, K.D.1
MacDonald, P.E.2
-
22
-
-
24744471463
-
Plutonium multirecycling in standard PWRs loaded with evolutionary fuels
-
Youinou, and Vasile Plutonium multirecycling in standard PWRs loaded with evolutionary fuels Nuclear Science and Engineering 151 2005 25 45
-
(2005)
Nuclear Science and Engineering
, vol.151
, pp. 25-45
-
-
Youinou1
Vasile2
-
23
-
-
79960271332
-
Void reactivity feedback in BWRs with MA bearing MOX fuels
-
Zakova, and Wallenius Void reactivity feedback in BWRs with MA bearing MOX fuels Annals of Nuclear Energy 2011
-
(2011)
Annals of Nuclear Energy
-
-
Zakova1
Wallenius2
-
24
-
-
80051872847
-
Physics and safety studies of a compact ADS design loaded with nitride fuel
-
Zhang, Fokau, Ishida, and Wallenius Physics and safety studies of a compact ADS design loaded with nitride fuel Annals of Nuclear Energy 38 11 2011 2350 2355
-
(2011)
Annals of Nuclear Energy
, vol.38
, Issue.11
, pp. 2350-2355
-
-
Zhang1
Fokau2
Ishida3
Wallenius4
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