-
4
-
-
0020143541
-
-
Turnbull J.A., Friskney C.A., Findlay J.R., Johnson F.A., Walter A.J. J. Nucl. Mater. 107:1982;168.
-
(1982)
J. Nucl. Mater.
, vol.107
, pp. 168
-
-
Turnbull, J.A.1
Friskney, C.A.2
Findlay, J.R.3
Johnson, F.A.4
Walter, A.J.5
-
5
-
-
0004771818
-
The diffusion coefficient for fission gas atoms in uranium dioxide
-
Transient and Accident Conditions, Preston, England, 18-22 September
-
J.A. Turnbull, R.J. White, C. Wise, The diffusion coefficient for fission gas atoms in uranium dioxide, in: Proceedings of the International Atomic Energy Agency Technical Committee Meeting on Water Reactor Fuel Element Computer Modelling in Steady State, Transient and Accident Conditions, Preston, England, 18-22 September 1988.
-
(1988)
In: Proceedings of the International Atomic Energy Agency Technical Committee Meeting on Water Reactor Fuel Element Computer Modelling in Steady State
-
-
Turnbull, J.A.1
White, R.J.2
Wise, C.3
-
8
-
-
84915894839
-
2 at typical light water reactor conditions, and a comparison with release models
-
US Nuclear Regulatory Commission
-
2 at typical light water reactor conditions, and a comparison with release models, Report NUREG/CR2298, US Nuclear Regulatory Commission, 1981.
-
(1981)
Report NUREG/CR2298
-
-
Appelhans, A.D.1
Turnbull, J.A.2
-
9
-
-
0345382586
-
-
Ursu I., Gheorghiu C., Soare C., Gheorghiu E. Rev. Roum. Phys. Tome. 32(9):1987;951-960.
-
(1987)
Rev. Roum. Phys. Tome
, vol.32
, Issue.9
, pp. 951-960
-
-
Ursu, I.1
Gheorghiu, C.2
Soare, C.3
Gheorghiu, E.4
-
13
-
-
0344520274
-
2 fuel elements and a discussion of proposed in-reactor experiments that may be used to test its validity
-
AECL-700
-
2 fuel elements and a discussion of proposed in-reactor experiments that may be used to test its validity, Atomic Energy of Canada Limited Report, AECL-700, 1957.
-
(1957)
Atomic Energy of Canada Limited Report
-
-
Booth, A.H.1
-
20
-
-
0005045302
-
An experimental and theoretical treatment of the release of Kr from hyperstoichiometric uranium dioxide
-
Gloucestershire, England, 7-9 April Central Electricity Generating Board
-
J.C. Killeen, J.A. Turnbull, An experimental and theoretical treatment of the release of Kr from hyperstoichiometric uranium dioxide, in: Proceedings of the Workshop Chemical Reactivity of Oxide Fuel and Fission Product Release, Gloucestershire, England, 7-9 April 1987, p. 387; Central Electricity Generating Board.
-
(1987)
In: Proceedings of the Workshop Chemical Reactivity of Oxide Fuel and Fission Product Release
, pp. 387
-
-
Killeen, J.C.1
Turnbull, J.A.2
-
24
-
-
0002238072
-
-
Lewis B.J., Andre B., Morel B., Dehaudt P., Maro D., Purdy P.L., Cox D.S., Iglesias F.C., Osborne M.F., Lorenz R.A. J. Nucl. Mater. 227:1995;83.
-
(1995)
J. Nucl. Mater.
, vol.227
, pp. 83
-
-
Lewis, B.J.1
Andre, B.2
Morel, B.3
Dehaudt, P.4
Maro, D.5
Purdy, P.L.6
Cox, D.S.7
Iglesias, F.C.8
Osborne, M.F.9
Lorenz, R.A.10
-
27
-
-
0344089064
-
Time-dependent release of fission products from LWR fuel under severe accident conditions
-
Avignon, France, 2-7 October
-
M.F. Osborne, R.A. Lorenz, J.L. Collins, T. Nakamura, Time-dependent release of fission products from LWR fuel under severe accident conditions, in: Proceedings of the International Conference on Thermal Reactor Safety, Avignon, France, 2-7 October, 1988, p. 1293.
-
(1988)
In: Proceedings of the International Conference on Thermal Reactor Safety
, pp. 1293
-
-
Osborne, M.F.1
Lorenz, R.A.2
Collins, J.L.3
Nakamura, T.4
-
28
-
-
0345382584
-
Correlation of recent fission product release data
-
in: J.T. Rogers (Ed.), Hemisphere, New York
-
T.S. Kress, R.A. Lorenz, T. Nakamura, M.F. Osborne, Correlation of recent fission product release data, in: J.T. Rogers (Ed.), Fission Product Transport Processes in Reactor Accidents, Hemisphere, New York, 1990.
-
(1990)
Fission Product Transport Processes in Reactor Accidents
-
-
Kress, T.S.1
Lorenz, R.A.2
Nakamura, T.3
Osborne, M.F.4
-
30
-
-
3643098772
-
2
-
Snowbird, Utah, 15-19 July Electric Power Research Institute
-
2, in: Proc. Topl. Mtg. Fission Product Behaviour and Source Term Research, Snowbird, Utah, 15-19 July 1984; Electric Power Research Institute, 1985.
-
(1984)
In: Proc. Topl. Mtg. Fission Product Behaviour and Source Term Research
-
-
Peehs, M.1
Kaspar, G.2
Neeb, K.H.3
-
31
-
-
85031617932
-
2
-
Karlsruhe, FRG, 11-15 November IWGFPT/25
-
2, IAEA Technical Committee On Fuel Rod Internal Chemistry And Fission Product Behaviour, Karlsruhe, FRG, 11-15 November 1985, IWGFPT/25.
-
(1985)
IAEA Technical Committee on Fuel Rod Internal Chemistry and Fission Product Behaviour
-
-
Peehs, M.1
Kaspar, G.2
Sontheimer, F.3
-
32
-
-
0344951071
-
2 in presence of zircaloy and oxygen
-
in: Product Release, Gloucestershire, England, 7-9 April Central Electricity Generating Board
-
2 in presence of zircaloy and oxygen, Proc. Workshop Chemical Reactivity of Oxide Fuel and Fission, in: Product Release, Gloucestershire, England, 7-9 April 1987, p. 441; Central Electricity Generating Board.
-
(1987)
Proc. Workshop Chemical Reactivity of Oxide Fuel and Fission
, pp. 441
-
-
Kaspar, G.1
Peehs, M.2
-
34
-
-
0029173012
-
-
Harnden-gillis A.C., Lewis B.J., Andrews W.S., Purdy P.L., Osborne M.F., Lorenz R.A. Nucl. Technol. 109:1995;39.
-
(1995)
Nucl. Technol.
, vol.109
, pp. 39
-
-
Harnden-Gillis, A.C.1
Lewis, B.J.2
Andrews, W.S.3
Purdy, P.L.4
Osborne, M.F.5
Lorenz, R.A.6
-
40
-
-
0030129541
-
-
Andre B., Ducros G., Leveque J.P., Osborne M.F., Lorenz R.A., Maro D. Nucl. Technol. 114:1996;23.
-
(1996)
Nucl. Technol.
, vol.114
, pp. 23
-
-
Andre, B.1
Ducros, G.2
Leveque, J.P.3
Osborne, M.F.4
Lorenz, R.A.5
Maro, D.6
-
42
-
-
0031988854
-
-
Lewis B.J., Corse B.J., Thompson W.T., Kaye M.H., Iglesias F.C., Elder P., Dickson R., Liu Z. J. Nucl. Mater. 252:1998;235.
-
(1998)
J. Nucl. Mater.
, vol.252
, pp. 235
-
-
Lewis, B.J.1
Corse, B.J.2
Thompson, W.T.3
Kaye, M.H.4
Iglesias, F.C.5
Elder, P.6
Dickson, R.7
Liu, Z.8
-
51
-
-
0347468267
-
2 in air and steam with relevance to fission product releases
-
Anaheim, California, 9-12 September NUREG/CP-0078, US Nuclear Regulatory Commission
-
2 in air and steam with relevance to fission product releases, in: Proceedings of the American Chemical Society Symposium on Chemical Phenomenon Associated with Radioactivity during Severe Nuclear Plant Accidents, Anaheim, California, 9-12 September 1986, NUREG/CP-0078, US Nuclear Regulatory Commission, pp. 2-35.
-
(1986)
In: Proceedings of the American Chemical Society Symposium on Chemical Phenomenon Associated with Radioactivity during Severe Nuclear Plant Accidents
, pp. 2-35
-
-
Cox, D.S.1
Iglesias, F.C.2
Hunt, C.E.L.3
Keller, N.A.4
Barrand, R.D.5
Mitchell, J.R.6
O'Connor, R.F.7
-
52
-
-
84917964009
-
2 oxidation in a steam environment
-
Canadian Nuclear Society, St. John, New Brunswick, 25-27 August
-
2 oxidation in a steam environment, in: Proceedings of the 16th Annual Nuclear Simulation Symposium, Canadian Nuclear Society, St. John, New Brunswick, 25-27 August 1992.
-
(1992)
In: Proceedings of the 16th Annual Nuclear Simulation Symposium
-
-
Aboud, R.1
Nath, V.I.2
Hu, R.3
-
54
-
-
0022926332
-
Vaporization Thermodynamics Of Fission Products From Fuel Under Nuclear-Accident Conditions
-
American Ceramic Society, Columbus, Ohio
-
D. Cubicciotti, Vaporization Thermodynamics Of Fission Products From Fuel Under Nuclear-Accident Conditions, Advances In Ceramics, vol. 17, American Ceramic Society, Columbus, Ohio, 1986, p. 211.
-
(1986)
Advances in Ceramics
, vol.17
, pp. 211
-
-
Cubicciotti, D.1
-
59
-
-
0142173990
-
-
Washington, DC
-
M.H. Kaye, W.T. Thompson, B.J. Lewis, Trans. Am. Nucl. Soc., Washington, DC 79 (1998) 123.
-
(1998)
Trans. Am. Nucl. Soc.
, vol.79
, pp. 123
-
-
Kaye, M.H.1
Thompson, W.T.2
Lewis, B.J.3
-
61
-
-
0345382576
-
ACRR fission product release tests ST-1 and ST-2
-
Avignon, France, 2-7 October
-
M.D. Allen, H.W. Stockman, K.O. Reil, A.J. Grimley, W.J. Camp, ACRR fission product release tests ST-1 and ST-2, in: Proceedings of the International Conference on Thermal Reactor Safety, vol. 5, Avignon, France, 2-7 October 1988.
-
(1988)
In: Proceedings of the International Conference on Thermal Reactor Safety
, vol.5
-
-
Allen, M.D.1
Stockman, H.W.2
Reil, K.O.3
Grimley, A.J.4
Camp, W.J.5
-
62
-
-
0025636576
-
Ruthenium release kinetics from uranium oxides
-
Dubrovnik, Yugoslavia, 22-26 May Hemisphere, New York
-
F.C. Iglesias, C.E.L. Hunt, F. Garisto, D.S. Cox, Ruthenium release kinetics from uranium oxides, in: Proceedings of the ICHMT Conference on Fission Product Transport Processes in Reactor Accidents, Dubrovnik, Yugoslavia, 22-26 May 1989, Hemisphere, New York, 1990, pp. 187-196.
-
(1989)
In: Proceedings of the ICHMT Conference on Fission Product Transport Processes in Reactor Accidents
, pp. 187-196
-
-
Iglesias, F.C.1
Hunt, C.E.L.2
Garisto, F.3
Cox, D.S.4
-
63
-
-
0024142878
-
Thermodynamic behaviour of ruthenium at high temperatures
-
AECL-9552
-
F. Garisto, Thermodynamic behaviour of ruthenium at high temperatures, Atomic Energy of Canada Limited report, AECL-9552, 1988.
-
(1988)
Atomic Energy of Canada Limited Report
-
-
Garisto, F.1
-
70
-
-
70350005309
-
A model for fuel oxidation and diffusion-based fission product release under severe nuclear reactor accident conditions
-
Pembroke, Ontario, 1-4 October
-
P.L. Purdy, B.J. Lewis, W.S. Andrews, D.S. Cox, F.C. Iglesias, A model for fuel oxidation and diffusion-based fission product release under severe nuclear reactor accident conditions, in: Fourth International Conference on CANDU Fuel, Pembroke, Ontario, 1-4 October 1995.
-
(1995)
In: Fourth International Conference on CANDU Fuel
-
-
Purdy, P.L.1
Lewis, B.J.2
Andrews, W.S.3
Cox, D.S.4
Iglesias, F.C.5
-
71
-
-
70350026775
-
Matrix stripping and fission product release at high temperature
-
Sorrento, Italy, 21-25 March (IAEA-SM-296/99)
-
C.A. Alexander, J.S. Ogden, L. Chan, R.W. Wright, Matrix stripping and fission product release at high temperature, in: Proceedings of the IAEA/OECD International Symposium on Severe Accidents in Nuclear Power Plants, Sorrento, Italy, 21-25 March 1988 (IAEA-SM-296/99).
-
(1988)
In: Proceedings of the IAEA/OECD International Symposium on Severe Accidents in Nuclear Power Plants
-
-
Alexander, C.A.1
Ogden, J.S.2
Chan, L.3
Wright, R.W.4
-
73
-
-
37149038795
-
2 in air and steam
-
Hamilton, Ontario, Canada, 26-30 August Pergamon Press, New York, ISBN 0-18-040415-4
-
2 in air and steam, in: Proceedings of the International Symposium on High Temperature Oxidation and Sulphidation Process, Hamilton, Ontario, Canada, 26-30 August 1990, Pergamon Press, New York, ISBN 0-18-040415-4.
-
(1990)
In: Proceedings of the International Symposium on High Temperature Oxidation and Sulphidation Process
-
-
Cox, D.S.1
Hunt, C.E.L.2
O'Connor, R.F.3
Barrand, R.D.4
Iglesias, F.C.5
-
74
-
-
0026193465
-
A model for the release of low-volatility fission products in oxidizing conditions
-
AECL-10440, July
-
D.S. Cox, C.E.L. Hunt, Z. Liu, F.C. Iglesias, N.A. Keller, R.D. Barrand, R.F. O'Connor, A model for the release of low-volatility fission products in oxidizing conditions, Atomic Energy of Canada Limited report, AECL-10440, July 1991.
-
(1991)
Atomic Energy of Canada Limited Report
-
-
Cox, D.S.1
Hunt, C.E.L.2
Liu, Z.3
Iglesias, F.C.4
Keller, N.A.5
Barrand, R.D.6
O'Connor, R.F.7
-
75
-
-
85031621850
-
-
these Proceedings
-
D.R. Olander, these Proceedings, p. 187.
-
-
-
Olander, D.R.1
-
76
-
-
0003737834
-
-
US Nuclear Regulatory Commission, NUREG/CR-5545, SAND90-0756, Rev. 1, R3, R4, December
-
T.J. Heames, D.A. Williams, N.E. Bixler, A.J. Grimley, C.J. Wheatley, N.A. Johns, P. Domagala, L.W. Dickson, C.A. Alexander, I. Osborn-Lee, S. Zawadzki, J. Rest, A. Mason, R.Y. Lee, VICTORIA: A Mechanistic Model of Radionuclide Behaviour in the Reactor Coolant System Under Severe Accident Conditions, US Nuclear Regulatory Commission, NUREG/CR-5545, SAND90-0756, Rev. 1, R3, R4, December 1992.
-
(1992)
VICTORIA: A Mechanistic Model of Radionuclide Behaviour in the Reactor Coolant System under Severe Accident Conditions
-
-
Heames, T.J.1
Williams, D.A.2
Bixler, N.E.3
Grimley, A.J.4
Wheatley, C.J.5
Johns, N.A.6
Domagala, P.7
Dickson, L.W.8
Alexander, C.A.9
Osborn-Lee, I.10
Zawadzki, S.11
Rest, J.12
Mason, A.13
Lee, R.Y.14
-
79
-
-
0343250572
-
Experimental studies and thermodynamic modeling of volatilities of uranium, plutonium, and americium from their oxides
-
UCRL-ID-114774
-
O.H. Krikorian et al., Experimental studies and thermodynamic modeling of volatilities of uranium, plutonium, and americium from their oxides, Lawrence Livermore National Laboratory report, UCRL-ID-114774, 1993.
-
(1993)
Lawrence Livermore National Laboratory Report
-
-
Krikorian, O.H.1
-
80
-
-
0343686244
-
Calculated Thermodynamic Functions for Gas-phase Uranium, Neptunium, Plutonium, and Americium Oxides, Oxyhydrioxides, Oxychlorides, and Oxyfluorides
-
UCRL-JC-122278
-
B.B. Ebbinghaus, Calculated Thermodynamic Functions for Gas-phase Uranium, Neptunium, Plutonium, and Americium Oxides, Oxyhydrioxides, Oxychlorides, and Oxyfluorides, Lawrence Livermore National Laboratory report, UCRL-JC-122278, 1995.
-
(1995)
Lawrence Livermore National Laboratory Report
-
-
Ebbinghaus, B.B.1
-
83
-
-
0344951051
-
ELSA: A simplified code for fission product release calculations
-
Transactions of the American Nuclear Society 10-14 November ISSN 0003-018X American Nuclear Society, La Grange Park, IL, 1996
-
H. Manenc, M.J. Notley, ELSA: A simplified code for fission product release calculations, Transactions of the American Nuclear Society, 1996 International Conference on the Global Benefits of Nuclear Technology, 10-14 November, 1996, ISSN 0003-018X, p. 250, American Nuclear Society, La Grange Park, IL, 1996.
-
(1996)
1996 International Conference on the Global Benefits of Nuclear Technology
, pp. 250
-
-
Manenc, H.1
Notley, M.J.2
-
86
-
-
85031621415
-
A Study of the Pellet/Clad (Uranium Dioxide/Zircaloy-4) Interaction at 1373 and 1473 K
-
AECL-7785, February
-
H.E. Rosinger, A Study of the Pellet/Clad (Uranium Dioxide/Zircaloy-4) Interaction at 1373 and 1473 K, Atomic Energy of Canada Limited report, AECL-7785, February 1983.
-
(1983)
Atomic Energy of Canada Limited Report
-
-
Rosinger, H.E.1
-
87
-
-
84915716827
-
-
Snowbird, UT American Nuclear Society, Lagrange Park, IL
-
R.V. Strain, Proc. Top. Mtg. Fission Product Behavior and Source Term Research, Snowbird, UT, 1983, American Nuclear Society, Lagrange Park, IL, 1984, p. 2.1.
-
(1983)
Proc. Top. Mtg. Fission Product Behavior and Source Term Research
, pp. 21
-
-
Strain, R.V.1
-
88
-
-
0041621699
-
-
Sorrento, Italy, 21-25 March (IAEA-SM-296/99)
-
P. Hofmann, H. Uetsuka, A.N. Wilhelm, E.A. Garcia, in: Proceedings of the IAEA/OECD International Symposium on Severe Accidents in Nuclear Power Plants, Sorrento, Italy, 21-25 March 1988 (IAEA-SM-296/99), p. 3.
-
(1988)
In: Proceedings of the IAEA/OECD International Symposium on Severe Accidents in Nuclear Power Plants
, pp. 3
-
-
Hofmann, P.1
Uetsuka, H.2
Wilhelm, A.N.3
Garcia, E.A.4
-
91
-
-
70350005306
-
2 by molten zircaloy-4 cladding
-
Karlsruhe, FRG, September Also published as Atomic Energy of Canada Limited report, AECL-8387, March
-
2 by molten zircaloy-4 cladding, in: Proceedings of the Fifth International Meeting on Thermal Nuclear Reactor Safety, Karlsruhe, FRG, September 1984. Also published as Atomic Energy of Canada Limited report, AECL-8387, March 1985.
-
(1984)
In: Proceedings of the Fifth International Meeting on Thermal Nuclear Reactor Safety
-
-
Rosinger, H.E.1
Demoline, K.2
Rondeau, R.K.3
-
103
-
-
0009165675
-
-
SAND89-0308, NUREG/CR-5345, September
-
M.D. Allen, H.W. Stockman, K.O. Reil, Fission product release and fuel behavior of irradiated light water reactor fuel under severe accident conditions: The ACRR ST-1 experiment, SAND89-0308, NUREG/CR-5345, September 1991.
-
(1991)
Fission Product Release and Fuel Behavior of Irradiated Light Water Reactor Fuel under Severe Accident Conditions: The ACRR ST-1 Experiment
-
-
Allen, M.D.1
Stockman, H.W.2
Reil, K.O.3
-
105
-
-
0345382553
-
-
ORNL/TM-11400, NUREG/CR-5481, January
-
M.F. Osborne, R.A. Lorenz, J.L. Collins, J.R. Tracis, C.S. Webster, T. Nakamura, Data Summary Report for Fission Product Release Test VI-4, ORNL/TM-11400, NUREG/CR-5481, January 1991.
-
(1991)
Data Summary Report for Fission Product Release Test VI-4
-
-
Osborne, M.F.1
Lorenz, R.A.2
Collins, J.L.3
Tracis, J.R.4
Webster, C.S.5
Nakamura, T.6
-
107
-
-
0345382550
-
-
Commissariat á l"Energie Atomique report, DPEI/SEAC No. 91/08, November
-
J.P. Leveque, G. Lhiaubet, B. Boulaud, HEVA Experimental programme: Final Report, Commissariat á l"Energie Atomique report, DPEI/SEAC No. 91/08, November 1991.
-
(1991)
HEVA Experimental Programme: Final Report
-
-
Leveque, J.P.1
Lhiaubet, G.2
Boulaud, B.3
-
109
-
-
0043190324
-
The interaction of Zircaloy cladding with fission product tellurium released during a severe reactor accident
-
Gloucestershire, England, 7-9 April Central Electricity Generating Board
-
B.R. Bowsher, S. Dickinson, R.A. Gomme, R.A. Jenkins, A.L. Nichols, J.S. Ogden, The interaction of Zircaloy cladding with fission product tellurium released during a severe reactor accident, in: Proceedings of the Workshop Chemical Reactivity of Oxide Fuel and Fission Product Release, Gloucestershire, England, 7-9 April 1987; Central Electricity Generating Board, p. 455.
-
(1987)
In: Proceedings of the Workshop Chemical Reactivity of Oxide Fuel and Fission Product Release
, pp. 455
-
-
Bowsher, B.R.1
Dickinson, S.2
Gomme, R.A.3
Jenkins, R.A.4
Nichols, A.L.5
Ogden, J.S.6
-
113
-
-
0028566751
-
Convective-diffusive transport of fission products in the gap of a failed fuel element
-
Canadian Nuclear Society, Session 5C, Montreal, Quebec, 5-8 June
-
Z.W. Lian, L.N. Carlucci, V.I. Arimescu, Convective-diffusive transport of fission products in the gap of a failed fuel element, Proceedings of the 15th Annual Conference of the Canadian Nuclear Society, Canadian Nuclear Society, Session 5C, Montreal, Quebec, 5-8 June 1994.
-
(1994)
Proceedings of the 15th Annual Conference of the Canadian Nuclear Society
-
-
Lian, Z.W.1
Carlucci, L.N.2
Arimescu, V.I.3
-
114
-
-
85031626972
-
Simulation of the transport of volatile fission products within the fuel-to-sheath gap of defective CANDU fuel rods
-
ISBN 0-919784-48-8, Toronto, Ontario, 21-24 September
-
H.W. Bonin, B.J. Lewis, Simulation of the transport of volatile fission products within the fuel-to-sheath gap of defective CANDU fuel rods, in: Proceedings of the Fifth International Conference on CANDU Fuel, ISBN 0-919784-48-8, Toronto, Ontario, 21-24 September 1997, pp. 118-132.
-
(1997)
In: Proceedings of the Fifth International Conference on CANDU Fuel
, pp. 118-132
-
-
Bonin, H.W.1
Lewis, B.J.2
-
116
-
-
85031632394
-
-
these Proceedings
-
B.J. Lewis, these Proceedings, p. 221.
-
-
-
Lewis, B.J.1
-
118
-
-
85031621376
-
-
Brookhaven National Laboratory report, W-6426, 17 April
-
V. Mubayi, J.A. Gieseke, D.R. Olander, M. Schwarz, Victoria Independent Peer Review, Brookhaven National Laboratory report, W-6426, 17 April 1997.
-
(1997)
Victoria Independent Peer Review
-
-
Mubayi, V.1
Gieseke, J.A.2
Olander, D.R.3
Schwarz, M.4
-
122
-
-
0018059842
-
-
Rand M.H., Ackerman R.J., Gronwold F., Oetting F.L., Pattoret A. Rev. Int. Hautes Temp. Refract. 15:1978;355.
-
(1978)
Rev. Int. Hautes Temp. Refract.
, vol.15
, pp. 355
-
-
Rand, M.H.1
Ackerman, R.J.2
Gronwold, F.3
Oetting, F.L.4
Pattoret, A.5
-
129
-
-
0345382553
-
-
ORNL/TM-11105, NUREG/CR-5340, September
-
M.F. Osborne, J.L. Collins, R.A. Lorenz, J.R. Travis, C.S. Webster, Data Summary Report for Fission Product Release Test VI-2, ORNL/TM-11105, NUREG/CR-5340, September 1989.
-
(1989)
Data Summary Report for Fission Product Release Test VI-2
-
-
Osborne, M.F.1
Collins, J.L.2
Lorenz, R.A.3
Travis, J.R.4
Webster, C.S.5
-
130
-
-
70350036177
-
An in-reactor loss-of-coolant test with flow blockage and rewet
-
Portland, Oregon, July Also issued as Atomic Energy of Canada Limited report, AECL-10464, October 1991
-
R.D. Macdonald, J.W. Devaal, D.S. Cox, L.W. Dickson, M.J. Jonckheere, C.E. Ferris, N.A. Keller, S.L. Wadsworth, An in-reactor loss-of-coolant test with flow blockage and rewet, in: Proceedings of the International Topical Meeting on Thermal Reactor Safety, Portland, Oregon, July 1991. Also issued as Atomic Energy of Canada Limited report, AECL-10464, October 1991.
-
(1991)
In: Proceedings of the International Topical Meeting on Thermal Reactor Safety
-
-
Macdonald, R.D.1
Devaal, J.W.2
Cox, D.S.3
Dickson, L.W.4
Jonckheere, M.J.5
Ferris, C.E.6
Keller, N.A.7
Wadsworth, S.L.8
-
131
-
-
0001907007
-
-
Leveque J.P., Andre B., Ducros G., Le Marois G., Lhiaubet G. Nucl. Technol. 188:1994;33.
-
(1994)
Nucl. Technol.
, vol.188
, pp. 33
-
-
Leveque, J.P.1
Andre, B.2
Ducros, G.3
Le Marois, G.4
Lhiaubet, G.5
-
133
-
-
0022942948
-
2 oxidation
-
Chalk River Nuclear Laboratories, Chalk River, Ontario, Canada, 6-8 October
-
2 oxidation, in: Proceedings of the International Conference on CANDU Fuel, Chalk River Nuclear Laboratories, Chalk River, Ontario, Canada, 6-8 October 1986, p. 508.
-
(1986)
In: Proceedings of the International Conference on CANDU Fuel
, pp. 508
-
-
Hunt, C.E.L.1
Iglesias, F.C.2
Cox, D.S.3
Keller, N.A.4
Barrand, R.D.5
Mitchell, J.R.6
O'Connor, R.F.7
-
134
-
-
0026975461
-
Fission-product release during post-test annealing of high-burnup CANDU fuel
-
Pembroke, Ont., Canada, 4-8 October
-
D.S. Cox, Z. Liu, R.S. Dickson, P.H. Elder, Fission-product release during post-test annealing of high-burnup CANDU fuel, in: Proceedings of the Third International Conference on CANDU Fuel, Pembroke, Ont., Canada, 4-8 October 1992, pp. 4-61.
-
(1992)
In: Proceedings of the Third International Conference on CANDU Fuel
, pp. 4-61
-
-
Cox, D.S.1
Liu, Z.2
Dickson, R.S.3
Elder, P.H.4
-
135
-
-
0004409134
-
2 in air and inert conditions at 1700-2350°K - Analysis of the MCE-1Experiment
-
Portland, Oregon, USA, 21-25 July Also issued as Atomic Energy of Canada Limited report, AECL-10438
-
2 in air and inert conditions at 1700-2350°K - Analysis of the MCE-1Experiment, in: Proceedings of the American Nuclear Society International Topical Meeting on Safety of Thermal Reactors, Portland, Oregon, USA, 21-25 July 1991. Also issued as Atomic Energy of Canada Limited report, AECL-10438.
-
(1991)
In: Proceedings of the American Nuclear Society International Topical Meeting on Safety of Thermal Reactors
-
-
Cox, D.S.1
Hunt, C.E.L.2
Liu, Z.3
Keller, N.A.4
Barrand, R.D.5
O'Connor, R.F.6
Iglesias, F.C.7
-
136
-
-
0028584970
-
Cesium release from CANDU fuel in argon, steam and air: The UCE12 experiment
-
Montreal, Que., Canada
-
R.S. Dickson, Z. Liu, D.S. Cox, N.A. Keller, R.F. O'Connor, R.D. Barrand, Cesium release from CANDU fuel in argon, steam and air: The UCE12 experiment, in: Proceedings of the 15th Annual Canadian Nuclear Association Meeting, Montreal, Que., Canada, 1994.
-
(1994)
In: Proceedings of the 15th Annual Canadian Nuclear Association Meeting
-
-
Dickson, R.S.1
Liu, Z.2
Cox, D.S.3
Keller, N.A.4
O'Connor, R.F.5
Barrand, R.D.6
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