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1
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2342645783
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The gas turbine-modular helium reactor: A promising option for near term deployment
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Embedded Topical American Nuclear Society 2002 Annual Meeting, Hollywood, Florida, USA, June 9-13
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M. P., LABAR, "The Gas Turbine-Modular Helium Reactor: A Promising Option for Near Term Deployment," Proc., 2002 International Congress on Advanced Nuclear Power Plants (ICAPP'02), Embedded Topical American Nuclear Society 2002 Annual Meeting, Hollywood, Florida, USA, June 9-13, (2002).
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(2002)
Proc., 2002 International Congress on Advanced Nuclear Power Plants (ICAPP'02)
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Labar, M.P.1
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2
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33745438508
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Pebble Bed Modular Reactor (PBMR) project update
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Embedded International Topical Meeting 2004 American Nuclear Society Annual Meeting, Pittsburg, Pennsylvania, USA, June 13-17
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R.A., MATZIE, "Pebble Bed Modular Reactor (PBMR) Project Update," Proc., 2004 International Congress on Advances in Nuclear Power Plants (ICAPP '04), Embedded International Topical Meeting 2004 American Nuclear Society Annual Meeting, Pittsburg, Pennsylvania, USA, June 13-17, (2004).
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(2004)
Proc., 2004 International Congress on Advances in Nuclear Power Plants (ICAPP '04)
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Matzie, R.A.1
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3
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0345604446
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Multiple-reheat brayton cycles for nuclear power conversion with molten coolants
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P. F., PETERSON, "Multiple-Reheat Brayton Cycles for Nuclear Power Conversion with Molten Coolants," Nucl. Technol., 144, 279-288 (2003).
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(2003)
Nucl. Technol.
, vol.144
, pp. 279-288
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Peterson, P.F.1
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4
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17444415038
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Optimized helium-brayton power conversion for fusion energy systems
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April
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H., ZHAO, G., Fukuda, R., Abbott and, P.F., Peterson, "Optimized Helium-Brayton Power Conversion for Fusion Energy Systems," Fusion Science and Technology, Vol. 47, April, (2005).
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(2005)
Fusion Science and Technology
, vol.47
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Zhao, H.1
Fukuda, G.2
Abbott, R.3
Peterson, P.F.4
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5
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33845799629
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Optimization of advanced high-temperature brayton cycles with multiple reheat stages
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Popes' Palace Conference Center, Avignon, France, October 2-6
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H. ZHAO and P.F. Peterson, "Optimization Of Advanced High-Temperature Brayton Cycles With Multiple Reheat Stages," The 11th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics (NURETH-11), Popes' Palace Conference Center, Avignon, France, October 2-6, (2005).
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(2005)
The 11th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics (NURETH-11)
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Zhao, H.1
Peterson, P.F.2
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6
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0345172386
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Molten-salt-cooled advanced high-temperature reactor for production of hydrogen and electricity
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C. W., FORS BERG, P. S., Pickard, and P. F., Peterson, "Molten-salt-cooled advanced high-temperature reactor for production of hydrogen and electricity," Nucl. Technol., 144, 289-302 (2003).
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(2003)
Nucl. Technol.
, vol.144
, pp. 289-302
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Fors Berg, C.W.1
Pickard, P.S.2
Peterson, P.F.3
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7
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33845731346
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A flexible base-line design for the Advanced High-Temperature Reactor utilizing Metallic reactor Internals (AHTR-MI)
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Embedded International Topical Meeting 2006 American Nuclear Society Annual Meeting, Reno, NV, USA, June 4-6
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P.F. PETERSON and H. Zhao, "A Flexible Base-Line Design for the Advanced High-Temperature Reactor Utilizing Metallic Reactor Internals (AHTR-MI)," Proc., 2006 International Congress on Advances in Nuclear Power Plants (ICAPP '06), Embedded International Topical Meeting 2006 American Nuclear Society Annual Meeting, Reno, NV, USA, June 4-6, (2006).
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(2006)
Proc., 2006 International Congress on Advances in Nuclear Power Plants (ICAPP '06)
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Peterson, P.F.1
Zhao, H.2
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