-
1
-
-
33745189227
-
Recent CRDM nozzle PWSCC experience at oconee nuclear station
-
September 23-27,2002, SFEN, Paris, France
-
M.R. Robinson, D.E. Whitaker, M.L. Arey, and S. Fyfitch, "Recent CRDM Nozzle PWSCC Experience at Oconee Nuclear Station," Fontevraud 5, Proceedings of Contribution of Materials Investigation to the Resolution of Problems Encountered in Pressurized Water Reactors, September 23-27,2002, SFEN, Paris, France (2002).
-
(2002)
Fontevraud 5, Proceedings of Contribution of Materials Investigation to the Resolution of Problems Encountered in Pressurized Water Reactors
-
-
Robinson, M.R.1
Whitaker, D.E.2
Arey, M.L.3
Fyfitch, S.4
-
2
-
-
33745183990
-
Laboratory investigation of the stainless steel cladding on the davis-besse reactor vessel head
-
TMS, Salt Lake City, Utah
-
H. Xu and S. Fyfitch, and J.W. Hyres, "Laboratory Investigation of the Stainless Steel Cladding on the Davis-Besse Reactor Vessel Head," the 12th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors. TMS, Salt Lake City, Utah (2005).
-
(2005)
The 12th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors
-
-
Xu, H.1
Fyfitch, S.2
Hyres, J.W.3
-
3
-
-
33745197409
-
Boric acid corrosion of the davis-besse reactor pressure vessel head
-
TMS, Salt Lake City, Utah
-
H. Xu and S. Fyfitch, and J.W. Hyres, "Boric Acid Corrosion of the Davis-Besse Reactor Pressure Vessel Head," the 12th International Conference on Environmental Degradation of Materials in Nuclear Power Systems Water Reactors, TMS, Salt Lake City, Utah (2005).
-
(2005)
The 12th International Conference on Environmental Degradation of Materials in Nuclear Power Systems Water Reactors
-
-
Xu, H.1
Fyfitch, S.2
Hyres, J.W.3
-
4
-
-
33745221054
-
-
American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section II, Part B, SB-167, ASME, New York, NY
-
"Specification for Nickel-Chromium-Iron Alloy Seamless Pipe and Tube," American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section II, Part B, SB-167, ASME, New York, NY (1965).
-
(1965)
Specification for Nickel-Chromium-Iron Alloy Seamless Pipe and Tube
-
-
-
5
-
-
52349120418
-
Crack-tip microstructures and impurities in stress-corrosion-cracked alloy 600 from recirculating and once-through steam generator
-
NACE International, Houston, Texas
-
L.E. Thomas, V.Y. Gertsman, and S.M. Bruemmer, "Crack-Tip Microstructures and Impurities in Stress-Corrosion-Cracked Alloy 600 from Recirculating and Once-Through Steam Generator," the 10th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, NACE International, Houston, Texas (2001).
-
(2001)
The 10th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors
-
-
Thomas, L.E.1
Gertsman, V.Y.2
Bruemmer, S.M.3
-
6
-
-
4344615994
-
Standard test methods for determining average grain size
-
ASTM E 112-96, Vol. 03.01, ASTM, West Conshohocken, PA
-
ASTM E 112-96, "Standard Test Methods for Determining Average Grain Size," Vol. 03.01, Book of ASTM Standards, ASTM, West Conshohocken, PA (2000).
-
(2000)
Book of ASTM Standards
-
-
-
7
-
-
33745183429
-
Overview of primary water cracking of alloys 182/82 in PWRs
-
Fontevraud 5, September 23-27, 2002, SFEN, Paris, France
-
R.S. Pathania, A.R. McIlree, and J. Hickling, "Overview of Primary Water Cracking of Alloys 182/82 in PWRs," Fontevraud 5, Proceedings of Contribution of Materials Investigation to the Resolution of Problems Encountered in Pressurized Water Reactors, September 23-27, 2002, SFEN, Paris, France (2002).
-
(2002)
Proceedings of Contribution of Materials Investigation to the Resolution of Problems Encountered in Pressurized Water Reactors
-
-
Pathania, R.S.1
McIlree, A.R.2
Hickling, J.3
|