-
1
-
-
0026404039
-
Fracture mechanics data and modeling of environmental cracking of nickel-base alloys in high temperature water
-
Paper No. 44, March 11-15, 1991, NACE
-
Andresen, P.L. 1991, "Fracture Mechanics Data and Modeling of Environmental Cracking of Nickel-Base Alloys in High Temperature Water," Paper No. 44, Corrosion 91, March 11-15, 1991, NACE.
-
(1991)
Corrosion 91
-
-
Andresen, P.L.1
-
2
-
-
84885268013
-
Mechanisms and kinetics of SCC in stainless steels
-
Houston, Texas: NACE International
-
Andresen, P.L., Angeliu, T.M., Young, L.M., Catlin, W.R., and Horn, R.M. 2002a, "Mechanisms and Kinetics of SCC in Stainless Steels," Tenth International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, August 5 to 9, 2001, Lake Tahoe, Nevada. Houston, Texas: NACE International.
-
(2002)
Tenth International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, August 5 to 9, 2001, Lake Tahoe, Nevada
-
-
Andresen, P.L.1
Angeliu, T.M.2
Young, L.M.3
Catlin, W.R.4
Horn, R.M.5
-
3
-
-
0242674808
-
Stress corrosion cracking growth rate behavior of alloy 22 (UNS N06022) in concentrated groudwater
-
The annual conference and corrosion show sponsored by NACE International. Paper No. 03683
-
Andresen, P.L., Emigh, P.W., Young, L.M., and Gordon, G.M. 2003, "Stress Corrosion Cracking Growth Rate Behavior of Alloy 22 (UNS N06022) in Concentrated Groudwater," Corrosion 2003. The annual conference and corrosion show sponsored by NACE International. Paper No. 03683.
-
(2003)
Corrosion 2003
-
-
Andresen, P.L.1
Emigh, P.W.2
Young, L.M.3
Gordon, G.M.4
-
4
-
-
0024054216
-
Life prediction by mechanistic modeling and system monitoring of environmental cracking of iron and nickel alloys in aqueous systems
-
Andresen, P.L. and Ford, F.L. 1988, "Life Prediction by Mechanistic Modeling and System Monitoring of Environmental Cracking of Iron and Nickel Alloys in Aqueous Systems," Materials Science and Engineering, A103, pp. 167-184.
-
(1988)
Materials Science and Engineering
, vol.A103
, pp. 167-184
-
-
Andresen, P.L.1
Ford, F.L.2
-
5
-
-
85039430833
-
Stress corrosion crack growth rate behavior of Ni alloys 182 and 600 in high temperature water
-
Paper No. 02510, NACE, March 2002
-
Andresen, P.L., Young, L.M., Emigh, P.W., and Horn, R.M. 2002b, "Stress Corrosion Crack Growth Rate Behavior of Ni alloys 182 and 600 in High Temperature Water," Paper No. 02510, Corrosion 2002, NACE, March 2002.
-
(2002)
Corrosion 2002
-
-
Andresen, P.L.1
Young, L.M.2
Emigh, P.W.3
Horn, R.M.4
-
9
-
-
0242674805
-
-
BBA000000-01717-2500-00006 REV 00. Civilian Radioactive Waste Management System (CRWMS) Management and Operation Contractor (M&O), Las Vegas, Nevada
-
CRWMS M&O 1996, Waste Package Closure Weld Development Report. BBA000000-01717-2500-00006 REV 00. Civilian Radioactive Waste Management System (CRWMS) Management and Operation Contractor (M&O), Las Vegas, Nevada.
-
(1996)
Waste Package Closure Weld Development Report
-
-
-
10
-
-
0003854673
-
-
DOE/RW-0539. Washington, D.C.: U.S. Department of Energy, Office of Civilian Radioactive Waste Management May 2001
-
DOE (U.S. Department of Energy) 2001, Yucca Mountain Science and Engineering Report. DOE/RW-0539. Washington, D.C.: U.S. Department of Energy, Office of Civilian Radioactive Waste Management May 2001.
-
(2001)
Yucca Mountain Science and Engineering Report
-
-
-
11
-
-
0002139532
-
Development and use of a predictive model of crack propagation in 304/316L, A533B/A508 and inconel 600/182 alloys in 288°C water
-
Theus, G.J. and Weeks, J.R., eds
-
Ford, F.P. and Andresen, P.L. 1988, "Development and Use of a Predictive Model of Crack Propagation in 304/316L, A533B/A508 and Inconel 600/182 Alloys in 288°C Water," Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, [Proceeding of the Third International Symposium, Traverse City, Michigan, August 30- September 3, 1987]. Theus, G.J. and Weeks, J.R., eds. Pages 798-800.
-
(1988)
Environmental Degradation of Materials in Nuclear Power Systems-water Reactors, [Proceeding of the Third International Symposium, Traverse City, Michigan, August 30-September 3, 1987]
, pp. 798-800
-
-
Ford, F.P.1
Andresen, P.L.2
-
13
-
-
0242694895
-
Modeling of stress corrosion cracking for high level radioactive-waste packages
-
PVP. The American Society of Mechanical Engineering. New York, NY
-
Lu, S.C., Gordon, G.M., Andresen, P.L., and Herrera, M.L. 2003, "Modeling of Stress Corrosion Cracking for High Level Radioactive-Waste Packages." Transportation, Storage, and Disposal of Radioactive Materials - 2003. PVP-Vol. 467. The American Society of Mechanical Engineering. New York, NY. pp. 119-127.
-
(2003)
Transportation, Storage, and Disposal of Radioactive Materials - 2003
, vol.467
, pp. 119-127
-
-
Lu, S.C.1
Gordon, G.M.2
Andresen, P.L.3
Herrera, M.L.4
-
14
-
-
7744238160
-
-
CNWRA 2003-01. San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses
-
Pensado, O., Dunn, D.S., Cragnolino. G.A,. and Jain, V. 2002, Passive Dissolution of Container Materials-Modeling and Experiments. CNWRA 2003-01. San Antonio, Texas: Center for Nuclear Waste Regulatory Analyses.
-
(2002)
Passive Dissolution of Container Materials-modeling and Experiments
-
-
Pensado, O.1
Dunn, D.S.2
Cragnolino, G.A.3
Jain, V.4
-
15
-
-
14344251002
-
Constant load SCC of proposed waste package materials in mixed salt solutions
-
Eleventh International Conference on Environmental Degradation of Materials in Nuclear Power Systems -Water Reactors, August 10-14, 2003, Stevenson, WA
-
Young, L.M., Catlin, G.M., Andresen, P.L., and Gordon, G.M. 2003, "Constant Load SCC of Proposed Waste Package Materials in Mixed Salt Solutions," Eleventh International Conference on Environmental Degradation of Materials in Nuclear Power Systems -Water Reactors, August 10-14, 2003, Stevenson, WA., American Nuclear Society Conference Proceedings, pp. 267-279.
-
(2003)
American Nuclear Society Conference Proceedings
, pp. 267-279
-
-
Young, L.M.1
Catlin, G.M.2
Andresen, P.L.3
Gordon, G.M.4
|