An Evaluation of Through-Thickness Changes in Primary Damage Production in Commercial Reactor Pressure Vessels

ASTM Special Technical Publication

Volumn STP 1405, Issue , 2001, Pages 204-217

  Stoller, Roger E ^a   Greenwood, Lawrence R ^b  

^a OAK RIDGE NATIONAL LABORATORY   (United States)

^b PACIFIC NORTHWEST NATIONAL LABORATORY   (United States)

Author keywords

damage attenuation; displacement cascades; ferritic steels; modeling; molecular dynamics; point defects; pressure vessels; radiation damage

Indexed keywords

IRON; MOLECULAR DYNAMICS; NEUTRON IRRADIATION; POINT DEFECTS; PRESSURE VESSELS; SIZE DISTRIBUTION;

COMMERCIAL REACTOR; DAMAGE ATTENUATION; DAMAGE PARAMETER; DISPLACEMENT CASCADES; ENERGY; ENERGY DEPENDENCE; MODELING; POINT DEFECT CLUSTERS; REACTOR PRESSURE VESSEL; THROUGH-THICKNESS;

RADIATION DAMAGE;

EID: 85030747125     PISSN: 00660558     EISSN: None     Source Type: Conference Proceeding    
DOI: 10.1520/STP10534S     Document Type: Conference Paper

References (28)

1. "Radiation Embrittlement of Reactor Vessel Materials, " Regulatory Guide 1.99, Revision 2, U.S. Nuclear Regulatory Commission, May 1988, available from the U.S. National Technical Information Service, Springfield, VA.
2. Randall, P. N., "Basis for Revision 2 of the U.S. Nuclear Regulatory Commission's Regulatory Guide 1.99, " Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels: An International Review, STP 909, L.E. Steele, Ed., American Society for Testing and Materials, West Conshohocken, PA, 1986, pp. 149-162.
3. Eason, E. D., Wright, J. E., and Odette, G. R., "Improved Embrittlement Correlations for Reactor Pressure Vessel Steels, " NUREG/CR-6551, MCS 970501, U.S. Nuclear Regulatory Commission, November 1998, available from the U.S. National Technical Information Service, Springfield, VA.
4. Recommendations of IAEA Specialists Meeting on Radiation Damage Units in Graphite and Ferritic and Austenitic Steels, Nuclear Engineering andDesign, 1975, 33, p. 48.
5. Stoller, R. E. and Odette, G. R., "Recommendations on Damage Exposure Units for Ferritic Steel Embrittlement, " Journal of Nuclear Materials 1992, 186, pp. 203-205.
6. Stoller, R. E. and Calder, A. F., "Statistical Analysis of a Library of Molecular Dynamics Cascade Simulations in Iron at 100K, "Journal of Nuclear Materials 2000, 283-287, 186, pp. 203-205.
7. Phythian, W. J., Stoller, R.E., Foreman, A. J. E., Calder, A. F., and Bacon, D. J., "A Comparison of Displacement Cascades in Copper and Iron by Molecular Dynamics and Its Application to Microstructural Evolution, " Journal of Nuclear Materials 1995, 223, pp. 245-261.
8. Stoller, R.E., "Point Defect Survival and Clustering Fractions Obtained From Molecular Dynamics Simulations of High Energy Cascades, " Journal of Nuclear Materials 1996, 233-237, pp. 999-1003.
9. Stoller, R.E., Odette G.R., and Wirth, B. D., "Primary Damage Formation in bcc Iron, " Journal of Nuclear Materials 1997, 251, pp. 49-69.
10. Stoller, R.E., "The Role of Cascade Energy and Temperature in Primary Defect Formation in Iron, " Journal of Nuclear Materials 2000, 276, pp. 22-32.
11. Albert J.E., Gritzner, M.L., Simmons, G.L., and Straker, E.A., "PWR and BWR Radiation Environments for Radiation Damage Studies, "EPRINP-152, Electric Power Research Institute, Palo Alto, CA, September 1977.
12. Stoller, R.E. and Greenwood, L.R., "An Evaluation of Neutron Energy Spectrum Effects Based on Molecular Dynamics Displacement Cascade Simulations, " Effects of Radiation on Materials, STP 1366, M. L. Hamilton, A. S. Kumar, S. T. Rosinski, and M. L. Grossbeck, Eds., American Society for Testing and Materials, West Conshohocken, PA, 2000, pp. 548-559.
13. Greenwood, L.R. and Smither, R.K., "SPECTER: Neutron Damage Calculations for Materials Irradiations, " ANL/FPP/TM-197, Argonne National Laboratory, Argonne, IL, January 1985.
14. Finnis, M.W., "MOLDY6-A Molecular Dynamics Program for Simulation of Pure Metals, " AERE R-13182, UKAEA Harwell Laboratory, Harwell, UK, 1988.
15. Finnis, M.W. and Sinclair, J.E., "A Simple Empirical N-body Potential for Transition Metals, " PhilosophicalMagazine-A 1984, 50, pp. 45-55
16. and Erratum, Philosophical Magazine-A, 1986, p. 161.
17. Calder, A.F. and Bacon, D.J., "A Molecular Dynamics Study of Displacement Cascades in a-iron, " Journal of Nuclear Materials 1993, 207, pp. 25-45.
18. Norgett, M.J., Robinson, M.T., and Torrens, I.M., "A Proposed Method of Calculating Displacement Dose Rates, " Nuclear Engineering and Design 1975, 33, pp. 50-54.
19. Stoller, R.E. and Greenwood, L.R., "A Comparison of the NRT Displacement Model and Primary Damage Formation Observed in Molecular Dynamics Cascade Simulations, " presented at the 10th International Symposium on Reactor Dosimetry, 12-17 September 1999, Osaka, Japan, to be published by the American Society of Testing and Materials in ASTM STP 1398
20. N. Soneda and T. Diaz de la Rubia, "Defect Production, Annealing Kinetics, and Damage Evolution in a-Fe: An Atomic-scale Computer Simulation, " PhilosophicalMagazineA 1998, 78, pp. 995-1019.
21. Stoller, R.E., "Molecular Dynamics Simulations of High Energy Cascades in Iron, " Microstructure of Irradiated Materials, I. M. Robertson, L. E. Rehn, S. J. Zinkle, and W. J. Phythian, Eds., Materials Research Society, Pittsburgh, PA, 1995, pp. 21-26.
22. B. D. Wirth and G. R. Odette, "Kinetic Lattice Monte Carlo Simulations of Cascade Aging in Iron and Dilute Iron-Copper Alloys, " Multiscale Modeling of Materials, V. V. Butalov, T. Diaz de la Rubia, P. Phillips, E. Kaxiras, and N. Ghoniem, Eds., Materials Research Society, Pittsburgh, PA, 1999, pp. 211-216.
23. Gold, R. and McElroy, W. N., "Radiation-Induced Embrittlement in Light Water Reactor Pressure Vessels, " Nuclear Engineering and Design 1987, 104, pp. 155-174.
24. Kussmaul, K., Fohl, J., and Weissenberg, T., "Assurance of the Pressure Vessel Integrity with Respect to Irradiation Embrittlement: Activities in the Federal Republic of Germany, " Radiation Embrittlement of Nuclear Reactor Pressure Vessel Steels, ASTMSTP1011, L. E. Steele, Ed., American Society of Testing and Materials, West Conshohocken, PA, 1989, pp. 3-26.
25. Suzuki, M., "Investigation of In-service Irradiated pressure Vessel Steel from the Decommissioned Reactor, JPDR, " ICONE-7411, 7th International Conference on Nuclear Engineering, Tokyo, Japan, April, 1999, pp. 1-8.
26. Nanstad, R. K., McCabe, D. E., and Swain, R. L., "Evaluation of Variability in Material Properties and Chemical Composition for Midland Reactor Weld WF-70, " Effects of Radiation on Materials, STP1325, R. K. Nanstad, M. L. Hamilton, F. A. Garner, and A. S. Kumar, Eds., American Society for Testing and Materials, West Conshohocken, PA, 1999, pp. 125-156.
27. Stoller, R. E. and Greenwood, L. R., "Subcascade Formation in Displacement Cascade Simulations; Implications for Fusion Reactor Materials, " Journal of Nuclear Materials 1999, 27l&272, pp. 57-62.
28. Greenwood, L. R., "SPECOMP Calculations of Radiation Damage in Compounds, " Reactor Dosimetry: Methods, Applications, and Standardization, ASTMSTP 1001, H. Farrar IV and E. P. Lippincott, Eds., American Society of Testing and Materials, West Conshohocken, PA, 1989, pp. 598-602.