-
1
-
-
84938665341
-
Swelling and inert gas diffusion in irradiated uranium
-
Geneva, Switzerland, 1-13 September
-
Barnes, R.S. (1958). Swelling and Inert Gas Diffusion in Irradiated Uranium. Proceedings of the 2nd United Nations International Conference on Peaceful Uses of Atomic Energy, Communique 5, No. 500, Geneva, Switzerland, 1-13 September.
-
(1958)
Proceedings of the 2nd United Nations International Conference on Peaceful Uses of Atomic Energy, Communique 5, No. 500
-
-
Barnes, R.S.1
-
2
-
-
0011808243
-
A theory of swelling and gas release for reactor materials
-
Barnes, R.S. (1964). A Theory of Swelling and Gas Release for Reactor Materials. Journal of Nuclear Materials 11, 135.
-
(1964)
Journal of Nuclear Materials
, vol.11
, pp. 135
-
-
Barnes, R.S.1
-
3
-
-
0043258377
-
Run-Beyond-Cladding Breach (RBCB) test results for the Integral Fast Reactor (IFR) metallic fuels program
-
Snowbird, Utah, 12-16 August
-
Batté, G. and G.L. Hofman (1990). Run-Beyond-Cladding Breach (RBCB) Test Results for the Integral Fast Reactor (IFR) Metallic Fuels Program. International Fast Reactor Safety Meeting IV, p.207, Snowbird, Utah, 12-16 August.
-
(1990)
International Fast Reactor Safety Meeting IV
, pp. 207
-
-
Batté, G.1
Hofman, G.L.2
-
4
-
-
0041755326
-
Integral fast reactor metallic fuel program in pile measurement of the thermal conductivity of irradiated metallic fuel
-
Bauer, T.H. and J.W. Holland (1992). Integral Fast Reactor Metallic Fuel Program in Pile Measurement of the Thermal Conductivity of Irradiated Metallic Fuel. Transactions of the American Nuclear Society 65, 278.
-
(1992)
Transactions of the American Nuclear Society
, vol.65
, pp. 278
-
-
Bauer, T.H.1
Holland, J.W.2
-
5
-
-
0025600670
-
Behavior of modern metallic fuel in TREAT transient power tests
-
Bauer, T.H., A.E.,Wright, W.R. Robinson, J.W. Holland and E.A. Rhodes (1990). Behavior of Modern Metallic Fuel in TREAT Transient Power Tests. Nuclear Technology 92, 325.
-
(1990)
Nuclear Technology
, vol.92
, pp. 325
-
-
Bauer, T.H.1
Wright, A.E.2
Robinson, W.R.3
Holland, J.W.4
Rhodes, E.A.5
-
6
-
-
0029322783
-
In-pile measurement of the thermal conductivity of irradiated metallic fuel
-
Bauer, T.H. and J.W. Holland (1995). In-Pile Measurement of the Thermal Conductivity of Irradiated Metallic Fuel. Nuclear Technology 110, 407.
-
(1995)
Nuclear Technology
, vol.110
, pp. 407
-
-
Bauer, T.H.1
Holland, J.W.2
-
8
-
-
0042757222
-
Fission gas release and thermal conductivity measurements on U-5 Wt % Fs irradiated in CP-5
-
Beck, W.N. and R.J. Fousek (1969). Fission Gas Release and Thermal Conductivity Measurements on U-5 Wt % Fs Irradiated in CP-5. Transactions of the American Nuclear Society 12, 78.
-
(1969)
Transactions of the American Nuclear Society
, vol.12
, pp. 78
-
-
Beck, W.N.1
Fousek, R.J.2
-
10
-
-
0040718785
-
In-core measurements of uranium - 5 wt.% fissium alloy thermal conductivity
-
Betten, P.R. (1985). In-Core Measurements of Uranium - 5 wt.% Fissium Alloy Thermal Conductivity. Transactions of the American Nuclear Society 50, 239.
-
(1985)
Transactions of the American Nuclear Society
, vol.50
, pp. 239
-
-
Betten, P.R.1
-
11
-
-
0042757223
-
Achieving high burn-up in fast reactors
-
Blake, L.R. (1961). Achieving High Burn-up in Fast Reactors. Reactor Science and Technology 14, 31.
-
(1961)
Reactor Science and Technology
, vol.14
, pp. 31
-
-
Blake, L.R.1
-
12
-
-
0039533396
-
Thermomigration and electromigration in zirconium
-
Campbell, D.R. and H.B Huntington (1969). Thermomigration and Electromigration in Zirconium. Physical Review 179, 601.
-
(1969)
Physical Review
, vol.179
, pp. 601
-
-
Campbell, D.R.1
Huntington, H.B.2
-
13
-
-
0024755944
-
The integral fast reactor
-
Chang, Y.I. (1989). The Integral Fast Reactor. Nuclear Technology 88, 129.
-
(1989)
Nuclear Technology
, vol.88
, pp. 129
-
-
Chang, Y.I.1
-
14
-
-
0042757216
-
-
American Institute of Metallurgical Engineering, Chicago, Illinois
-
Claudson, T.T., G.T. Geering, J.W. Goffard and J.E. Minor (1959). Operational Performance of Bonded and Unbonded Uranium Fuel Rods, Nuclear Metallurgy, American Institute of Metallurgical Engineering, Chicago, Illinois.
-
(1959)
Operational Performance of Bonded and Unbonded Uranium Fuel Rods, Nuclear Metallurgy
-
-
Claudson, T.T.1
Geering, G.T.2
Goffard, J.W.3
Minor, J.E.4
-
17
-
-
0019923316
-
Fast-neutron hodoscope at treat: Methods for quantitative determination of fuel dispersal
-
DeVolpi, A., C.L. Fink, G.E. Marsh, E.A Rhodes, and G.S. Stanford (1982). Fast-Neutron Hodoscope at TREAT: Methods for Quantitative Determination of Fuel Dispersal, Nuclear Technology 56, 141.
-
(1982)
Nuclear Technology
, vol.56
, pp. 141
-
-
DeVolpi, A.1
Fink, C.L.2
Marsh, G.E.3
Rhodes, E.A.4
Stanford, G.S.5
-
19
-
-
0042757211
-
Research on the fabrication, properties, and irradiation behavior of plutonium fuels for the U.K. reactor programme
-
Richland, Washington, 13-14 September
-
Frost, B.R.T., P.G. Mardon and L.E. Russell (1962). Research on the Fabrication, Properties, and Irradiation Behavior of Plutonium Fuels for the U.K. Reactor Programme. Proceedings of the American Nuclear Society Meeting on Plutonium as a Power Reactor Fuel, p.4.1, Richland, Washington, 13-14 September.
-
(1962)
Proceedings of the American Nuclear Society Meeting on Plutonium As a Power Reactor Fuel
, pp. 41
-
-
Frost, B.R.T.1
Mardon, P.G.2
Russell, L.E.3
-
20
-
-
0041755318
-
The effects of neutron irradiation on λ-uranium and some fissile alloys of cubic crystal structure
-
Greenwood, G.W. (1962). The Effects of Neutron Irradiation on λ-Uranium and Some Fissile Alloys of Cubic Crystal Structure. Journal of Nuclear Materials 6-1, 26.
-
(1962)
Journal of Nuclear Materials
, vol.6
, Issue.1
, pp. 26
-
-
Greenwood, G.W.1
-
22
-
-
0018943825
-
Irradiation behavior of experimental mark-II EBR-II driver fuel
-
Hofman, G.L. (1980). Irradiation Behavior of Experimental Mark-II EBR-II Driver Fuel. Nuclear Technology 47, 7.
-
(1980)
Nuclear Technology
, vol.47
, pp. 7
-
-
Hofman, G.L.1
-
23
-
-
0042757209
-
Chemical interaction of metallic fuel with austenitic and ferritic stainless steel cladding
-
Tucson, Arizona, 7 September
-
Hofman, G.L., A.C. Hins, D.L. Porter, L. Leibowitz and E.L. Wood (1986). Chemical Interaction of Metallic Fuel with Austenitic and Ferritic Stainless Steel Cladding. Proceedings of the International Conference on Reliable Fuels for Liquid Metal Reactors, p. 12, Tucson, Arizona, 7 September.
-
(1986)
Proceedings of the International Conference on Reliable Fuels for Liquid Metal Reactors
, pp. 12
-
-
Hofman, G.L.1
Hins, A.C.2
Porter, D.L.3
Leibowitz, L.4
Wood, E.L.5
-
24
-
-
51649147203
-
Swelling behavior of U-Pu-Zr fuel
-
Hofman, G.L., Pahl, R.G., Lahm, C.E. and Porter, D.L. (1990). Swelling Behavior of U-Pu-Zr Fuel. Metallurgical Transactions A. 21A, 517.
-
(1990)
Metallurgical Transactions A
, vol.21 A
, pp. 517
-
-
Hofman, G.L.1
Pahl, R.G.2
Lahm, C.E.3
Porter, D.L.4
-
27
-
-
0025387148
-
Development of the SESAMI metallic fuel performance code
-
Kobayashi, T., M. Kinoshita and S. Hattori (1990). Development of the SESAMI Metallic Fuel Performance Code. Nuclear Technology 89, 183.
-
(1990)
Nuclear Technology
, vol.89
, pp. 183
-
-
Kobayashi, T.1
Kinoshita, M.2
Hattori, S.3
-
28
-
-
0042255986
-
Fission gas induced swelling in uranium at high temperatures and pressures
-
Kulcinski, G.L., R.D. Leggett, C.R. Hann and B. Mastel (1969). Fission Gas Induced Swelling in Uranium at High Temperatures and Pressures. Journal of Nuclear Materials 30, 3.
-
(1969)
Journal of Nuclear Materials
, vol.30
, pp. 3
-
-
Kulcinski, G.L.1
Leggett, R.D.2
Hann, C.R.3
Mastel, B.4
-
29
-
-
0042256007
-
EBR-II test programs
-
Snowbird, Utah, 12-16 August
-
Lambert, J.D.B., W.K. Lehto, J.I. Sackett, D.J. Hill, H.P. Planchon and R.W. Lindsay (1990). EBR-II Test Programs. International Fast Reactor Safety Meeting III, p. 181, Snowbird, Utah, 12-16 August.
-
(1990)
International Fast Reactor Safety Meeting III
, pp. 181
-
-
Lambert, J.D.B.1
Lehto, W.K.2
Sackett, J.I.3
Hill, D.J.4
Planchon, H.P.5
Lindsay, R.W.6
-
31
-
-
0042757181
-
Basic swelling studies, radiation effects
-
Asheville, North Carolina, September
-
Leggett, R.D., T.K., Bierlein and B. Mastel (1967). Basic Swelling Studies, Radiation Effects. American Institute of Metallurgical Engineering Symposium, p.303, Asheville, North Carolina, September.
-
(1967)
American Institute of Metallurgical Engineering Symposium
, pp. 303
-
-
Leggett, R.D.1
Bierlein, T.K.2
Mastel, B.3
-
32
-
-
0042757175
-
Etude du gonflenent d'alliages d'uranium sous irradiation
-
Lehmann, J.P. Paoli, N. Azam (1968). Etude du Gonflenent d'Alliages d'Uranium Sous Irradiation. Journal of Nuclear Materials 27, 285.
-
(1968)
Journal of Nuclear Materials
, vol.27
, pp. 285
-
-
Lehmann1
Paoli, J.P.2
Azam, N.3
-
33
-
-
0042757180
-
The study of irradiation damage in uranium by electron microscopy
-
Paper No. 7, London, England
-
Makin, M.J., W.H. Chatwin, J.H. Evans, B. Hudson and E.D. Hyam (1962). The Study of Irradiation Damage in Uranium by Electron Microscopy. Institute of Metallurgy Symposium on Uranium and Graphite, Paper No. 7, London, England.
-
(1962)
Institute of Metallurgy Symposium on Uranium and Graphite
-
-
Makin, M.J.1
Chatwin, W.H.2
Evans, J.H.3
Hudson, B.4
Hyam, E.D.5
-
34
-
-
0041755291
-
Thermal migration of hydrogen in zirconium-uranium-hydrogen alloys
-
Merten, U., J.C. Bokros, D.B. Couggisberg and A.P. Hatcher (1963). Thermal Migration of Hydrogen in Zirconium-Uranium-Hydrogen Alloys. Journal of Nuclear Materials 10-3, 201.
-
(1963)
Journal of Nuclear Materials
, vol.10
, Issue.3
, pp. 201
-
-
Merten, U.1
Bokros, J.C.2
Couggisberg, D.B.3
Hatcher, A.P.4
-
36
-
-
1642383872
-
-
Argonne National Laboratory Report ANL-7602
-
Murphy, W.F., W.M. Beck, S.L. Brown, B.T. Kopowski and L.A. Neimark (1969). Post Irradiation Examination of U-Pu-Zr Fuel Elements Irradiated in EBR-II to 4.5 at % Burnup, Argonne National Laboratory Report ANL-7602.
-
(1969)
Post Irradiation Examination of U-Pu-Zr Fuel Elements Irradiated in EBR-II to 4.5 at % Burnup
-
-
Murphy, W.F.1
Beck, W.M.2
Brown, S.L.3
Kopowski, B.T.4
Neimark, L.A.5
-
38
-
-
0014891968
-
The uranium-plutonium-zirconium ternary alloy system
-
American Institute of Metallurgical Engineering
-
O'Boyle D.R. and A.E. Dwight (1970). The Uranium-Plutonium-Zirconium Ternary Alloy System. Plutonium 1970 and Other Actinides Nuclear Metallurgy, 17, American Institute of Metallurgical Engineering.
-
(1970)
Plutonium 1970 and Other Actinides Nuclear Metallurgy
, vol.17
-
-
O'Boyle, D.R.1
Dwight, A.E.2
-
39
-
-
0025459120
-
Experimental studies of U-Pu-Zr fast reactor fuel pins in EBR-II
-
Pahl, R.G., D.L. Porter, C.E. Lahm and Hofman, G.L. (1990a). Experimental Studies of U-Pu-Zr Fast Reactor Fuel Pins in EBR-II. Metallurgical Transactions A. 21A, 1863.
-
(1990)
Metallurgical Transactions A
, vol.21 A
, pp. 1863
-
-
Pahl, R.G.1
Porter, D.L.2
Lahm, C.E.3
Hofman, G.L.4
-
40
-
-
0006407569
-
Steady-state irradiation testing of U-Pu-Zr fuel to >18 at% burnup
-
Snowbird, Utah, 12-16 August
-
Pahl, R.G., R.S. Wisner, M.C. Billone and G.L. Hofman (1990b). Steady-State Irradiation Testing of U-Pu-Zr Fuel to >18 at% Burnup. Proceedings of the International Conference Fast Reactor Safety IV, 129, Snowbird, Utah, 12-16 August.
-
(1990)
Proceedings of the International Conference Fast Reactor Safety IV
, pp. 129
-
-
Pahl, R.G.1
Wisner, R.S.2
Billone, M.C.3
Hofman, G.L.4
-
41
-
-
0025459086
-
Fuel constituent redistribution during the early stages of U-Pu-Zr irradiation
-
Porter, D.L., C.E. Lahm and R.G. Pahl (1990). Fuel Constituent Redistribution During the Early Stages of U-Pu-Zr Irradiation. Metallurgical Transactions A, 21A, 1871.
-
(1990)
Metallurgical Transactions A
, vol.21 A
, pp. 1871
-
-
Porter, D.L.1
Lahm, C.E.2
Pahl, R.G.3
-
42
-
-
0041755290
-
Swelling in alpha uranium due to irradiation
-
University of Chicago Press, Chap. XXXI
-
Pugh, S.F. (1961). Swelling in Alpha Uranium Due to Irradiation. The Metal Plutonium, University of Chicago Press, Chap. XXXI.
-
(1961)
The Metal Plutonium
-
-
Pugh, S.F.1
-
43
-
-
0026851577
-
Fuel motion in over-power tests of metallic integral fast reactor fuel
-
Rhodes, E.A., T.H. Bauer, G.S. Stanford, J.P. Regis and C.E. Dickerman (1992). Fuel Motion in Over-Power Tests of Metallic Integral Fast Reactor Fuel. Nuclear Technology 98, 91.
-
(1992)
Nuclear Technology
, vol.98
, pp. 91
-
-
Rhodes, E.A.1
Bauer, T.H.2
Stanford, G.S.3
Regis, J.P.4
Dickerman, C.E.5
-
44
-
-
0043258337
-
The role of EBR-II and treat in establishing liquid metal reactor safety
-
Washington, DC, 11-15 November
-
Sackett, J.I., W.K. Lehto and C.W. Solbrig (1990). The Role of EBR-II and Treat in Establishing Liquid Metal Reactor Safety. Proceedings, LMR: A Decade of LMR Progress and Promise, p.61, Washington, DC, 11-15 November.
-
(1990)
Proceedings, LMR: A Decade of LMR Progress and Promise
, pp. 61
-
-
Sackett, J.I.1
Lehto, W.K.2
Solbrig, C.W.3
-
45
-
-
0043258338
-
-
Radiation Effects in Breeder Reactor Structural Materials, American Institute of Metallurgical Engineering, Chicago, Illinois
-
Seidel, B.R. and R.E. Einziger (1977). In-Reactor Cladding Breach of EBR-II Driver Fuel Elements, Radiation Effects in Breeder Reactor Structural Materials, American Institute of Metallurgical Engineering, Chicago, Illinois.
-
(1977)
In-reactor Cladding Breach of EBR-II Driver Fuel Elements
-
-
Seidel, B.R.1
Einziger, R.E.2
-
46
-
-
0042255985
-
Experience with EBR-II driver fuel
-
Tucson, Arizona, 7-11 September
-
Seidel, B.R., D.L. Porter, L.C. Walters and G.L. Hofman (1986a). Experience with EBR-II Driver Fuel. Proceedings of the International Conference Reliable Fuels for Liquid Metal Reactors, p.2-106, Tucson, Arizona, 7-11 September.
-
(1986)
Proceedings of the International Conference Reliable Fuels for Liquid Metal Reactors
, pp. 2-106
-
-
Seidel, B.R.1
Porter, D.L.2
Walters, L.C.3
Hofman, G.L.4
-
47
-
-
0042757174
-
Off-normal performance of EBR-II driver fuel
-
Tucson, Arizona, 7-11 September
-
Seidel, B.R., G.L. Barté, C.E. Lahm, R.M. Fryer, J.F. Koenig and G.L. Hofman (1986b). Off-Normal Performance of EBR-II Driver Fuel. Proceedings International Conf. Reliable Fuels for Liquid Metal Reactors, p.6-48, Tucson, Arizona, 7-11 September.
-
(1986)
Proceedings International Conf. Reliable Fuels for Liquid Metal Reactors
, pp. 6-48
-
-
Seidel, B.R.1
Barté, G.L.2
Lahm, C.E.3
Fryer, R.M.4
Koenig, J.F.5
Hofman, G.L.6
-
50
-
-
0042757169
-
Improvements in the fabrication of metallic fuels
-
Tracy, D.B., S.P. Henslee, N.E. Dodds and K.J. Longua (1989). Improvements in the Fabrication of Metallic Fuels. Transactions of the American Nuclear Society 60, 314.
-
(1989)
Transactions of the American Nuclear Society
, vol.60
, pp. 314
-
-
Tracy, D.B.1
Henslee, S.P.2
Dodds, N.E.3
Longua, K.J.4
-
51
-
-
30844433420
-
Fuel/cladding compatibility in irradiated metallic fuel pins at elevated temperatures
-
Snowbird, Utah, 12-16 August
-
Tsai, H. (1990). Fuel/Cladding Compatibility in Irradiated Metallic Fuel Pins at Elevated Temperatures. International Fast Reactor Safety Meeting II, p.257, Snowbird, Utah, 12-16 August.
-
(1990)
International Fast Reactor Safety Meeting II
, pp. 257
-
-
Tsai, H.1
-
52
-
-
84874413249
-
Behavior of low-burnup metallic fuels for the integral fast reactor at elevated temperatures in ex-reactor tests
-
Kyoto, Japan, 13 October
-
Tsai, H. (1991). Behavior of Low-Burnup Metallic Fuels for the Integral Fast Reactor at Elevated Temperatures in Ex-Reactor Tests. Conference on Fast Reactors and Related Fuel Cycles III, 1.18-1, Kyoto, Japan, 13 October.
-
(1991)
Conference on Fast Reactors and Related Fuel Cycles III
, vol.1
, pp. 18-21
-
-
Tsai, H.1
-
53
-
-
0042255982
-
-
Institute fur Metallphysik, Universitat Gottingen, Germany American Institute of Metallurgical Engineering, Detroit, Michigan
-
Van Loo, F.J.J., J.A. Van Beak, C.F. Bastin and R. Metselaar (1984). The Role of Thermodynamics and Kinetics in Multiphase Ternary Diffusion, Institute fur Metallphysik, Universitat Gottingen, Germany American Institute of Metallurgical Engineering, Detroit, Michigan.
-
(1984)
The Role of Thermodynamics and Kinetics in Multiphase Ternary Diffusion
-
-
Van Loo, F.J.J.1
Van Beak, J.A.2
Bastin, C.F.3
Metselaar, R.4
-
56
-
-
0021425275
-
Performance of metallic fuels and blankets in liquid-metal fast breeder reactors
-
Walters, L.C., B.R. Seidel and J.H. Kittel (1984). Performance of Metallic Fuels and Blankets in Liquid-Metal Fast Breeder Reactors. Nuclear Technology 65, 179.
-
(1984)
Nuclear Technology
, vol.65
, pp. 179
-
-
Walters, L.C.1
Seidel, B.R.2
Kittel, J.H.3
-
57
-
-
84884796915
-
Compatibility between metallic U-Pu-Base fuels and potential cladding materials
-
Scottsdale, Arizona, October
-
Zegler, S.T. and C.M. Walter (1967). Compatibility Between Metallic U-Pu-Base Fuels and Potential Cladding Materials. American Institute of Metallurgical Engineering Symposium on Plutonium Fuels Technology 13, 335, Scottsdale, Arizona, October.
-
(1967)
American Institute of Metallurgical Engineering Symposium on Plutonium Fuels Technology
, vol.13
, pp. 335
-
-
Zegler, S.T.1
Walter, C.M.2
|