-
1
-
-
40849143392
-
A first report on deformation mechanism maps
-
Ashby, M.F., 1972. A first report on deformation mechanism maps. Acta Met. 20, 887-894; Frost, H.J., Ashby, M.F., 1982. Deformation Mechanism Maps. Pergamon Press, Oxford.
-
(1972)
Acta Met.
, vol.20
, pp. 887-894
-
-
Ashby, M.F.1
-
2
-
-
40849143392
-
-
Pergamon Press, Oxford
-
Ashby, M.F., 1972. A first report on deformation mechanism maps. Acta Met. 20, 887-894; Frost, H.J., Ashby, M.F., 1982. Deformation Mechanism Maps. Pergamon Press, Oxford.
-
(1982)
Deformation Mechanism Maps
-
-
Frost, H.J.1
Ashby, M.F.2
-
3
-
-
85168710739
-
In-reactor deformation of Zr-2.5 wt.% Nb pressure tubes
-
Influence of Radiation on Material Properties: Proceedings of the 13th International Symposium (Part II)
-
Causey, A.R., Fidleris, V., MacEwen, S.R., Schulte, C.W., 1987. In-reactor deformation of Zr-2.5 wt.% Nb pressure tubes. In: Influence of Radiation on Material Properties: Proceedings of the 13th International Symposium (Part II). ASTM STP 956, pp. 54-68.
-
(1987)
ASTM STP
, vol.956
, pp. 54-68
-
-
Causey, A.R.1
Fidleris, V.2
Macewen, S.R.3
Schulte, C.W.4
-
4
-
-
0024640221
-
Prediction of maximum allowable temperature for dry storage of Zircaloy-clad spent fuel in inert atmosphere
-
Chin B.A., Gilbert E.R. Prediction of maximum allowable temperature for dry storage of Zircaloy-clad spent fuel in inert atmosphere. Nucl. Tech. 85:1989;57-65.
-
(1989)
Nucl. Tech.
, vol.85
, pp. 57-65
-
-
Chin, B.A.1
Gilbert, E.R.2
-
5
-
-
0024087716
-
The irradiation creep and growth phenomena
-
Fidleris V. The irradiation creep and growth phenomena. J. Nucl. Mater. 159:1988;22-42.
-
(1988)
J. Nucl. Mater.
, vol.159
, pp. 22-42
-
-
Fidleris, V.1
-
6
-
-
0018466133
-
Creep damage in Zircaloy-4 at LWR temperatures
-
Keusseyan R.L., Hu C.P., Li C.Y. Creep damage in Zircaloy-4 at LWR temperatures. J. Nucl. Mater. 80:1979;390-392.
-
(1979)
J. Nucl. Mater.
, vol.80
, pp. 390-392
-
-
Keusseyan, R.L.1
Hu, C.P.2
Li, C.Y.3
-
7
-
-
0016498226
-
Deformation mechanism mapping of α-Zr and Zirclaloy-2
-
Knorr D.B., Notis M.R. Deformation mechanism mapping of α-Zr and Zirclaloy-2. J. Nucl. Mater. 56:1975;18-23.
-
(1975)
J. Nucl. Mater.
, vol.56
, pp. 18-23
-
-
Knorr, D.B.1
Notis, M.R.2
-
8
-
-
5544252605
-
A model for analysis of the effect of final annealing on the in- and out-reactor creep behavior of Zircaloy cladding
-
Zirconium in the Nuclear Industry: Proceedings of the Eleventh International Symposium
-
Limback, M., Andersson, T., 1996. A model for analysis of the effect of final annealing on the in- and out-reactor creep behavior of Zircaloy cladding. In: Zirconium in the Nuclear Industry: Proceedings of the Eleventh International Symposium. ASTM STP 1295, pp. 448-468.
-
(1996)
ASTM STP
, vol.1295
, pp. 448-468
-
-
Limback, M.1
Andersson, T.2
-
10
-
-
0025429818
-
Creep deformation of an unirradiated Zircaloy-4 nuclear fuel cladding tube under dry storage conditions
-
Mayuzumi M., Onchi T. Creep deformation of an unirradiated Zircaloy-4 nuclear fuel cladding tube under dry storage conditions. J. Nucl. Mater. 171:1990;381-388.
-
(1990)
J. Nucl. Mater.
, vol.171
, pp. 381-388
-
-
Mayuzumi, M.1
Onchi, T.2
-
11
-
-
0026128940
-
A method to evaluate the maximum allowable temperature of spent fuel in dry storage during a postulated accident
-
Mayuzumi M., Onchi T. A method to evaluate the maximum allowable temperature of spent fuel in dry storage during a postulated accident. Nucl. Tech. 93:1991;382-388.
-
(1991)
Nucl. Tech.
, vol.93
, pp. 382-388
-
-
Mayuzumi, M.1
Onchi, T.2
-
12
-
-
0015661928
-
Transitional creep mechanisms in Al-5Mg at high stresses
-
Murty K.L. Transitional creep mechanisms in Al-5Mg at high stresses. Scripta Met. 7:1973;899-902.
-
(1973)
Scripta Met.
, vol.7
, pp. 899-902
-
-
Murty, K.L.1
-
13
-
-
0010709636
-
Biaxial creep of Zircaloy cladding
-
Murty K.L. Biaxial creep of Zircaloy cladding. Trans. IIM. 39:1986;357-368.
-
(1986)
Trans. IIM
, vol.39
, pp. 357-368
-
-
Murty, K.L.1
-
14
-
-
0001655045
-
Dislocation jump distances during creep of pure and doped NaCl single crystals using nuclear magnetic resonance pulse techniques
-
Murty K.L., Kanert O. Dislocation jump distances during creep of pure and doped NaCl single crystals using nuclear magnetic resonance pulse techniques. J. Appl. Phys. 67:1990;2866-2872.
-
(1990)
J. Appl. Phys.
, vol.67
, pp. 2866-2872
-
-
Murty, K.L.1
Kanert, O.2
-
16
-
-
0002233595
-
Stress corrosion cracking and pellet cladding mechanical interaction of Zircaloys - Application to LWRs
-
Khanna, A.S., Sharma, K.S., Sinha, A.K. (Eds.). Academic Books International, New Delhi
-
Murty, K.L., 1999. Stress corrosion cracking and pellet cladding mechanical interaction of Zircaloys - application to LWRs. In: Khanna, A.S., Sharma, K.S., Sinha, A.K. (Eds.), Emerging Trends in Corrosion Control - Evaluation, Monitoring and Solutions. Academic Books International, New Delhi, pp. 702-710.
-
(1999)
Emerging Trends in Corrosion Control - Evaluation, Monitoring and Solutions
, pp. 702-710
-
-
Murty, K.L.1
-
17
-
-
0442320687
-
Internal pressurization creep of thin-walled tubing of Zr-alloys for dry storage feasibility of nuclear spent fuel
-
Murty, K.L., 2000. Internal pressurization creep of thin-walled tubing of Zr-alloys for dry storage feasibility of nuclear spent fuel. J. Metals, pp. 34-38.
-
(2000)
J. Metals
, pp. 34-38
-
-
Murty, K.L.1
-
18
-
-
0442305054
-
Thermal creep of Zircaloy-4 cladding
-
Paper C3/4
-
Murty, K.L., Clevinger, G.S., Papazoglou, T.P., 1977. Thermal creep of Zircaloy-4 cladding. In: Proceedings of the 4th International Conference on Structural Mechanics in Reactor Technology, Paper C3/4.
-
(1977)
Proceedings of the 4th International Conference on Structural Mechanics in Reactor Technology
-
-
Murty, K.L.1
Clevinger, G.S.2
Papazoglou, T.P.3
-
19
-
-
0010662549
-
Effect of stress-ratio on biaxial creep and dislocation microstructures in recrystallized Ti3Al2.5V tubing
-
Talef, E.M., Syn, C.K., Lesuer, D.R. (Eds.), TMS
-
Murty, K.L., Paradkar, A., Nangalia, S., 2000. Effect of stress-ratio on biaxial creep and dislocation microstructures in recrystallized Ti3Al2.5V tubing. In: Talef, E.M., Syn, C.K., Lesuer, D.R. (Eds.), Proceedings of TMS Symposium, Deformation, Processing and Properties of Structural Materials, TMS, pp. 169-179.
-
(2000)
Proceedings of TMS Symposium, Deformation, Processing and Properties of Structural Materials
, pp. 169-179
-
-
Murty, K.L.1
Paradkar, A.2
Nangalia, S.3
-
20
-
-
0029632958
-
Transitions in creep mechanisms and creep anisotropy in a Zr-1Nb-1Sn-0.2Fe sheet
-
Murty, K.L., Ravi, J., Wiratmo, 1995. Transitions in creep mechanisms and creep anisotropy in a Zr-1Nb-1Sn-0.2Fe sheet. Nucl. Eng. Design, 156, pp. 359-371.
-
(1995)
Nucl. Eng. Design
, vol.156
, pp. 359-371
-
-
Murty, K.L.1
Ravi, J.2
Wiratmo3
-
21
-
-
0022660297
-
LWR spent fuel storage behavior
-
Peehs M., Fleisch J. LWR spent fuel storage behavior. J. Nucl. Mater. 137:1986;190-202.
-
(1986)
J. Nucl. Mater.
, vol.137
, pp. 190-202
-
-
Peehs, M.1
Fleisch, J.2
-
22
-
-
0010709639
-
Experimentally based spent fuel dry storage performance criteria
-
US DOE-CONF-86041/UC-85
-
Peehs, M., Kaspar, G., Steinberg, E., 1986. Experimentally based spent fuel dry storage performance criteria. In: Proceedings of the Third International Spent Fuel Storage Techniques Symposium and Workshop, vol. 1. S-316-S-331, US DOE-CONF-86041/UC-85, pp. S-316-331.
-
(1986)
Proceedings of the Third International Spent Fuel Storage Techniques Symposium and Workshop
, vol.1
-
-
Peehs, M.1
Kaspar, G.2
Steinberg, E.3
-
23
-
-
0010704004
-
Temperature limit determination for the inert dry storage of spent nuclear fuel
-
Pescatore, C., Cowgill, M.G., 1994. Temperature limit determination for the inert dry storage of spent nuclear fuel. EPRI Report TR-103949.
-
(1994)
EPRI Report
, vol.TR-103949
-
-
Pescatore, C.1
Cowgill, M.G.2
-
25
-
-
0016521350
-
Intergranular fracture at elevated temperature
-
Raj R., Ashby M.F. Intergranular fracture at elevated temperature. Acta Met. 23:1975;653-667.
-
(1975)
Acta Met.
, vol.23
, pp. 653-667
-
-
Raj, R.1
Ashby, M.F.2
-
26
-
-
0028446989
-
Effects of recrystallization and Nb-additions on texture and mechanical anisotropy of Zircaloy
-
Ravi J., Mahmood S.T., Murty K.L. Effects of recrystallization and Nb-additions on texture and mechanical anisotropy of Zircaloy. Nucl. Eng. Design. 148:1994;1-15.
-
(1994)
Nucl. Eng. Design
, vol.148
, pp. 1-15
-
-
Ravi, J.1
Mahmood, S.T.2
Murty, K.L.3
-
28
-
-
0018004908
-
Creep properties of Zr-1 wt.%Nb alloy
-
Thorpe W.R., Smith I.O. Creep properties of Zr-1 wt.%Nb alloy. J. Nucl. Mater. 75:1978;209-219.
-
(1978)
J. Nucl. Mater.
, vol.75
, pp. 209-219
-
-
Thorpe, W.R.1
Smith, I.O.2
-
30
-
-
0346243755
-
Effect of temperature on mechanical anisotropy of recrystallized Zircaloy-4 Sheet
-
Wang Y., Mathew M.D., Murty K.L. Effect of temperature on mechanical anisotropy of recrystallized Zircaloy-4 Sheet. Metals Mater. 4(4):1998;723-726.
-
(1998)
Metals Mater.
, vol.4
, Issue.4
, pp. 723-726
-
-
Wang, Y.1
Mathew, M.D.2
Murty, K.L.3
-
31
-
-
36849138280
-
Steady state creep of crystals
-
Weertman J. Steady state creep of crystals. J. Appl. Phys. 28:1957;1185-1189.
-
(1957)
J. Appl. Phys.
, vol.28
, pp. 1185-1189
-
-
Weertman, J.1
-
32
-
-
0343253714
-
On the question of void formation in neutron irradiated zirconium
-
Wolfenden A., Farrel K. On the question of void formation in neutron irradiated zirconium. Scripta Met. 6:1972;127-129.
-
(1972)
Scripta Met.
, vol.6
, pp. 127-129
-
-
Wolfenden, A.1
Farrel, K.2
-
33
-
-
0342863683
-
Suppression of void formation in zirconium
-
Zirconium in Nuclear Applications
-
Yoo, M.H., 1994. Suppression of void formation in zirconium. In: Zirconium in Nuclear Applications. ASTM STP 551, pp. 292-307.
-
(1994)
ASTM STP
, vol.551
, pp. 292-307
-
-
Yoo, M.H.1
|