-
1
-
-
85031631642
-
-
US Report WAPD-MM-184 (February 1953), Bettis Atomic Power Lab., West Mifflin, PA
-
K.M. Goldman, D.E. Thomas, Hydrogen pickup during corrosion testing of zirconium, US Report WAPD-MM-184 (February 1953), Bettis Atomic Power Lab., West Mifflin, PA.
-
Hydrogen Pickup during Corrosion Testing of Zirconium
-
-
Goldman, K.M.1
Thomas, D.E.2
-
2
-
-
0000299765
-
Enhancement of aqueous corrosion of Zircaloy-4 due to hydride precipitation at the metal/oxide interface
-
Kobe, Japan, ASTM-STP-1132
-
A.M. Garde, Enhancement of aqueous corrosion of Zircaloy-4 due to hydride precipitation at the metal/oxide interface, in: Proceedings of 9th Int. Symp. on Zr in the Nuclear Industry, Kobe, Japan, ASTM-STP-1132, 1991, pp. 556-594.
-
(1991)
In: Proceedings of 9th Int. Symp. on Zr in the Nuclear Industry
, pp. 556-594
-
-
Garde, A.M.1
-
3
-
-
0038925652
-
PWR Zircaloy fuel cladding corrosion performance, mechanisms and modelling
-
Garmisch-Partenkirchen, Ger., ASTM-STP-1295
-
B. Cheng, P.M. Gilmore, H.H. Klepfer, PWR Zircaloy fuel cladding corrosion performance, mechanisms and modelling, in: Proceedings of 11th Int. Symp. on Zr in the Nuclear Industry, Garmisch-Partenkirchen, Ger., ASTM-STP-1295, 1996, pp. 137-160.
-
(1996)
In: Proceedings of 11th Int. Symp. on Zr in the Nuclear Industry
, pp. 137-160
-
-
Cheng, B.1
Gilmore, P.M.2
Klepfer, H.H.3
-
4
-
-
0344520198
-
Fuel performance evaluation for EPRI program planning
-
Avignon, France
-
R.L. Yang, O. Ozer, H.H. Klepfer, Fuel performance evaluation for EPRI program planning, in: Proceedings of Int. Topical Meeting on LWR Fuel Performance-Fuel for the 90's, Avignon, France, 1991, pp. 258-271.
-
(1991)
In: Proceedings of Int. Topical Meeting on LWR Fuel Performance-Fuel for the 90's
, pp. 258-271
-
-
Yang, R.L.1
Ozer, O.2
Klepfer, H.H.3
-
5
-
-
0344520196
-
-
ibid.
-
P. Guedeney, M. Trotabas, M. Boschiero, C. Forat, P. Blanpain, FRAGEMA Fuel Rod Behaviour Characterisation at High Burnup, ibid., 2 (1991) 627-638.
-
(1991)
FRAGEMA Fuel Rod Behaviour Characterisation at High Burnup
, vol.2
, pp. 627-638
-
-
Guedeney, P.1
Trotabas, M.2
Boschiero, M.3
Forat, C.4
Blanpain, P.5
-
6
-
-
0346406240
-
Recent ABB design and performance experience
-
W. Palm Beach, FL
-
G. Vesterlund, L.V. Corsetti, Recent ABB design and performance experience, in: Proceedings of Internal Topical Meeting on LWR Fuel Performance, W. Palm Beach, FL, 1994, pp. 62-70.
-
(1994)
In: Proceedings of Internal Topical Meeting on LWR Fuel Performance
, pp. 62-70
-
-
Vesterlund, G.1
Corsetti, L.V.2
-
7
-
-
0021789017
-
Mechanisms of hydrogen absorption by zirconium alloys
-
Atomic Energy of Canada Ltd., Chalk River Nuclear Laboratories
-
B. Cox, Mechanisms of hydrogen absorption by zirconium alloys, Canadian Report AECL-8702 (1985), Atomic Energy of Canada Ltd., Chalk River Nuclear Laboratories.
-
(1985)
Canadian Report AECL-8702
-
-
Cox, B.1
-
11
-
-
85031637691
-
Hydrogen permeation of oxide films on zirconium
-
May Atomic International, Canoga Park, CA
-
T. Smith, Hydrogen permeation of oxide films on zirconium, US Report NAA-SR-6267 (May 1962), Atomic International, Canoga Park, CA.
-
(1962)
US Report NAA-SR-6267
-
-
Smith, T.1
-
13
-
-
85031626795
-
-
414t and U.S. Report HW-76562 Rev. (1963), Hanford Atomic Products Operation, Richland, WA
-
D.W. Shannon, Corrosion 19 (1963) 414t and U.S. Report HW-76562 Rev. (1963), Hanford Atomic Products Operation, Richland, WA.
-
(1963)
Corrosion
, vol.19
-
-
Shannon, D.W.1
-
17
-
-
0004486035
-
Some experiments on the permeation of hydrogen through oxide films on zirconium
-
WAPD-BT-19 Bettis Atomic Power Lab., W. Mifflin, PA
-
S. Aronson, Some experiments on the permeation of hydrogen through oxide films on zirconium, U.S. Report, Bettis Technical Review, WAPD-BT-19 (1960), pp. 75-81, Bettis Atomic Power Lab., W. Mifflin, PA.
-
(1960)
U.S. Report, Bettis Technical Review
, pp. 75-81
-
-
Aronson, S.1
-
20
-
-
85031624557
-
A contribution to the mechanism of dissolution and diffusion of oxygen in zirconium
-
Vienna, July SM66/18; and Swiss Report EIR-82 (1965) Würenlingen, CH
-
W.W. Doerffler, A contribution to the mechanism of dissolution and diffusion of oxygen in zirconium, in: Proceedings of IAEA Conference on Thermodynamics of Nuclear Materials and Atomic Transformations in Solids, Vienna, July 1965, SM66/18; and Swiss Report EIR-82 (1965), Würenlingen, CH.
-
(1965)
In: Proceedings of IAEA Conference on Thermodynamics of Nuclear Materials and Atomic Transformations in Solids
-
-
Doerffler, W.W.1
-
22
-
-
0021630582
-
Cracking zirconium alloys in hydrogen
-
Vancouver, BC, ASTM-STP-824
-
C.E. Coleman, B. Cox, Cracking zirconium alloys in hydrogen, in: Proceedings of 6th Int. Symp. on Zr in the Nuclear Industry, Vancouver, BC, ASTM-STP-824, 1984, pp. 675-690.
-
(1984)
In: Proceedings of 6th Int. Symp. on Zr in the Nuclear Industry
, pp. 675-690
-
-
Coleman, C.E.1
Cox, B.2
-
24
-
-
84904915608
-
-
McIntyre N.S., Davidson R.D., Eisener C.G., Good G.M., Mount G.R., Warr B.D., Elmoselhi M., Vac J. Sci. Technol. A. 9:1991;1402.
-
(1991)
Sci. Technol. A
, vol.9
, pp. 1402
-
-
McIntyre, N.S.1
Davidson, R.D.2
Eisener, C.G.3
Good, G.M.4
Mount, G.R.5
Warr, B.D.6
Elmoselhi, M.7
Vac, J.8
-
26
-
-
0010847441
-
Hydrogen distribution in oxidised zirconium alloys by autoradiography
-
Atomic Energy of Canada Ltd., Chalk River Nuclear Laboratories
-
C. Roy, Hydrogen distribution in oxidised zirconium alloys by autoradiography, Canadian Report, AECL-2085 (1964), Atomic Energy of Canada Ltd., Chalk River Nuclear Laboratories.
-
(1964)
Canadian Report, AECL-2085
-
-
Roy, C.1
-
28
-
-
5544304477
-
Hydrogen pickup and redistribution in alpha-annealed Zircaloy-4
-
Garmisch-Partenkirchen, Ger., ASTM-STP-1295
-
B.F. Kammenzind, D.G. Franklin, H.R. Peters, W.J. Duffin, Hydrogen pickup and redistribution in alpha-annealed Zircaloy-4, in: Proceedings of 11th Int. Symp. on Zr in the Nuclear Industry, Garmisch-Partenkirchen, Ger., ASTM-STP-1295, 1996, pp. 338-370.
-
(1996)
In: Proceedings of 11th Int. Symp. on Zr in the Nuclear Industry
, pp. 338-370
-
-
Kammenzind, B.F.1
Franklin, D.G.2
Peters, H.R.3
Duffin, W.J.4
-
29
-
-
0344088967
-
-
Electric Power Research Inst. Report NP6979-D
-
B. Cox, N. Ramasubramanian, V.C. Ling, Zircaloy Corrosion Properties Under LWR Coolant Conditions, Part 1, Electric Power Research Inst. Report NP6979-D, 1990.
-
(1990)
Zircaloy Corrosion Properties under LWR Coolant Conditions
, Issue.1 PART
-
-
Cox, B.1
Ramasubramanian, N.2
Ling, V.C.3
-
30
-
-
0009057415
-
A study of the hydrogen uptake mechanism in zirconium alloys
-
Baltimore, MD., ASTM-STP-1245
-
M.B. Elmoselhi, B.D. Warr, S. McIntyre, A study of the hydrogen uptake mechanism in zirconium alloys, in: Proceedings of 10th Int. Symp. on Zr in the Nuclear Industry, Baltimore, MD., ASTM-STP-1245, 1994, pp. 62-79.
-
(1994)
In: Proceedings of 10th Int. Symp. on Zr in the Nuclear Industry
, pp. 62-79
-
-
Elmoselhi, M.B.1
Warr, B.D.2
McIntyre, S.3
-
31
-
-
0345382494
-
Lithium and boron effects in the corrosion mechanism of zirconium alloys under coolant chemistry conditions
-
Bournemouth, UK
-
N. Ramasubramanian, Lithium and boron effects in the corrosion mechanism of zirconium alloys under coolant chemistry conditions, in: Proceedings of 7th Int. Conf. on Water Chemistry of Nuclear Reactor Systems, Bournemouth, vol. 1, UK, 1996, pp. 91-93
-
(1996)
In: Proceedings of 7th Int. Conf. on Water Chemistry of Nuclear Reactor Systems
, vol.1
, pp. 91-93
-
-
Ramasubramanian, N.1
-
34
-
-
84920629491
-
Oxidation of a Zr-2.5%Nb Alloy in steam and air
-
UK Atomic Energy Authority, Harwell, Berks
-
B. Cox, J.A. Read, Oxidation of a Zr-2.5%Nb Alloy in steam and air, UK Report, AERE-R4459 (1963), UK Atomic Energy Authority, Harwell, Berks.
-
(1963)
UK Report, AERE-R4459
-
-
Cox, B.1
Read, J.A.2
-
37
-
-
84913040155
-
The oxidation and corrosion of zirconium and its alloys, Part X, Hydrogen absorption during oxidation in steam and aqueous solutions
-
UK Atomic Energy Authority, Harwell, Berks
-
B. Cox, M.J. Davis, A.D. Dent, The oxidation and corrosion of zirconium and its alloys, Part X, Hydrogen absorption during oxidation in steam and aqueous solutions, UK Report, AERE-M621 (April 1960), UK Atomic Energy Authority, Harwell, Berks.
-
(1960)
UK Report, AERE-M621
-
-
Cox, B.1
Davis, M.J.2
Dent, A.D.3
-
38
-
-
0344088968
-
The effect of some alloying additions on the oxidation of zirconium in steam
-
September UK Atomic Energy Authority, Harwell, Berks
-
B. Cox, The effect of some alloying additions on the oxidation of zirconium in steam, UK Report, AERE-R4458 (September 1963), UK Atomic Energy Authority, Harwell, Berks.
-
(1963)
UK Report, AERE-R4458
-
-
Cox, B.1
-
39
-
-
0023330127
-
Zirconium intermetallics and hydrogen uptake during corrosion
-
April Atomic Energy of Canada Ltd., Chalk River Nuclear Labs
-
B. Cox, Zirconium intermetallics and hydrogen uptake during corrosion, Canadian Report, AECL-9383 (April 1987), Atomic Energy of Canada Ltd., Chalk River Nuclear Labs.
-
(1987)
Canadian Report, AECL-9383
-
-
Cox, B.1
-
42
-
-
85031628488
-
-
CEA, Grenoble, France, private communication
-
F. Lefebvre, CEA, Grenoble, France, private communication.
-
-
-
Lefebvre, F.1
-
45
-
-
0344520192
-
The oxide topography on crystal-bar and reactor grade sponge zirconium
-
B. Cox, A.R. McIntosh, The oxide topography on crystal-bar and reactor grade sponge zirconium, Canadian Report, AECL-3223 (1968).
-
(1968)
Canadian Report, AECL-3223
-
-
Cox, B.1
McIntosh, A.R.2
-
47
-
-
84920631394
-
EPRI Failed fuel degradation R&D program
-
W. Palm Beach, FL
-
R.L. Yang, O. Ozer, S.K. Yagnik, B. Cheng, H.H. Klepfer, H. Kjaer-Pederson, P. Rank, EPRI Failed fuel degradation R&D program, in: Proceedings of 1994 Int. Top Meeting on Light Water Reactor Fuel Performance, W. Palm Beach, FL, 435-446.
-
In: Proceedings of 1994 Int. Top Meeting on Light Water Reactor Fuel Performance
, pp. 435-446
-
-
Yang, R.L.1
Ozer, O.2
Yagnik, S.K.3
Cheng, B.4
Klepfer, H.H.5
Kjaer-Pederson, H.6
Rank, P.7
-
48
-
-
0347665835
-
What is wrong with current models for in-reactor corrosion
-
Meeting on Fundamental Aspects of Corrosion on Zirconium Base Alloys in Water-Reactor Environments, IWGFPT/34, Portland, OR, September
-
B. Cox, What is wrong with current models for in-reactor corrosion, in: Proceedings of IAEA Technical Committee. Meeting on Fundamental Aspects of Corrosion on Zirconium Base Alloys in Water-Reactor Environments, IWGFPT/34, Portland, OR, September 1989, pp. 167-173.
-
(1989)
In: Proceedings of IAEA Technical Committee
, pp. 167-173
-
-
Cox, B.1
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