-
2
-
-
3643073847
-
Recent Advances in Measuring ECPs in BWR Systems
-
Jekyll Island, Georgia, August 6-10, National Association of Corrosion Engineers
-
M. E. INDIG, "Recent Advances in Measuring ECPs in BWR Systems," Proc. 4th Int. Symp. Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, Jekyll Island, Georgia, August 6-10, 1989, p. 4-411, National Association of Corrosion Engineers.
-
(1989)
Proc. 4th Int. Symp. Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors
, pp. 4-411
-
-
Indig, M.E.1
-
7
-
-
0003173094
-
-
MS Thesis, Department of Nuclear Engineering, Massachusetts Institute of Technology
-
J. CHUN, "Modeling of BWR Water Chemistry," MS Thesis, Department of Nuclear Engineering, Massachusetts Institute of Technology (1990).
-
(1990)
Modeling of BWR Water Chemistry
-
-
Chun, J.1
-
8
-
-
0029406351
-
Modeling Water Chemistry, Electrochemical Corrosion Potential, and Crack Growth Rate in the Boiling Water Reactor Heat Transport Circuits - I: The DAMAGE-PREDICTOR Algorithm
-
T.-K. YEH, D. D. MACDONALD, and A. T. MOTTA, "Modeling Water Chemistry, Electrochemical Corrosion Potential, and Crack Growth Rate in the Boiling Water Reactor Heat Transport Circuits - I: The DAMAGE-PREDICTOR Algorithm," Nucl. Sci. Eng., 121, 468 (1995).
-
(1995)
Nucl. Sci. Eng.
, vol.121
, pp. 468
-
-
Yeh, T.-K.1
Macdonald, D.D.2
Motta, A.T.3
-
9
-
-
0030172104
-
Modeling Water Chemistry, Electrochemical Corrosion Potential, and Crack Growth Rate in the Boiling Water Reactor Heat Transport Circuits - II: Simulation of Operating Reactors
-
T.-K. YEH and D. D. MACDONALD, "Modeling Water Chemistry, Electrochemical Corrosion Potential, and Crack Growth Rate in the Boiling Water Reactor Heat Transport Circuits - II: Simulation of Operating Reactors," Nucl. Sci. Eng., 123, 295 (1996).
-
(1996)
Nucl. Sci. Eng.
, vol.123
, pp. 295
-
-
Yeh, T.-K.1
Macdonald, D.D.2
-
10
-
-
3643100884
-
Cracking in the Lower Region of the Core Shroud in Boiling Water Reactors
-
U.S. Nuclear Regulatory Commission
-
"Cracking in the Lower Region of the Core Shroud in Boiling Water Reactors," NRC Information Notice 94-42, Suppl. 1, U.S. Nuclear Regulatory Commission (1994).
-
(1994)
NRC Information Notice 94-42
, Issue.1 SUPPL.
-
-
-
11
-
-
84920632404
-
Intergranular Stress Corrosion Cracking of Core Shroud in Boiling Water Reactors
-
U.S. Nuclear Regulatory Commission
-
"Intergranular Stress Corrosion Cracking of Core Shroud in Boiling Water Reactors," NRC Generic Letter 94-04, U.S. Nuclear Regulatory Commission (1994).
-
(1994)
NRC Generic Letter 94-04
-
-
-
13
-
-
0021560986
-
Stress Corrosion Cracking in BWR and PWR Piping
-
Myrtle Beach, South Carolina, August 22-25, NACE
-
R. W. WEEKS, "Stress Corrosion Cracking in BWR and PWR Piping," Proc. Int. Symp. Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, Myrtle Beach, South Carolina, August 22-25, 1983, p. 69, NACE.
-
(1983)
Proc. Int. Symp. Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors
, pp. 69
-
-
Weeks, R.W.1
-
14
-
-
0021541340
-
Recent Observations of Cracks in Large Diameter BWR Piping
-
Myrtle Beach, South Carolina, August 22-25, NACE
-
J. C. DANKO, "Recent Observations of Cracks in Large Diameter BWR Piping," Proc. Int. Symp. Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, Myrtle Beach, South Carolina, August 22-25, 1983, p. 209, NACE.
-
(1983)
Proc. Int. Symp. Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors
, pp. 209
-
-
Danko, J.C.1
-
15
-
-
0003483748
-
Corrosion-Assisted Cracking of Stainless and Low-Alloy Steels in LWR Environments
-
EPRI NP-5064M, Electric Power Research Institute Feb.
-
P. FORD et al., "Corrosion-Assisted Cracking of Stainless and Low-Alloy Steels in LWR Environments," Final Report, EPRI NP-5064M, Electric Power Research Institute (Feb. 1987).
-
(1987)
Final Report
-
-
Ford, P.1
|