-
1
-
-
0000396671
-
The next generation of fast reactors
-
Adamov E., Orlov V., Filin A., Leonov V., Sila-Novitski A., Smirnov V., and Tsikunov V. The next generation of fast reactors. Nucl. Eng. Des. 173 (1997) 143-150
-
(1997)
Nucl. Eng. Des.
, vol.173
, pp. 143-150
-
-
Adamov, E.1
Orlov, V.2
Filin, A.3
Leonov, V.4
Sila-Novitski, A.5
Smirnov, V.6
Tsikunov, V.7
-
2
-
-
33845530610
-
Transuranics recycling in various reactor/fuel cycle systems
-
Albuquerque, NM, USA, November 12-16
-
Aquien A., Kazimi M.S., and Hejzlar P. Transuranics recycling in various reactor/fuel cycle systems. Transactions of the American Nuclear Society, vol. 95. Albuquerque, NM, USA, November 12-16 (2006)
-
(2006)
Transactions of the American Nuclear Society, vol. 95
-
-
Aquien, A.1
Kazimi, M.S.2
Hejzlar, P.3
-
3
-
-
5644290821
-
A description of the S-PRISM plant
-
Baltimore, MD, USA, April 2-6
-
Boardman C.E., et al. A description of the S-PRISM plant. ICONE-8168, Proc. of ICONE-8. Baltimore, MD, USA, April 2-6 (2000)
-
(2000)
ICONE-8168, Proc. of ICONE-8
-
-
Boardman, C.E.1
-
4
-
-
0004281313
-
Comparison of coolants
-
Etherington H. (Ed) (Sect. 9-3, Chap. 6.5)
-
Bonilla C.F. Comparison of coolants. In: Etherington H. (Ed). Nuclear Engineering Handbook (1958) 9-90 (Sect. 9-3, Chap. 6.5)
-
(1958)
Nuclear Engineering Handbook
, pp. 9-90
-
-
Bonilla, C.F.1
-
6
-
-
5644236840
-
Medium power lead alloy fast reactor balance of plant options
-
Dostal V., Hejzlar P., and Todreas N.E. Medium power lead alloy fast reactor balance of plant options. Nucl. Technol. 147 September (2004) 388-405
-
(2004)
Nucl. Technol.
, vol.147
, Issue.September
, pp. 388-405
-
-
Dostal, V.1
Hejzlar, P.2
Todreas, N.E.3
-
7
-
-
70449660630
-
-
Energy Solutions, 2008. GNEP deployment studies: overall summary report. Revision 1, No. DOE/NE/24503.1-1, May 19.
-
Energy Solutions, 2008. GNEP deployment studies: overall summary report. Revision 1, No. DOE/NE/24503.1-1, May 19.
-
-
-
-
8
-
-
0000351691
-
New equations for heat and mass transfer in turbulent pipe and channel flow
-
Gnielinski V. New equations for heat and mass transfer in turbulent pipe and channel flow. Int. Chem. Eng. 16 April (2) (1976) 359-368
-
(1976)
Int. Chem. Eng.
, vol.16
, Issue.April 2
, pp. 359-368
-
-
Gnielinski, V.1
-
9
-
-
70449676301
-
-
GIF, 2002. A technology roadmap for Generation IV nuclear energy systems. GIF-002-00, December.
-
GIF, 2002. A technology roadmap for Generation IV nuclear energy systems. GIF-002-00, December.
-
-
-
-
10
-
-
33847198677
-
Use of beryllium oxide to shape power and reduce void reactivity in gas-cooled fast reactors
-
Vancouver, Canada, September 10-14
-
Handwerk C.S., Driscoll M.J., and Hejzlar P. Use of beryllium oxide to shape power and reduce void reactivity in gas-cooled fast reactors. PHYSOR 2006. Vancouver, Canada, September 10-14 (2006)
-
(2006)
PHYSOR 2006
-
-
Handwerk, C.S.1
Driscoll, M.J.2
Hejzlar, P.3
-
11
-
-
70449689739
-
-
2-cooled fast reactor. MIT-ANP-TR-113, Center for Advanced Nuclear Energy Systems, Massachusetts Institute of Technology.
-
2-cooled fast reactor. MIT-ANP-TR-113, Center for Advanced Nuclear Energy Systems, Massachusetts Institute of Technology.
-
-
-
-
13
-
-
33845732272
-
2 cycle-a promising power conversion system for Generation IV reactors
-
Reno, NV, USA, Paper 6307, June 4-8
-
2 cycle-a promising power conversion system for Generation IV reactors. Proc. International Congress on Advances in Nuclear Power Plants ICAPP'06. Reno, NV, USA, Paper 6307, June 4-8 (2006)
-
(2006)
Proc. International Congress on Advances in Nuclear Power Plants ICAPP'06
-
-
Hejzlar, P.1
Dostal, V.2
Driscoll, M.J.3
-
14
-
-
45149116166
-
Preliminary core design studies for the advanced burner reactor over a wide range of conversion ratios
-
Argonne National Laboratory
-
Hoffman, E.A, Yang, W.S., Hill, R.N., 2006. Preliminary core design studies for the advanced burner reactor over a wide range of conversion ratios. ANL-AFCI-177, Advanced Fuel Cycle Initiative, Argonne National Laboratory.
-
(2006)
ANL-AFCI-177, Advanced Fuel Cycle Initiative
-
-
Hoffman, E.A.1
Yang, W.S.2
Hill, R.N.3
-
15
-
-
0032073301
-
Design and development of fast breeder reactor passive reactivity control systems: LEM and LIM
-
Kambe M., and Uotani M. Design and development of fast breeder reactor passive reactivity control systems: LEM and LIM. Nucl. Technol. 122 May (1998) 179
-
(1998)
Nucl. Technol.
, vol.122
, Issue.May
, pp. 179
-
-
Kambe, M.1
Uotani, M.2
-
16
-
-
0030682849
-
Feasibility study on the reliable steam generator with helically coiled double wall tubes on FBR
-
May 26-30
-
Kubo A., et al. Feasibility study on the reliable steam generator with helically coiled double wall tubes on FBR. ICONE5-2327. May 26-30 (1997)
-
(1997)
ICONE5-2327
-
-
Kubo, A.1
-
17
-
-
46549083293
-
Deteriorated turbulent heat transfer of gas up-flow in a circular tube: experimental data
-
Lee J.I., Hejzlar P., Saha P., Stahle P., Kazimi M.S., and McEligot D.M. Deteriorated turbulent heat transfer of gas up-flow in a circular tube: experimental data. Int. J. Heat Mass Transf. 51 (2008) 3259-3266
-
(2008)
Int. J. Heat Mass Transf.
, vol.51
, pp. 3259-3266
-
-
Lee, J.I.1
Hejzlar, P.2
Saha, P.3
Stahle, P.4
Kazimi, M.S.5
McEligot, D.M.6
-
18
-
-
37749030024
-
Incorporating reliability analysis into the design of passive cooling systems with an application to a gas-cooled reactor
-
Mackay F.J., Apostolakis G., and Hejzlar P. Incorporating reliability analysis into the design of passive cooling systems with an application to a gas-cooled reactor. Nucl. Eng. Des. 238 (2008) 217-228
-
(2008)
Nucl. Eng. Des.
, vol.238
, pp. 217-228
-
-
Mackay, F.J.1
Apostolakis, G.2
Hejzlar, P.3
-
19
-
-
34248996861
-
Advanced core design studies with oxide and metal fuels for next generation sodium-cooled fast reactors
-
Seoul, Korea, Paper 5195, May 15-19
-
Mizuno T., Ogawa T., Sugino K., and Naganuma M. Advanced core design studies with oxide and metal fuels for next generation sodium-cooled fast reactors. Proc. International Congress on Advances in Nuclear Power Plants ICAPP'05. Seoul, Korea, Paper 5195, May 15-19 (2005)
-
(2005)
Proc. International Congress on Advances in Nuclear Power Plants ICAPP'05
-
-
Mizuno, T.1
Ogawa, T.2
Sugino, K.3
Naganuma, M.4
-
20
-
-
70449646444
-
Lead cooled flexible conversion ratio fast reactor
-
Nikiforova A., Hejzlar P., and Todreas N.E. Lead cooled flexible conversion ratio fast reactor. Nucl. Eng. Des. 239 (2009) 2596-2611
-
(2009)
Nucl. Eng. Des.
, vol.239
, pp. 2596-2611
-
-
Nikiforova, A.1
Hejzlar, P.2
Todreas, N.E.3
-
21
-
-
84865606079
-
Comparison of sodium and lead/lead-bismuth as a coolant and LMFR safety
-
Baltimore, MD, USA, April 2-6
-
Ninokata H., Sorokin A.P., and Kirillov P.L. Comparison of sodium and lead/lead-bismuth as a coolant and LMFR safety. Proc. of 8th Int. Conf. on Nuclear Engineering. Baltimore, MD, USA, April 2-6 (2000)
-
(2000)
Proc. of 8th Int. Conf. on Nuclear Engineering
-
-
Ninokata, H.1
Sorokin, A.P.2
Kirillov, P.L.3
-
24
-
-
49349109368
-
Risk-informed design changes in passive decay heat removal system
-
Patalano G., Apostolakis G.E., and Hejzlar P. Risk-informed design changes in passive decay heat removal system. Nucl. Technol. 163 (2008) 191-208
-
(2008)
Nucl. Technol.
, vol.163
, pp. 191-208
-
-
Patalano, G.1
Apostolakis, G.E.2
Hejzlar, P.3
-
25
-
-
70449666560
-
Roles and needs for simulation for the development of new reactors
-
Lawrence Livermore National Laboratory, December 14-15
-
Peterson P.F. Roles and needs for simulation for the development of new reactors. Presentation at Nuclear Fuel Cycle Workshop. Lawrence Livermore National Laboratory, December 14-15 (2005)
-
(2005)
Presentation at Nuclear Fuel Cycle Workshop
-
-
Peterson, P.F.1
-
26
-
-
70449629552
-
Liquid salt cooled flexible conversion ratio fast reactor
-
Petroski R., Hejzlar P., and Todreas N.E. Liquid salt cooled flexible conversion ratio fast reactor. Nucl. Eng. Des. 239 (2009) 2612-2625
-
(2009)
Nucl. Eng. Des.
, vol.239
, pp. 2612-2625
-
-
Petroski, R.1
Hejzlar, P.2
Todreas, N.E.3
-
27
-
-
2642537741
-
Reactor physics studies in support of GFR core design
-
New Orleans, LA, USA, November
-
Pope M.A., Driscoll M.J., and Hejzlar P. Reactor physics studies in support of GFR core design. Proc. of GLOBAL 2003. New Orleans, LA, USA, November (2003)
-
(2003)
Proc. of GLOBAL 2003
-
-
Pope, M.A.1
Driscoll, M.J.2
Hejzlar, P.3
-
28
-
-
70449660627
-
-
2-direct cycle GFR. MIT-ANP-TR-107, Center for Advanced Nuclear Energy Systems, Massachusetts Institute of Technology.
-
2-direct cycle GFR. MIT-ANP-TR-107, Center for Advanced Nuclear Energy Systems, Massachusetts Institute of Technology.
-
-
-
-
29
-
-
63349088762
-
Thermal hydraulic challenges of gas-cooled fast reactors with passive safety features
-
Pope M.A., Lee J.I., Hejzlar P., and Driscoll M.J. Thermal hydraulic challenges of gas-cooled fast reactors with passive safety features. Nucl. Eng. Des. 239 (2009) 840-854
-
(2009)
Nucl. Eng. Des.
, vol.239
, pp. 840-854
-
-
Pope, M.A.1
Lee, J.I.2
Hejzlar, P.3
Driscoll, M.J.4
-
30
-
-
4244018233
-
The rush to heavy liquid metal reactor coolants-gimmick or reasoned
-
Baltimore, USA, April
-
Spencer B.W. The rush to heavy liquid metal reactor coolants-gimmick or reasoned. Proc. 8th Int. Conf. on Nuclear Eng. Baltimore, USA, April (2000) 2-6
-
(2000)
Proc. 8th Int. Conf. on Nuclear Eng.
, pp. 2-6
-
-
Spencer, B.W.1
-
33
-
-
5644254761
-
Medium power lead alloy reactors-missions for this reactor technology
-
Todreas N.E., MacDonald P.E., Hejzlar P., Buongiorno J., and Loewen E.P. Medium power lead alloy reactors-missions for this reactor technology. Nucl. Technol. 147 September (2004) 305-320
-
(2004)
Nucl. Technol.
, vol.147
, Issue.September
, pp. 305-320
-
-
Todreas, N.E.1
MacDonald, P.E.2
Hejzlar, P.3
Buongiorno, J.4
Loewen, E.P.5
-
35
-
-
68649109516
-
Flexible conversion ratio fast reactor systems evaluations
-
Final Report, MIT-NFC-PR-101, Center for Advanced Nuclear Energy Systems, MIT, June
-
Todreas, N.E., Hejzlar, P., Shwageraus, E., Petroski, R., Nikiforova, A., Fong, C.J., Whitman, J., 2008. Flexible conversion ratio fast reactor systems evaluations. Final Report, MIT-NFC-PR-101, Center for Advanced Nuclear Energy Systems, MIT, June.
-
(2008)
-
-
Todreas, N.E.1
Hejzlar, P.2
Shwageraus, E.3
Petroski, R.4
Nikiforova, A.5
Fong, C.J.6
Whitman, J.7
-
36
-
-
70449670843
-
Flexible conversion ratio fast reactors: overview
-
Todreas N.E., Hejzlar P., Petroski R., Nikiforova A., Shwageraus E., Fong C.J., and Dricoll M.J. Flexible conversion ratio fast reactors: overview. Nucl. Eng. Des. 239 (2009) 2582-2595
-
(2009)
Nucl. Eng. Des.
, vol.239
, pp. 2582-2595
-
-
Todreas, N.E.1
Hejzlar, P.2
Petroski, R.3
Nikiforova, A.4
Shwageraus, E.5
Fong, C.J.6
Dricoll, M.J.7
-
37
-
-
0024132804
-
The integral fast reactor concept: physics of operation and safety
-
Wade D.C., and Chang Y.I. The integral fast reactor concept: physics of operation and safety. Nucl. Sci. Eng. 100 (1988) 507-524
-
(1988)
Nucl. Sci. Eng.
, vol.100
, pp. 507-524
-
-
Wade, D.C.1
Chang, Y.I.2
-
38
-
-
0002115141
-
The design rationale of the IFR
-
Wade D.C., and Hill R.N. The design rationale of the IFR. Prog. Nucl. Energy 31 January (1) (1997) 13-42
-
(1997)
Prog. Nucl. Energy
, vol.31
, Issue.January 1
, pp. 13-42
-
-
Wade, D.C.1
Hill, R.N.2
-
40
-
-
33845802503
-
-
March
-
Williams, D.F., Toth, L.M., Clarno, K.T., 2006. Assessment of candidate molten salt coolants for the advanced high-temperature reactor (AHTR). ORNL/TM-2006/12, March.
-
(2006)
Assessment of candidate molten salt coolants for the advanced high-temperature reactor (AHTR). ORNL/TM-2006/12
-
-
Williams, D.F.1
Toth, L.M.2
Clarno, K.T.3
|