-
1
-
-
77957717240
-
Studies on supercritical water reactor fuel assemblies using the sub-channel code COBRA-EN
-
L. Ammirabile Studies on supercritical water reactor fuel assemblies using the sub-channel code COBRA-EN Nucl. Eng. Des. 240 2010 3087 3094
-
(2010)
Nucl. Eng. Des.
, vol.240
, pp. 3087-3094
-
-
Ammirabile, L.1
-
4
-
-
77954926637
-
-
2009 First International Conference on, pp. 1-5
-
H. Breitkreutz, x Ro, A. hrmoser, and W. Petry 3-Dimensional Coupled Neutronic and Thermohydraulic Calculations for a Compact Core Combining MCNPX and CFX, Advancements in Nuclear Instrumentation Measurement Methods and Their Applications (ANIMMA) 2009 2009 First International Conference on, pp. 1-5
-
(2009)
3-Dimensional Coupled Neutronic and Thermohydraulic Calculations for A Compact Core Combining MCNPX and CFX, Advancements in Nuclear Instrumentation Measurement Methods and Their Applications (ANIMMA)
-
-
Breitkreutz, H.1
Ro, X.2
Hrmoser, A.3
Petry, W.4
-
6
-
-
84872324946
-
-
ANS PHYSOR-2010 Conference Workshop, Pittsburgh, PA
-
F. Brown, W. Martin, J. Leppanen, W. Haeck, and B. Cochet Reactor Physics Analysis with Monte Carlo 2010 ANS PHYSOR-2010 Conference Workshop, Pittsburgh, PA
-
(2010)
Reactor Physics Analysis with Monte Carlo
-
-
Brown, F.1
Martin, W.2
Leppanen, J.3
Haeck, W.4
Cochet, B.5
-
7
-
-
84872327380
-
-
US 3976749 (Aug, 1976) Wedemeyer 423/256; US 4029740 (Jun, 1977) Ervin 423/254; US 4059539 (Nov, 1977) Potter 252/641, US
-
G.C.O.H. Carl A. Alexander Metal-actinide Nitride Nuclear Fuel 1986 US 3976749 (Aug, 1976) Wedemeyer 423/256; US 4029740 (Jun, 1977) Ervin 423/254; US 4059539 (Nov, 1977) Potter 252/641, US
-
(1986)
Metal-actinide Nitride Nuclear Fuel
-
-
Carl, A.1
Alexander, G.C.O.H.2
-
8
-
-
84858720654
-
Development of sub-channel code SACoS and its application in coupled neutronics/thermal hydraulics system for SCWR
-
K.S. Chaudri, Y. Su, R. Chen, W. Tian, G. Su, and S. Qiu Development of sub-channel code SACoS and its application in coupled neutronics/thermal hydraulics system for SCWR Ann. Nucl. Energy 45 2012 37 45
-
(2012)
Ann. Nucl. Energy
, vol.45
, pp. 37-45
-
-
Chaudri, K.S.1
Su, Y.2
Chen, R.3
Tian, W.4
Su, G.5
Qiu, S.6
-
10
-
-
84872327804
-
-
Laboratory Directed Research and Development (LDRD) on Mono-uranium Nitride Fuel Development for SSTAR and Space Applications
-
Choi, J., Ebbinghaus, B., Meiers, T., Ahn, J., 2006. Laboratory Directed Research and Development (LDRD) on Mono-uranium Nitride Fuel Development for SSTAR and Space Applications, Lawrence Livermore National Laboratory (LLNL) Report, UCRL-TR-218931.
-
(2006)
Lawrence Livermore National Laboratory (LLNL) Report, UCRL-TR-218931
-
-
Choi, J.1
Ebbinghaus, B.2
Meiers, T.3
Ahn, J.4
-
11
-
-
33244471559
-
Pseudo material construct for coupled neutronlc-thermal-hydraulic analysis of VHTGR
-
Transactions of the American Nuclear Society - 2005 Annual Meeting
-
J.L. Conlin, W. Ji, J.C. Lee, and W.R. Martin Pseudo material construct for coupled neutronic-thermal-hydraulic analysis of VHTGR Trans. Am. Nucl. Soc. 92 2005 225 227 (Pubitemid 43283239)
-
(2005)
Transactions of the American Nuclear Society
, vol.92
, pp. 225-227
-
-
Conlin, J.L.1
Ji, W.2
Lee, J.C.3
Martin, W.R.4
-
14
-
-
84872294454
-
Evaluation of Alternate Materials for Coated Particle Fuels for the Gas-Cooled Fast Reactor
-
Demkowicz, P.A., Wright, K., Gan, J., Petti, D., Allen T., Blanchard, J., 2006. Evaluation of Alternate Materials for Coated Particle Fuels for the Gas-Cooled Fast Reactor. Laboratory Directed Research and Development Program FY 2006 Final Report, Idaho National Laboratory (INL) Report, INL/EXT-06-11749.
-
(2006)
Laboratory Directed Research and Development Program FY 2006 Final Report, Idaho National Laboratory (INL) Report, INL/EXT-06-11749
-
-
Demkowicz, P.A.1
Wright, K.2
Gan, J.3
Petti, D.4
Allen, T.5
Blanchard, J.6
-
16
-
-
79957779718
-
Long operation life reactor for lunar surface power
-
M.S. El-Genk, and T.M. Schriener Long operation life reactor for lunar surface power Nucl. Eng. Des. 241 2011 2339 2352
-
(2011)
Nucl. Eng. Des.
, vol.241
, pp. 2339-2352
-
-
El-Genk, M.S.1
Schriener, T.M.2
-
17
-
-
2342449329
-
An analysis of coated particles fuel compact-general purpose heat source (CPFC-GPHS)
-
M.S. El-Genk, and J.-M. Tournier An analysis of coated particles fuel compact-general purpose heat source (CPFC-GPHS) Prog. Nucl. Energy 44 2004 215 236
-
(2004)
Prog. Nucl. Energy
, vol.44
, pp. 215-236
-
-
El-Genk, M.S.1
Tournier, J.-M.2
-
21
-
-
80054093483
-
Kinetic study of the reaction between uranium monocarbide and water vapor
-
Y. Hori, and T. Mukaibo Kinetic study of the reaction between uranium monocarbide and water vapor Bull. Chem. Soc. Jpn. 40 1967 1878 1883
-
(1967)
Bull. Chem. Soc. Jpn.
, vol.40
, pp. 1878-1883
-
-
Hori, Y.1
Mukaibo, T.2
-
22
-
-
77953363346
-
Small PWR core design with coated particle based fuel with a novel composition
-
A. Hussain, and C. Xinrong Small PWR core design with coated particle based fuel with a novel composition Prog. Nucl. Energy 52 2010 531 535
-
(2010)
Prog. Nucl. Energy
, vol.52
, pp. 531-535
-
-
Hussain, A.1
Xinrong, C.2
-
23
-
-
84872357428
-
Hyperion Power Generation, Denver. J.P G., (1972), Phase relationships in the ternary system U-Ni-N
-
H.P.G. Inc Hyperion Power Generation, Denver. J.P G., (1972), Phase relationships in the ternary system U-Ni-N J. Nucl. Mater. 45 2011 40 46
-
(2011)
J. Nucl. Mater.
, vol.45
, pp. 40-46
-
-
Inc, H.P.G.1
-
24
-
-
33644890439
-
HTGR reactor physics and fuel cycle studies
-
J.C. Kuijper, X. Raepsaet, J.B.M. de Haas, W. von Lensa, U. Ohlig, H.J. Ruetten, H. Brockmann, F. Damian, F. Dolci, W. Bernnat, J. Oppe, J.L. Kloosterman, N. Cerullo, G. Lomonaco, A. Negrini, J. Magill, and R. Seiler HTGR reactor physics and fuel cycle studies Nucl. Eng. Des. 236 2006 615 634
-
(2006)
Nucl. Eng. Des.
, vol.236
, pp. 615-634
-
-
Kuijper, J.C.1
Raepsaet, X.2
De Haas, J.B.M.3
Von Lensa, W.4
Ohlig, U.5
Ruetten, H.J.6
Brockmann, H.7
Damian, F.8
Dolci, F.9
Bernnat, W.10
Oppe, J.11
Kloosterman, J.L.12
Cerullo, N.13
Lomonaco, G.14
Negrini, A.15
Magill, J.16
Seiler, R.17
-
25
-
-
0034818737
-
Investigation of the use of ceramic materials in innovative light water reactor - fuel rod concepts
-
DOI 10.1016/S0029-5493(00)00369-1
-
W. Lippmann, J. Knorr, R. Nöring, and M. Umbreit Investigation of the use of ceramic materials in innovative light water reactor-fuel rod concepts Nucl. Eng. Des. 205 2001 13 22 (Pubitemid 32874668)
-
(2001)
Nuclear Engineering and Design
, vol.205
, Issue.1-2
, pp. 13-22
-
-
Lippmann, W.1
Knorr, J.2
Noring, R.3
Umbreit, M.4
-
26
-
-
68149181757
-
Core and sub-channel evaluation of a thermal SCWR
-
X.J. Liu, and X. Cheng Core and sub-channel evaluation of a thermal SCWR Nucl. Eng. Technol. 41 2009
-
(2009)
Nucl. Eng. Technol.
, vol.41
-
-
Liu, X.J.1
Cheng, X.2
-
27
-
-
58149133576
-
Thermal-hydraulic and neutron-physical characteristics of a new SCWR fuel assembly
-
X.J. Liu, and X. Cheng Thermal-hydraulic and neutron-physical characteristics of a new SCWR fuel assembly Ann. Nucl. Energy 36 2009 28 36
-
(2009)
Ann. Nucl. Energy
, vol.36
, pp. 28-36
-
-
Liu, X.J.1
Cheng, X.2
-
28
-
-
70450221938
-
Safety analysis of reactivity initiated accidents in a HPLWR reactor by the coupled ATHLET-KIKO3D code
-
C. Maráczy, A. Keresztúri, I. Trosztel, and G. Hegyi Safety analysis of reactivity initiated accidents in a HPLWR reactor by the coupled ATHLET-KIKO3D code Prog. Nucl. Energy 52 2010 190 196
-
(2010)
Prog. Nucl. Energy
, vol.52
, pp. 190-196
-
-
Maráczy, C.1
Keresztúri, A.2
Trosztel, I.3
Hegyi, G.4
-
29
-
-
22044439335
-
-
MatWeb
-
MatWeb, 2012. MatWeb Material Property Data, http://www.matweb.com/ search/DataSheet.aspx?MatGUID=94950a2d209040a09b89952d45086134.
-
(2012)
MatWeb Material Property Data
-
-
-
31
-
-
34547849542
-
Thermomechanics of candidate coatings for advanced gas reactor fuels
-
DOI 10.1016/j.jnucmat.2007.05.014, PII S0022311507007593, Nuclear Fuels and Structural Materials 1
-
A. Nosek, J. Conzen, H. Doescher, C. Martin, and J. Blanchard Thermomechanics of candidate coatings for advanced gas reactor fuels J. Nucl. Mater. 371 2007 288 303 (Pubitemid 47247744)
-
(2007)
Journal of Nuclear Materials
, vol.371
, Issue.1-3
, pp. 288-303
-
-
Nosek, A.1
Conzen, J.2
Doescher, H.3
Martin, C.4
Blanchard, J.5
-
32
-
-
0041781613
-
Analysis of burnup and economic potential of alternative fuel materials in thermal reactors
-
S.M. Oggianu, H.C. No, and M.S. Kazimi Analysis of burnup and economic potential of alternative fuel materials in thermal reactors Nucl. Technol. 143 2003 256 269
-
(2003)
Nucl. Technol.
, vol.143
, pp. 256-269
-
-
Oggianu, S.M.1
No, H.C.2
Kazimi, M.S.3
-
33
-
-
0031627948
-
Conceptual design study of advanced power reactors
-
PII S0149197097000140
-
Y. Oka, and S. Koshizuka Conceptual design study of advanced power reactors Prog. Nucl. Energy 32 1998 163 177 (Pubitemid 128392202)
-
(1998)
Progress in Nuclear Energy
, vol.32
, Issue.1-2
, pp. 163-177
-
-
Oka, Y.1
Koshizuka, S.2
-
35
-
-
84950621772
-
Direct cycle light water reactor operating at supercritical pressure
-
Y. Oka, S. Koshizuka, and T. Yamasaki Direct cycle light water reactor operating at supercritical pressure J. Nucl. Sci. Technol. 29 1992
-
(1992)
J. Nucl. Sci. Technol.
, vol.29
-
-
Oka, Y.1
Koshizuka, S.2
Yamasaki, T.3
-
37
-
-
84872336503
-
-
ASME Conference Proceedings 2010, pp. 767-774
-
C. Pascoe, A. Milner, H. Patel, W. Peiman, G. Richards, L. Grande, and I. Pioro Thermal Aspects of Using Uranium Dicarbide Fuel in an SCWR at Maximum Heat-flux Conditions 2010 ASME Conference Proceedings 2010, pp. 767-774
-
(2010)
Thermal Aspects of Using Uranium Dicarbide Fuel in An SCWR at Maximum Heat-flux Conditions
-
-
Pascoe, C.1
Milner, A.2
Patel, H.3
Peiman, W.4
Richards, G.5
Grande, L.6
Pioro, I.7
-
39
-
-
70450224482
-
The Simplified Supercritical Water-Cooled Reactor (SSCWR), a new SCWR design
-
T. Reiss, G. Csom, S. Fehér, and S. Czifrus The Simplified Supercritical Water-Cooled Reactor (SSCWR), a new SCWR design Prog. Nucl. Energy 52 2010 177 189
-
(2010)
Prog. Nucl. Energy
, vol.52
, pp. 177-189
-
-
Reiss, T.1
Csom, G.2
Fehér, S.3
Czifrus, S.4
-
40
-
-
78649688141
-
Reactor Physics Simulations with Coupled Monte Carlo Calculations and Computational Fluid Dynamics
-
Istanbul, Turkey
-
Seker, V., Thomas, J.W., Downar, T.J., 2007. Reactor Physics Simulations with Coupled Monte Carlo Calculations and Computational Fluid Dynamics, International Conference on Emerging Nuclear Energy Systems (ICENES-2007), Istanbul, Turkey.
-
(2007)
International Conference on Emerging Nuclear Energy Systems (ICENES-2007)
-
-
Seker, V.1
Thomas, J.W.2
Downar, T.J.3
-
41
-
-
68349117275
-
SCWR subchannel code ATHAS development and CANDU-SCWR analysis
-
J. Shan, B. Zhang, C. Li, and L.K.H. Leung SCWR subchannel code ATHAS development and CANDU-SCWR analysis Nucl. Eng. Des. 239 2009 1979 1987
-
(2009)
Nucl. Eng. Des.
, vol.239
, pp. 1979-1987
-
-
Shan, J.1
Zhang, B.2
Li, C.3
Leung, L.K.H.4
-
42
-
-
44149088529
-
SSTAR: The U.S. Lead-Cooled fast reactor (LFR)
-
C.F. Smith, W.G. Halsey, N.W. Brown, J.J. Sienicki, A. Moisseytsev, and D.C. Wade SSTAR: the U.S. Lead-Cooled fast reactor (LFR) J. Nucl. Mater. 326 2007 255 259
-
(2007)
J. Nucl. Mater.
, vol.326
, pp. 255-259
-
-
Smith, C.F.1
Halsey, W.G.2
Brown, N.W.3
Sienicki, J.J.4
Moisseytsev, A.5
Wade, D.C.6
-
43
-
-
0037375804
-
High performance light water reactor
-
D. Squarer, T. Schulenberg, D. Struwe, Y. Oka, D. Bittermann, N. Aksan, C. Maraczy, R. Kyrki-Rajamäki, A. Souyri, and P. Dumaz High performance light water reactor Nucl. Eng. Des. 221 2003 167 180
-
(2003)
Nucl. Eng. Des.
, vol.221
, pp. 167-180
-
-
Squarer, D.1
Schulenberg, T.2
Struwe, D.3
Oka, Y.4
Bittermann, D.5
Aksan, N.6
Maraczy, C.7
Kyrki-Rajamäki, R.8
Souyri, A.9
Dumaz, P.10
-
45
-
-
17644439858
-
XPS and XRD studies of corrosion of uranium nitride by water
-
PII S0925838898001571
-
S. Sunder, and N.H. Miller XPS and XRD studies of corrosion of uranium nitride by water J. Alloys Compd. 271-273 1998 568 572 (Pubitemid 128425026)
-
(1998)
Journal of Alloys and Compounds
, vol.271-273
, pp. 568-572
-
-
Sunder, S.1
Miller, N.H.2
-
46
-
-
84861611666
-
Microencapsulated fuel technology for commercial light water and advanced reactor application
-
K.A. Terrani, L.L. Snead, and J.C. Gehin Microencapsulated fuel technology for commercial light water and advanced reactor application J. Nucl. Mater. 427 2012 209 224
-
(2012)
J. Nucl. Mater.
, vol.427
, pp. 209-224
-
-
Terrani, K.A.1
Snead, L.L.2
Gehin, J.C.3
-
50
-
-
0036568015
-
Improved cross-section modeling methodology for coupled three-dimensional transient simulations
-
DOI 10.1016/S0306-4549(01)00085-8, PII S0306454901000858
-
J.K. Watson, and K.N. Ivanov Improved cross-section modeling methodology for coupled three-dimensional transient simulations Ann. Nucl. Energy 29 2002 937 966 (Pubitemid 34100028)
-
(2002)
Annals of Nuclear Energy
, vol.29
, Issue.8
, pp. 937-966
-
-
Watson, J.K.1
Ivanov, K.N.2
-
51
-
-
84869053209
-
Uranium Mononitride as a Potential Commercial LWR Fuel
-
Chicago, Illinois, USA
-
Xu, P., Lahoda, E.J., Johnson, S.C., Baranwal, R., Ray, S., 2012. Uranium Mononitride as a Potential Commercial LWR Fuel, International Congress on the Advances in Nuclear Power Plants, Chicago, Illinois, USA.
-
(2012)
International Congress on the Advances in Nuclear Power Plants
-
-
Xu, P.1
Lahoda, E.J.2
Johnson, S.C.3
Baranwal, R.4
Ray, S.5
-
52
-
-
14844363454
-
Three-dimensional core design of high temperature supercritical-pressure light water reactor with neutronic and thermal-hydraulic coupling
-
A. Yamaji, Y. Oka, and S. Koshizuka Three-dimensional core design of high temperature supercritical-pressure light water reactor with neutronic and thermal-hydraulic coupling J. Nucl. Sci. Technol. 42 2005 8 19 (Pubitemid 40352103)
-
(2005)
Journal of Nuclear Science and Technology
, vol.42
, Issue.1
, pp. 8-19
-
-
Yamaji, A.1
Oka, Y.2
Koshizuka, S.3
-
53
-
-
0043253075
-
-
PNNL-14116
-
Yang, Z.G., Paxton, D.M., Weil, K.S., Stevenson, J.W., Singh, P., 2002. Materials Properties Database for Selection of High-temperature Alloys and Concepts of Alloy Design for SOFC Applications, Pacific Northwest National Laboratory (PNNL) Report, PNNL-14116.
-
(2002)
Materials Properties Database for Selection of High-temperature Alloys and Concepts of Alloy Design for SOFC Applications, Pacific Northwest National Laboratory (PNNL) Report
-
-
Yang, Z.G.1
Paxton, D.M.2
Weil, K.S.3
Stevenson, J.W.4
Singh, P.5
-
54
-
-
84861828049
-
Fuel residence time in BWRs with nitride fuels
-
J. Zakova, and J. Wallenius Fuel residence time in BWRs with nitride fuels Ann. Nucl. Energy 47 2012 182 191
-
(2012)
Ann. Nucl. Energy
, vol.47
, pp. 182-191
-
-
Zakova, J.1
Wallenius, J.2
|