-
1
-
-
33845802503
-
-
Oak Ridge National Laboratory, ORNL/TM-2006/12, March
-
D. F. WILLIAMS, L. M. TOTH, K. T. CLARNO, "Assessment of Candidate Molten Salt Coolants for the Advanced High-Temperature Reactor (AHTR), " Oak Ridge National Laboratory, ORNL/TM-2006/12, March 2006.
-
(2006)
Assessment of Candidate Molten Salt Coolants for The Advanced High-Temperature Reactor (AHTR)
-
-
Williams, D.F.1
Toth, L.M.2
Clarno, K.T.3
-
3
-
-
0345172386
-
Molten-salt-cooled advanced high-temperature reactor for production of hydrogen and electricity
-
C.W. FORSBERG, P. PICKARD, and P.F. PETERSON, "Molten-Salt-Cooled Advanced High-Temperature Reactor for Production of Hydrogen and Electricity, " Nuclear Technology Vol. 144, pp. 289-302 (2003).
-
(2003)
Nuclear Technology
, vol.144
, pp. 289-302
-
-
Forsberg, C.W.1
Pickard, P.2
Peterson, P.F.3
-
4
-
-
33845731346
-
A flexible baseline design for the advanced high temperature reactor utilizing metallic reactor internals (AHTR-MI)
-
P.F. PETERSON and H. ZHAO, "A Flexible Baseline Design For the Advanced High Temperature Reactor Utilizing Metallic Reactor Internals (AHTR-MI), " Proceedings of the 2006 International Congress on Advances in Nuclear Power Plants, 1CAPP'06, 2006, p 650-661.
-
Proceedings of The 2006 International Congress on Advances in Nuclear Power Plants, 1CAPP'06, 2006, P 650-661.
-
-
Peterson, P.F.1
Zhao, H.2
-
7
-
-
0141673784
-
-
U.S. DOE NUCLEAR ENERGY RESEARCH ADVISORY COMMITTEE AND THE GENERATION IV INTERNATIONAL FORUM, Report No. GIF002-00, December 1
-
U.S. DOE NUCLEAR ENERGY RESEARCH ADVISORY COMMITTEE AND THE GENERATION IV INTERNATIONAL FORUM, "A Technology Roadmap for Generation IV Nuclear Energy Systems, " Report No. GIF002-00, December 1, 2002.
-
(2002)
A Technology Roadmap for Generation IV Nuclear Energy Systems
-
-
-
8
-
-
45149110548
-
-
Global 2007, Boise, Idaho, September 9-13
-
P. BARDET, et al. "The Pebble Recirculation Experiment (PREX) for the AHTR, " Global 2007, Boise, Idaho, September 9-13, 2007.
-
(2007)
The Pebble Recirculation Experiment (PREX) for the AHTR
-
-
Bardet, P.1
-
9
-
-
45149121746
-
-
Global 2007, Boise, Idaho, September 9-13
-
A. GRIVEAU, F. FARDIN, H. ZHAO, AND P.F. PETERSON "Transient Thermal Response of the PB-AHTR to Loss of Forced Cooling, " Global 2007, Boise, Idaho, September 9-13, 2007.
-
(2007)
Transient Thermal Response of the PB-AHTR to Loss of Forced Cooling
-
-
Griveau, A.1
Fardin, F.2
Zhao, H.3
Peterson, P.F.4
-
11
-
-
70349974523
-
-
Global 2007, Boise, Idaho, September 9-13
-
M. FRATONI, F. KOENIG, E. GREENSPAN, AND P.F. PETERSON "Neutronic and Depletion Analysis of the PB-AHTR, " Global 2007, Boise, Idaho, September 9-13, 2007.
-
(2007)
Neutronic and Depletion Analysis of the PB-AHTR
-
-
Fraton I, M.1
Koenig, F.2
Greenspan, E.3
Peterson, P.F.4
-
12
-
-
10644258084
-
R&D on core seismic design
-
T. Iyoku, J. Smita, M. lshihara, and S. Ueta "R&D on Core Seismic Design" Nuclear Engineering and Design, Vol. 233, pp. 225-234, 2004.
-
(2004)
Nuclear Engineering and Design
, vol.233
, pp. 225-234
-
-
Iyoku, T.1
Smita, J.2
Lshihara, M.3
Ueta, S.4
-
13
-
-
33745186128
-
-
January, Mineral Commodity Summaries
-
U.S. GEOLOGICAL SURVEY, Mineral Commodity Summaries, pg. 32, January 2005.
-
(2005)
U.S. Geological Survey
, pp. 32
-
-
-
15
-
-
0029178244
-
Tribology at high temperatures
-
A. P. SEMENOV, "Tribology at high temperatures, " Tribology International, Vol. 28, No. 1, pp. 45-50, 1995.
-
(1995)
Tribology International
, vol.28
, Issue.1
, pp. 45-50
-
-
Semenov, A.P.1
-
16
-
-
0025434624
-
The influence of the environment on the friction and wear of graphitic carbons
-
H. ZAJDI, D. PAULMIER AND J. LEPAGE, The influence of the Environment on the Friction and Wear of Graphitic Carbons, Applied Surface Science Vol. 44 pp. 221-233, 1990.
-
(1990)
Applied Surface Science
, vol.44
, pp. 221-233
-
-
Zajd I, H.1
Paulmier, D.2
Lepage, J.3
-
17
-
-
32544440151
-
The influence of roughness on tribological properties of nuclear grade graphite
-
L. XIAOWEI, Y. SUYUAN, S. XUANYU, H. SHUYAN, The influence of roughness on tribological properties of nuclear grade graphite, Journal of Nuclear Materials, Vol. 350, pp. 74-82 (2006).
-
(2006)
Journal of Nuclear Materials
, vol.350
, pp. 74-82
-
-
Xiaowei, L.1
Suyuan, Y.2
Xuanyu, S.3
Shuyan, H.4
-
21
-
-
0345604446
-
Multiple-reheat brayton cycles for nuclear power conversion with molten coolants
-
P. F. PETERSON, "Multiple-Reheat Brayton Cycles for Nuclear Power Conversion with Molten Coolants, " Nucl. Technol., 144, 279-288 (2003).
-
(2003)
Nucl. Technol.
, vol.144
, pp. 279-288
-
-
Peterson, P.F.1
-
22
-
-
33845749206
-
Low-temperature multiple-reheat closed gas power cycles for the AHTR and LSFR
-
Embedded International Topical Meeting 2006 American Nuclear Society Annual Meeting, Reno, NV, USA, June 4-6
-
H. ZHAO AND P.F. PETERSON "Low-temperature multiple-reheat closed gas power cycles for the AHTR and LSFR, " 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).
-
(2006)
Proc, 2006 International Congress on Advances in Nuclear Power Plants (ICAPP '06)
-
-
Zhao, H.1
Peterson, P.F.2
-
23
-
-
33745823581
-
-
DOEHTGR-86-024, Amendment 13, Chapter 3, August
-
U.S. DOE, "Preliminary Safety Information Document for the Standard Modular High Temperature Gas-Cooled Reactor, " DOEHTGR-86-024, Amendment 13, Chapter 3, August, 1992.
-
(1992)
Preliminary Safety Information Document for the Standard Modular High Temperature Gas-Cooled Reactor
-
-
Doe, U.S.1
-
30
-
-
70349950219
-
-
PhD Dissertation, University of California, Berkeley
-
R.E. GAMBLE, "Decoupling, Complexity and Importance in the Design and Analysis of Complex Transport Systems, " PhD Dissertation, University of California, Berkeley, 2002.
-
(2002)
Decoupling, Complexity and Importance in the Design and Analysis of Complex Transport Systems
-
-
Gamble, R.E.1
-
31
-
-
4544297428
-
On the role of defense in depth in risk-informed regulation
-
Washington, DC, August 22-26, 408-413, American Nuclear Society, La Grange Park, Illinois
-
SORENSEN, J.N., APOSTOLAKIS, G.E., KRESS, T.S., POWERS, D.A., "On the Role of Defense in Depth in Risk-Informed Regulation. In: Proceedings of PSA '99, International Topical Meeting on Probabilistic Safety Assessment, Washington, DC, August 22-26, pp. 408-413, American Nuclear Society, La Grange Park, Illinois (1999).
-
(1999)
Proceedings of PSA '99, International Topical Meeting on Probabilistic Safety Assessment
-
-
Sorensen, J.N.1
Apostolakis, G.E.2
Kress, T.S.3
Powers, D.A.4
-
36
-
-
34047103818
-
Three-dimensional imaging and precision metrology for liquid-salt-cooled reactors
-
Albuquerque, New Mexico, November 12-16
-
C.W. FORSBERG, V.K. VARMA, T.W. BURGESS, "Three-Dimensional Imaging and Precision Metrology for Liquid-Salt-Cooled Reactors, " 5th International Topical Meeting on Nuclear Plant Instrumentation, Controls, and Human Machine Interface Technology, Albuquerque, New Mexico, November 12-16, 2006.
-
(2006)
5th International Topical Meeting on Nuclear Plant Instrumentation, Controls, and Human Machine Interface Technology
-
-
Forsberg, C.W.1
Varma, V.K.2
Burgess, T.W.3
-
37
-
-
0028538718
-
Scale modeling of oscillating sheet jets for the HYLIFE-II inertial confinement fusion reactor
-
C.J. CAVANAUGH and P.F. PETERSON, "Scale Modeling of Oscillating Sheet Jets for the HYLIFE-II Inertial Confinement Fusion Reactor, " Fusion Technology, Vol. 26, pp. 917-921, 1994.
-
(1994)
Fusion Technology
, vol.26
, pp. 917-921
-
-
Cavanaugh, C.J.1
Peterson, P.F.2
-
38
-
-
45149095361
-
Design of scaled integral experiments for high temperature liquid salt and helium fluid mechanics and heat transfer
-
Avignon, France, October 2-6
-
P. BARDET and P.F. PETERSON, "Design of Scaled Integral Experiments for High Temperature Liquid Salt and Helium Fluid Mechanics and Heat Transfer", Eleventh International Topical Meeting on Nuclear Reactor Thermal Hydraulics, Avignon, France, October 2-6 2005.
-
(2005)
Eleventh International Topical Meeting on Nuclear Reactor Thermal Hydraulics
-
-
Bardet, P.1
Peterson, P.F.2
-
39
-
-
70349961177
-
Investigation of criticality parameters of high temperature reactors at kurchtov institute's astra critical facility
-
Petten, NL, Apr. 22-24
-
N.E. KUKHARKTN, E.S. GLUSHKOV, G.V. KOMPANIETS, V.A. LOBYNTSEV, D.N. POLYAKOV, O.N. SMIRNOV Investigation of Criticality Parameters of High Temperature Reactors at Kurchtov Institute's ASTRA Critical Facility, " HTR-2002 Conference on High-Temperature Reactors, Petten, NL, Apr. 22-24 (2002).
-
(2002)
HTR-2002 Conference on High-Temperature Reactors
-
-
Kukharktn, N.E.1
Glushkov, E.S.2
Kompaniets, G.V.3
Lobyntsev, V.A.4
Polyakov, D.N.5
Smirnov, O.N.6
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