HSSI Publications March 1998 Ð March 2000
 
  1. T. M. Rosseel, Lockheed Martin Energy Research Corp., Oak Ridge National Laboratory, Oak Ridge, TN, Heavy-Section Steel Irradiation Program Semiannual Report for October 1996-March 1997, NUREG Report, NUREG/CR-5591, Vol. 8, No. 1, (ORNL/TM-11568/V8&N1) February 1998.
  2. P. Pereige, K. F. Russell, R. E. Stoller, M. K. Miller, Lockheed Martin Energy Research Corp., Oak Ridge National Laboratory, Influence of Long-Term Thermal Aging on the Microstructural Evolution of Nuclear Reactor Pressure Vessel Materials, NUREG Report, NUREG/CR-6537, (ORNL/TM-13406) March 1998.
  3. W. R. Corwin, Lockheed Martin Energy Research Corp., Oak Ridge National Laboratory, Oak Ridge, TN, Heavy-Section Steel Irradiation Program Semiannual Report for October 1992-March 1993, NUREG Report, NUREG/CR-5591, Vol. 4, No. 1, (ORNL/TM-11568/V4&N1) April, 1998.
  4. J. H. Giovanola, R. W. Klopp, J. E. Crocker, D. J. Alexander, W. R. Corwin, and R. K. Nanstad, "Using Small Cracked Round Bars to Measure the Fracture Toughness of a Pressure Vessel Steel Weldment: A Feasibility Study," pp. 328-352 in Small Specimen Test Techniques, ASTM STP 1329, W. R. Corwin and E. van Walle, Eds., American Society for Testing and Materials, 1998.
  5. M. A. Sokolov, D. E. McCabe, Y. A. Davidov, and R. K. Nanstad, "Use of Precracked Charpy and Smaller Specimens to Establish the Master Curve," pp. 238-252 in Small Specimen Test Techniques, ASTM STP 1329, W. R. Corwin and E. van Walle, Eds., American Society for Testing and Materials, 1998.
  6. K. Onizawa, E. van Walle, R. K. Nanstad, M. A. Sokolov, and W. A. Pavinich, "Critical Analysis of Results from the ASTM Round-Robin on Reconstitution," pp. 383-410 in Small Specimen Test Techniques, ASTM STP 1329, W. R. Corwin and E. van Walle, Eds., American Society for Testing and Materials, 1998.
  7. I. Remec, C. A. Baldwin, and K. B. K. Kam, Lockheed Martin Energy Research Corporation, Oak Ridge Natl. Lab., Oak Ridge, Tenn., Neutron Exposure Parameters for Capsule 10.05 in the Heavy-Section Steel Irradiation Program Tenth Irradiation Series, USNRC Report NUREG/CR-6600 (ORNL/TM-13548), October 1998.
  8. I. Remec, C. A. Baldwin, and F. B. K. Kam, Lockheed Martin Energy Research Corporation, Oak Ridge Natl. Lab., Oak Ridge, Tenn., Neutron Exposure Parameters for the Dosimetry Capsule in the Heavy-Section Steel Irradiation Program Tenth Irradiation Series, USNRC Report NUREG/CR-6601 (ORNL/TM-13549), October 1998.
  9. S. K. Iskander, P. P. Milella, A. Pini, and E. T. Manneschmidt, "Crack-Arrest Testing of Irradiated Nuclear Reactor Pressure Vessel Steels," Journal of Testing and Evaluation, 26(6), 546-554 (November 1998).
  10. R. E. Stoller, "The Impact of Mobile Point Defect Clusters in a Kinetic Model of Pressure Vessel Embrittlement," Effect of Radiation on Materials: 18th International Symposium, ASTM 1325, R. K. Nanstad, M. L. Hamilton, F. A. Garner, and A. S. Kumar, American Society for Testing and Materials, 1999, pp. 14-29.
  11. R. K. Nanstad, D. E. McCabe, and R. L. Swain, "Evaluation of Variability in Material Properties and Chemical Composition for Midland Reactor Weld WF-70," Effect of Radiation on Materials: 18th International Symposium, ASTM 1325, R. K. Nanstad, M. L. Hamilton, F. A. Garner, and A. S. Kumar, American Society for Testing and Materials, 1999, pp. 125-156.
  12. M. A. Sokolov and R. K. Nanstad, "Comparison of Irradiation-Induced Shifts of KJC and Charpy Impact Toughness for Reactor Pressure Vessel Steels," Effect of Radiation on Materials: 18th International Symposium, ASTM 1325, R. K. Nanstad, M. L. Hamilton, F. A. Garner, and A. S. Kumar, American Society for Testing and Materials, 1999, pp. 167-190.
  13. S. K. Iskander, R. K. Nanstad, M. A. Sokolov, D. E. McCabe, J. T. Hutton, and D. L. Thomas, "Use of Forces From Instrumented Charpy V-Notch Testing of Determine Crack-Arrest Toughness," Effect of Radiation on Materials: 18th International Symposium, ASTM 1325, R. K. Nanstad, M. L. Hamilton, F. A. Garner, and A. S. Kumar, American Society for Testing and Materials, 1999, pp. 204-222.
  14. M. A. Sokolov, S. Spooner, G. R. Odette, B. D. Wirth, and G. E. Lucas, "Sans Study of High-Copper RPV Welds in Irradiated and Annealed Conditions," Effect of Radiation on Materials: 18th International Symposium, ASTM 1325, R. K. Nanstad, M. L. Hamilton, F. A. Garner, and A. S. Kumar, American Society for Testing and Materials, 1999, pp. 333-345.
  15. S. K. Iskander, M. A. Sokolov, and R. K. Nanstad, "Comparison of Different Experimental and Analytical Measures of the Thermal Annealing Response of Neutron-Irradiated RPV Steels," Effect of Radiation on Materials: 18th International Symposium, ASTM 1325, R. K. Nanstad, M. L. Hamilton, F. A. Garner, and A. S. Kumar, American Society for Testing and Materials, 1999, pp. 403-420.
  16. R. K. Nanstad, M. L. Hamilton, F. A. Garner, and A. S. Kumar, Eds., Effects of Radiation on Materials, 18th International Symposium, ASTM STP 1325, American Society for Testing and Materials, West Conshohocken, Pennsylvania, 1999.
  17. D. E. McCabe, "Initial Evaluation of the Heat-Affected Zone, Local Embrittlement Phenomenon as it Applies to Nuclear Reactor Vessels," ORNL/NRC/LTR-99/10 (September 1999).
  18. D. W. Heatherly, K. R. Thoms, I. I. Siman-Tov, and M. T. Hurst, "Design, Fabrication, and Initial Operation of a Reusable Irradiation Facility," ORNL/NRC/LTR-99/16.
  19. D. E. McCabe, "Initial Evaluation of the Heat-Affected Zone, Local Embrittlement Phenomenon as it Applies to Nuclear Reactor Vessels," ORNL/NRC/LTR-99/10, September 1999.
  20. S. K. Iskander, J. T. Hutton, L. E. Creech, R. K. Nanstad, E. T. Manneschmidt, T. M. Rosseel, and P. S. Bishop, Lockheed Martin Energy Research, Inc., Oak Ridge Natl. Lab., Oak Ridge, TN., "Interim Results of Toughness Tests on Irradiated Materials Removed from the Decommissioned Japan Power Development Reactor JPDR," ORNL/NRC/LTR-99-23.
  21. M. K. Miller, P. Pareige, and M. G. Burke, "Understanding Pressure Vessel Steels: An Atom Probe Perspective," Matls. Charac., 44, 223 (2000).
  22. J. R. Hawthorne, M. A. Solkolov, and W. L. Server, "Exploratory Test of 288¼C Radiation Resistance of Two USSR-Produced Reactor Pressure Vessel Steels," Effects of Radiation on Materials: 19th International Symposium, ASTM STP 1366, M. L. Hamilton, A. S. Kumar, S. T. Rosinski, M. L. Grossbeck, 2000, pp.16-32.
  23. J. A. Wang, "Analysis of Irradiation Data for A302B and A533B Correlation Monitor Materials," Effects of Radiation on Materials: 19th International Symposium, ASTM STP 1366, M. L. Hamilton, A. S. Kumar, S. T. Rosinski, M. L. Grossbeck, 2000, pp. 33-55.
  24. S. K. Iskander, R. K. Nanstad, D. E. McCabe, and R. L. Swain, "Effects of Irradiation on Crack-Arrest Toughness of a Low Upper-Shelf Energy, High-Copper Weld," Effects of Radiation on Materials: 19th International Symposium, ASTM STP 1366, M. L. Hamilton, A. S. Kumar, S. T. Rosinski, M. L. Grossbeck, 2000, pp. 245-265.
  25. D. E. McCabe, R. K. Nanstad, and M. A. Sokolov, "Efects of Irradiation and Thermal Annealing on Fracture Toughness of the Midland Reactor Weld WF-70," Effects of Radiation on Materials: 19th International Symposium, ASTM STP 1366, M. L. Hamilton, A. S. Kumar, S. T. Rosinski, M. L. Grossbeck, 2000, pp. 306-322.
  26. M. A. Sokolov, A. A. Chernobaeva, R. K. Nanstad, Y. A. Nikolaev, and Y. N. Korolev, "Irradiation, Annealing, and Reirradiation Effects on American and Russian Reactor Pressure Vessel Steels," Effects of Radiation on Materials: 19th International Symposium, ASTM STP 1366, M. L. Hamilton, A. S. Kumar, S. T. Rosinski, M. L. Grossbeck, 2000, pp.415-434.
  27. R. E. Stoller and L. R. Greenwood, "an Evaluation of Neutron Energy Spectrum Effects in Iron Based on Molecular Dynamics Displacement Cascade Simulations," Effects of Radiation on Materials: 19th International Symposium, ASTM STP 1366, M. L. Hamilton, A. S. Kumar, S. T. Rosinski, M. L. Grossbeck, 2000, pp. 548-559.
 
HSSI NUREG Reports (submitted for publication)
  1. T. M. Rosseel., Lockheed Martin Energy Research, Inc., Oak Ridge Natl. Lab., Oak Ridge, TN., HSSI (L1098) Semiannual Progress Report, V8 N2, NUREG/CR-5591, submitted to the NRC, July 1998.
  2. J. Giovanola and J. E. Crocker, SRI, International, Fracture Toughness Testing with Cracked Round Bars: Feasibility Study, NUREG/CR-6342 (ORNL/SUB/94-DHK60), submitted to the NRC, September 1998.
  3. D. E. McCabe, R. K. Nanstad, S. K. Iskander, D. W. Heatherly, and R. L. Swain, Evaluation of WF-70 Weld Metal from the Midland Unit 1 Reactor Vessel - Final Report, NUREG/CR-5736 (ORNL/TM-13748), submitted to the NRC for publication, February 1999.
  4. M. A. Sokolov and R. K. Nanstad, Comparison of Irradiation-Induced Shifts of KJc and Charpy Impact Toughness for Reactor Pressure Vessel Steels, NUREG/CR-6609 (ORNL/TM-13755), submitted to the NRC for publication, May 1999.
  5. D. J. Alexander, K. B. Alexander, M. K. Miller and R. K. Nanstad, The Effect of Aging at 343 C on the Microstructure and Mechanical Properties of Type 308 Stainless Steel Weldments, NUREG/CR-6628 (ORNL/TM-13767), submitted to the NRC for publication, July 1999
  6. M. K. Miller, P. Pareige, K. F. Russell, and R. E. Stoller, Atom Probe Tomography Characterization of the Solute Distributions in a Neutron-Irradiated and Annealed Pressure Vessel Steel Weld," NUREG/CR-6629, ORNL/TM-13768, submitted to the NRC for publication, September 1999.
  7. I. Remec, E. D. Blakeman, and C. A. Baldwin, Characterization of the Neutron Field in the HSSI/ UCSB Irradiation Facility at the Ford Nuclear Reactor, NUREG/CR-6646, ORNL/TM-1999/140, submitted to the NRC for publication, September 1999.
 
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