-
1
-
-
5544310313
-
Effects of hydride precipitate localization and neutron fluence on the ductility of irradiated zircaloy-4
-
Garmisch-Partenkirchen, ASTM International, West Conshohocken, PA
-
th International Symposium on Zr in the Nuclear Industry, ASTM STP 1295, Garmisch-Partenkirchen, ASTM International, West Conshohocken, PA, 1996, pp. 407-430.
-
(1996)
th International Symposium on Zr in the Nuclear Industry, ASTM STP
, vol.1295
, pp. 407-430
-
-
Garde, A.M.1
Smith, G.P.2
Pirek, R.C.3
-
2
-
-
0030252279
-
A regulatory assessment of test data for reactivity initiated accidents
-
Meyer, R. O., McCardell, R. K., Chung, H. M., Diamond, D. J., and Scott, H. H., "A Regulatory Assessment of Test Data for Reactivity Initiated Accidents," Nuclear Safety, Vol.37, 1996, pp. 872-387.
-
(1996)
Nuclear Safety
, vol.37
, pp. 872-1387
-
-
Meyer, R.O.1
McCardell, R.K.2
Chung, H.M.3
Diamond, D.J.4
Scott, H.H.5
-
3
-
-
30744451360
-
Phenomena Identification and Ranking Tables (PIRTs) for reactivity initiated accidents in pressurized water reactors containing high burnup fuel
-
Boyack, B. E., Motta, A. T., Peddicord, K. L. Alexander, C. A., Deveney, R. C., Dunn, B. M. et al., "Phenomena Identification and Ranking Tables (PIRTs) for Reactivity Initiated Accidents in Pressurized Water Reactors Containing High Burnup Fuel," Nuclear Regulatory Commission NUREC/CR-6742, 2001.
-
(2001)
Nuclear Regulatory Commission NUREC/CR-6742
-
-
Boyack, B.E.1
Motta, A.T.2
Peddicord, K.L.3
Alexander, C.A.4
Deveney, R.C.5
Dunn, B.M.6
-
5
-
-
1442311481
-
Irradiation hardening behavior of polycrystalline metals after low temperature irradiation
-
Byun, T. S. and Parrel, K., "Irradiation Hardening Behavior of Polycrystalline Metals after Low Temperature Irradiation," Journal of Nuclear Materials, Vol. 326, 2004, pp. 86-96.
-
(2004)
Journal of Nuclear Materials
, vol.326
, pp. 86-96
-
-
Byun, T.S.1
Parrel, K.2
-
6
-
-
0032098768
-
Behavior and rupture of hydridcd zircaloy-4 tubes and sheets
-
Prat, F., Grange, M. Besson, J., and Andrieu, E., "Behavior and Rupture of Hydridcd Zircaloy-4 Tubes and Sheets," Metallurgical Transactions A, Vol. 29A, 1998, pp. 1643-1651.
-
(1998)
Metallurgical Transactions A
, vol.29 A
, pp. 1643-1651
-
-
Prat, F.1
Grange, M.2
Besson, J.3
Andrieu, E.4
-
7
-
-
0037353796
-
Hydride embrittlement and irradiation effects on the hoop mechanical properties of pressurized water and boiling-water reactor zircaloy cladding tubes
-
Arsene, S., Bai, J. B., and Bombard, P., "Hydride Embrittlement and Irradiation Effects on the Hoop Mechanical Properties of Pressurized Water and Boiling-Water Reactor Zircaloy Cladding Tubes," Metallurgical and Materials Transactions A, Vol. 34A, 2003, pp. 553-588.
-
(2003)
Metallurgical and Materials Transactions A
, vol.34 A
, pp. 553-588
-
-
Arsene, S.1
Bai, J.B.2
Bombard, P.3
-
8
-
-
0033885308
-
Anisotropic behavior and rupture of hydrided zircaloy-4 sheets
-
Grange, M., Besson, J., and Andrieu, E., "Anisotropic Behavior and Rupture of Hydrided Zircaloy-4 Sheets," Metallurgical and Materials Transactions A, Vol. 31 A, 2000, pp. 679-690.
-
(2000)
Metallurgical and Materials Transactions A
, vol.31 A
, pp. 679-690
-
-
Grange, M.1
Besson, J.2
Andrieu, E.3
-
9
-
-
0030290899
-
Fracture toughness of zircaloy cladding tubes
-
Garmisch-Partenkirchen, Germany
-
th ASTM International Symposium on Zr in the Nuclear Industry, ASTM STP 1295, Garmisch-Partenkirchen, Germany, 1996, pp. 431-447.
-
(1996)
th ASTM International Symposium on Zr in the Nuclear Industry, ASTM STP
, vol.1295
, pp. 431-447
-
-
Grigoriov, V.1
Josefsson, B.2
Rosborg, B.3
-
10
-
-
0037122510
-
Analysis of the fracture behavior of hydrided cladding tube at elevated temperatures by fracture mechanics
-
Yamanaka, S., Kuroda, M., Setoyama, D., Uno, M., Takeda, K., Anada, H., et al. "Analysis of the Fracture Behavior of Hydrided Cladding Tube at Elevated Temperatures by Fracture Mechanics," Journal of Alloys and Compounds, Vols. 330-332, 2002, pp. 400-403.
-
(2002)
Journal of Alloys and Compounds
, vol.330-332
, pp. 400-403
-
-
Yamanaka, S.1
Kuroda, M.2
Setoyama, D.3
Uno, M.4
Takeda, K.5
Anada, H.6
-
11
-
-
8844246412
-
Embrittlement of hydrided zircaloy-4 under RIA-like conditions
-
Annecy, France
-
th ASTM International Symposium on Zr in the Nuclear Industry, ASTM STP 1423, Annecy, France, 2002, pp. 702-719.
-
(2002)
th ASTM International Symposium on Zr in the Nuclear Industry, ASTM STP
, vol.1423
, pp. 702-719
-
-
Daum, R.S.1
Majumdar, S.2
Tsai, H.C.3
Billone, M.C.4
Bates, D.W.5
Koss, D.A.6
-
12
-
-
0042784199
-
The influence of hydride blisters on the fracture of zircaloy-4
-
Pierron, O.N., Koss, D. A., Motta, A. T., and Chan, K. S., "The Influence of Hydride Blisters on the Fracture of Zircaloy-4," Journal of Nuclear Materials, Vol. 322, 2003, pp. 21-35.
-
(2003)
Journal of Nuclear Materials
, vol.322
, pp. 21-35
-
-
Pierron, O.N.1
Koss, D.A.2
Motta, A.T.3
Chan, K.S.4
-
13
-
-
0022043251
-
The influence of multiaxial stress states on the hydrogen embrittlement of zirconium alloy sheet
-
Yunchang, F. and Koss, D. A., "The Influence of Multiaxial Stress States on the Hydrogen Embrittlement of Zirconium Alloy Sheet," Metallurgical Transactions A, Vol. 16A, 1985, pp. 675-681.
-
(1985)
Metallurgical Transactions A
, vol.16 A
, pp. 675-681
-
-
Yunchang, F.1
Koss, D.A.2
-
14
-
-
30744447418
-
Mechanical properties of high burnup BWR fuel cladding tubes under simulated RIA conditions
-
Orlando, FL
-
Natatsuka, M., Une, K., Tokunaga, K., and Ohta, T. "Mechanical Properties of High Burnup BWR Fuel Cladding Tubes under Simulated RIA Conditions," Proc. 2004 Int. Meeting on LWR Fuel Performance, Orlando, FL, 2004, pp. 526-535.
-
(2004)
Proc. 2004 Int. Meeting on LWR Fuel Performance
, pp. 526-535
-
-
Natatsuka, M.1
Une, K.2
Tokunaga, K.3
Ohta, T.4
-
15
-
-
0000064879
-
Effect of texture, grain size, and cold work on the precipitation of oriented hydrides in zircaloy tubing and plate
-
Kearns, J. J. and Woods, C. R., "Effect of Texture, Grain Size, and Cold Work on the Precipitation of Oriented Hydrides in Zircaloy Tubing and Plate," J. Nucl. Mater., Vol. 20, 1966, pp. 241.
-
(1966)
J. Nucl. Mater.
, vol.20
, pp. 241
-
-
Kearns, J.J.1
Woods, C.R.2
-
16
-
-
5544315059
-
A unified model to describe the anisotropic viscoplastic zircaloy-4 cladding tubes
-
Garmisch-Partenkirchen
-
th International Symposium on Zr in the Nuclear Industry, ASTM STP 1295, Garmisch-Partenkirchen, 1996, pp. 373-393.
-
(1996)
th International Symposium on Zr in the Nuclear Industry, ASTM STP
, vol.1295
, pp. 373-393
-
-
Delobelle, P.1
Robinet, P.2
Bouffioux, P.3
Greyer, P.4
LePichon, I.5
-
17
-
-
0023834706
-
Deformation mechanisms, texture and anisotropy in zirconium and zirconium alloys
-
ASTM International, West Conshohocken, PA
-
Tenckhoff, E., "Deformation Mechanisms, Texture and Anisotropy in Zirconium and Zirconium Alloys," ASTM STP 966, ASTM International, West Conshohocken, PA, 1988.
-
(1988)
ASTM STP
, vol.966
-
-
Tenckhoff, E.1
-
18
-
-
0037318038
-
Tensile specimen geometry and the constitutive behavior of zircaloy 4
-
Pierron, O. N., Koss, D. A., and Motta, A. T., "Tensile Specimen Geometry and the Constitutive Behavior of Zircaloy 4," Journal of Nuclear Materials, Vol. 312, 2002, pp. 257-261.
-
(2002)
Journal of Nuclear Materials
, vol.312
, pp. 257-261
-
-
Pierron, O.N.1
Koss, D.A.2
Motta, A.T.3
-
19
-
-
0032310347
-
Failure of zircaloy cladding under transverse plane-strain deformation
-
Link, T. M., Koss D. A., and Motta, A. T. "Failure of Zircaloy Cladding under Transverse Plane-Strain Deformation," Nuclear Engineering and Design, Vol. 186, 1998; pp. 379-394.
-
(1998)
Nuclear Engineering and Design
, vol.186
, pp. 379-394
-
-
Link, T.M.1
Koss, D.A.2
Motta, A.T.3
-
21
-
-
49949135428
-
Limit strains in the process of stretch-forming sheet metal
-
Marciniak Z. and Kuczynski, K., "Limit Strains in the Process of Stretch-Forming Sheet Metal," International Journal of Mechanical Sciences, Vol. 9, 1967, pp. 609-620.
-
(1967)
International Journal of Mechanical Sciences
, vol.9
, pp. 609-620
-
-
Marciniak, Z.1
Kuczynski, K.2
-
22
-
-
0029360202
-
A simple technique to generate in-plane forming limit curves and selected applications
-
Raghavan, K. S., "A Simple Technique to Generate In-Plane Forming Limit Curves and Selected Applications," Metallurgical and Materials Transactions A, Vol. 26A, 1995, p. 2075-2084.
-
(1995)
Metallurgical and Materials Transactions A
, vol.26 A
, pp. 2075-2084
-
-
Raghavan, K.S.1
-
24
-
-
0030287689
-
The influence of temperature and yield strength on delayed hydride cracking in hydrided zircaloy 2
-
ASTM International, West Conshohocken, PA
-
th International Symposium, ASTM STP 1295, ASTM International, West Conshohocken, PA, 1996, pp. 394-404.
-
(1996)
th International Symposium, ASTM STP
, vol.1295
, pp. 394-404
-
-
Efsing, P.1
Pettersson, K.2
-
25
-
-
0031074204
-
Subcritical crack growth behavior for hydrided zircaloy-4 plate
-
Huang, J. H. and Ho, C. S., "Subcritical Crack Growth Behavior for Hydrided Zircaloy-4 Plate," Materials Chemistry and Physics, Vol. 47, 1997, pp. 184-192.
-
(1997)
Materials Chemistry and Physics
, vol.47
, pp. 184-192
-
-
Huang, J.H.1
Ho, C.S.2
-
26
-
-
0036399903
-
Mechanical property testing of irradiated zircaloy cladding under reactor transient conditions
-
ASTM International, West Conshohocken, PA
-
Daum, R. S., Majumdar, S., Tsai, H., Bray, T. S., Koss, D. A., Motta, A. T. et al., "Mechanical Property Testing of Irradiated Zircaloy Cladding Under Reactor Transient Conditions," Proc. 4th Int. Sym. on Small Specimen Test Techniques, ASTM STP 1418, ASTM International, West Conshohocken, PA, 2002, pp. 195-210.
-
(2002)
Proc. 4th Int. Sym. on Small Specimen Test Techniques, ASTM STP
, vol.1418
, pp. 195-210
-
-
Daum, R.S.1
Majumdar, S.2
Tsai, H.3
Bray, T.S.4
Koss, D.A.5
Motta, A.T.6
-
27
-
-
0344000742
-
Hydride morphology and hydrogen embrittlement of zircaloy fuel cladding used in NSRR/HBO experiment
-
Portland, OR
-
Nagase, F. and Uetsuka H., "Hydride Morphology and Hydrogen Embrittlement of Zircaloy Fuel Cladding Used in NSRR/HBO Experiment," Proceedings of the ANS International Topical Meeting on Light Water Reactor Performance, ANS, Portland, OR, 1997, p. 677.
-
(1997)
Proceedings of the ANS International Topical Meeting on Light Water Reactor Performance, ANS
, pp. 677
-
-
Nagase, F.1
Uetsuka, H.2
-
28
-
-
51249167854
-
Hydride embrittlement in zircaloy-4 plate: Part I. Influence of microstructure on the hydride embrittlement in zircaloy-4 at 20° and 350°C
-
Bai, J. B., Prioul, C., and Francois D., "Hydride Embrittlement in Zircaloy-4 Plate: Part I. Influence of Microstructure on the Hydride Embrittlement in Zircaloy-4 at 20° and 350°C," Metallurgical and Materials Transactions A, Vol. 25 A, 1994, pp. 1185-1197.
-
(1994)
Metallurgical and Materials Transactions A
, vol.25 A
, pp. 1185-1197
-
-
Bai, J.B.1
Prioul, C.2
Francois, D.3
|