-
1
-
-
0025842966
-
Microstructural development and solidification cracking susceptibility of austenitic stainless steel welds
-
J. A. Brooks, A. W. Thompson, “Microstructural development and solidification cracking susceptibility of austenitic stainless steel welds,”Int. Mater. Rev., 36[1], 16-44 (1991).
-
(1991)
Int. Mater. Rev.
, vol.36
, Issue.1
, pp. 16-44
-
-
Brooks, J.A.1
Thompson, A.W.2
-
3
-
-
0242627105
-
Sigma Phase and other effects of prolonged heating at elevated temperatures on 25 percent chromium-20 percent nickel steel
-
STP110, ASTM
-
G. N. Emanuel, “Sigma Phase and other effects of prolonged heating at elevated temperatures on 25 percent chromium-20 percent nickel steel,” Symposium on the Nature, Occurrence, and Effects of Sigma Phase, STP110, ASTM, 82-99 (1951).
-
(1951)
Symposium on the Nature, Occurrence, and Effects of Sigma Phase
, pp. 82-99
-
-
Emanuel, G.N.1
-
4
-
-
51249165539
-
Fracture and the formation of sigma phase, M23C6, and austenite from delta-ferrite in an AISI 304L stainless steel
-
6, and austenite from delta-ferrite in an AISI 304L stainless steel,”Metall. Mater. Trans. A, 25A, 1147-1158(1994).
-
(1994)
Metall. Mater. Trans. A
, vol.25A
, pp. 1147-1158
-
-
Tseng, C.C.1
Shen, Y.2
Thompson, S.W.3
-
5
-
-
0026169886
-
A phase embrittlement of a type 310 stainless steel
-
A. V Kington, F. W. Noble, “a phase embrittlement of a type 310 stainless steel,”Mater. Sci. Eng., A138, 259-266 (1991).
-
(1991)
Mater. Sci. Eng
, vol.A138
, pp. 259-266
-
-
Kington, A.V.1
Noble, F.W.2
-
6
-
-
0242542226
-
Fracture toughness and tensile properties of irradiated reactor pressure vessel cladding material
-
ASTM STP 1405, S. T. Rosinski et al. Eds., ASTM, West Conshohocken, PA
-
M. G. Hortsten, W. P A. Belcher, “Fracture toughness and tensile properties of irradiated reactor pressure vessel cladding material,” Effect of Radiation on Materials: 20th International Symposium, ASTM STP 1405, S. T. Rosinski et al. Eds., ASTM, West Conshohocken, PA. (2001).
-
(2001)
Effect of Radiation on Materials: 20Th International Symposium
-
-
Hortsten, M.G.1
Belcher, W.P.A.2
-
7
-
-
0242458713
-
Degradation of mechanical properties of stainless steel cladding due to neutron irradiation and thermal aging
-
ASTM STP 1175, A. S. Kumar et al. Eds. ASTM, Philadelphia
-
F. M. Haggag, “Degradation of mechanical properties of stainless steel cladding due to neutron irradiation and thermal aging,” Effect of Radiation on Materials: 16th International Symposium, ASTM STP 1175, A. S. Kumar et al. Eds. ASTM, Philadelphia, (1993).
-
(1993)
Effect of Radiation on Materials: 16Th International Symposium
-
-
Haggag, F.M.1
-
8
-
-
0038586739
-
Effects of irradiation on the fracture properties of stainless steel weld overlay cladding
-
F. M. Haggag, W. R. Corwin, R. K. Nanstard, “Effects of irradiation on the fracture properties of stainless steel weld overlay cladding,”Nucl. Eng. Des., 124, 129-141 (1990).
-
(1990)
Nucl. Eng. Des.
, vol.124
, pp. 129-141
-
-
Haggag, F.M.1
Corwin, W.R.2
Nanstard, R.K.3
-
9
-
-
0039550333
-
State-of-the-art review of cladding materials data
-
PVP-, ASME
-
J. K. Sharples, D. P. G. Lidbury, M. G. Horsten, et al., “State-of-the-art review of cladding materials data,” Severe Accidents and Other Topics in the RPV Design-2000, PVP-Vol. 403, ASME, 195-204 (2000).
-
(2000)
Severe Accidents and Other Topics in the RPV Design-2000
, vol.403
, pp. 195-204
-
-
Sharples, J.K.1
Lidbury, D.P.G.2
Horsten, M.G.3
-
10
-
-
0343168089
-
Evaluation of thermal aging embrittlement in CF8 duplex stainless steel by small punch test
-
J. S. Cheon, I. S. Kim, “Evaluation of thermal aging embrittlement in CF8 duplex stainless steel by small punch test,” J. Nucl. Mater., 278, 96-103 (2000).
-
(2000)
J. Nucl. Mater.
, vol.278
, pp. 96-103
-
-
Cheon, J.S.1
Kim, I.S.2
-
11
-
-
0345476704
-
Effect of isothermal treatment of SAF 2205 duplex stainless steel on migration of S/y interface boundary and growth of austenite
-
K. M. Lee, H. S. Cho, D. C. Choi, “Effect of isothermal treatment of SAF 2205 duplex stainless steel on migration of S/y interface boundary and growth of austenite,” J. Alloys Compounds, 285, 156-161 (1999).
-
(1999)
J. Alloys Compounds
, vol.285
, pp. 156-161
-
-
Lee, K.M.1
Cho, H.S.2
Choi, D.C.3
-
14
-
-
0021516735
-
Fracture behavior of a neutron-irradiated stainless steel submerged arc weld cladding overlay
-
W. R. Cowin, R. G. Berggren, R. K. Nanstad, et al., “Fracture behavior of a neutron-irradiated stainless steel submerged arc weld cladding overlay,”Nucl. Eng. Des., 89, 199-221 (1985).
-
(1985)
Nucl. Eng. Des.
, vol.89
, pp. 199-221
-
-
Cowin, W.R.1
Berggren, R.G.2
Nanstad, R.K.3
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