메뉴 건너뛰기




Volumn STP 1405, Issue , 2001, Pages 151-173

Review of Phosphorus Segregation and Intergranular Embrittlement in Reactor Pressure Vessel Steels

Author keywords

grain boundaries; HAZ; intergranular embrittlement; phosphorus segregation; thermal anneal heat treatment

Indexed keywords

BRITTLE FRACTURE; CHROMIUM ALLOYS; EMBRITTLEMENT; HEAT AFFECTED ZONE; HEAT TREATMENT; MANGANESE ALLOYS; MOLYBDENUM ALLOYS; NEUTRON IRRADIATION; PRESSURE VESSELS; PRESSURIZED WATER REACTORS; SEGREGATION (METALLOGRAPHY); TEMPERATURE; TEXTURES; THERMAL AGING;

EID: 85131426478     PISSN: 00660558     EISSN: None     Source Type: Conference Proceeding    
DOI: 10.1520/STP10531S     Document Type: Conference Paper
Times cited : (28)

References (30)
  • 3
    • 0023425022 scopus 로고
    • Effects Of Manganese On The Grain Boundary Segregation, Bulk and Grain Boundary Diffusivity Of Phosphorus In Ferrite
    • Grabke, H. J., Hennesen, K., Moller R., and Wei, W., "Effects Of Manganese On The Grain Boundary Segregation, Bulk and Grain Boundary Diffusivity Of Phosphorus In Ferrite", Scripta Metallurgica, Vol. 21, 1987, pp. 1329-1334.
    • (1987) Scripta Metallurgica , vol.21 , pp. 1329-1334
    • Grabke, H.J.1    Hennesen, K.2    Moller, R.3    Wei, W.4
  • 4
    • 0010515157 scopus 로고    scopus 로고
    • Neutron Radiation Embrittlement Studies In Support Of Continued Operation And Validation By Sampling Of Magnox Reactor Steel Pressure Vessels And Components
    • Jones R. B., and Bolton C. J., "Neutron Radiation Embrittlement Studies In Support Of Continued Operation And Validation By Sampling Of Magnox Reactor Steel Pressure Vessels And Components", in Proc. 24th Water Reactor Safety Meeting organised USNRC October 1996.
    • (1996) Proc. 24th Water Reactor Safety Meeting organised USNRC October
    • Jones, R.B.1    Bolton, C.J.2
  • 6
    • 0033353923 scopus 로고    scopus 로고
    • Development of Embrittlement Prediction Models for U.S. Power Reactors and the Impact of Heat-Affected Zone to Thermal Annealing
    • R.K.Nanstad, M.L.Hamilton, F.A.Garner and A.S.Kumar, Eds., American Society for Testing and Materials, West Conshohocken, PA
    • th International Symposium, ASTMSTP 1325, 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 525-540.
    • (1999) th International Symposium, ASTMSTP , vol.1325 , pp. 525-540
    • Wang, J.A.1
  • 7
    • 0033340301 scopus 로고    scopus 로고
    • Experimental Tests of Irradiation-Anneal-Reirradiated Effects on Mechanical Properties of RPV Plate and Weld Materials
    • R.K.Nanstad, M.L.Hamilton, F.A.Garner and A.S.Kumar, Eds., American Society for Testing and Materials, West Conshohocken, PA
    • tn International Symposium, ASTMSTP 1325, 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 388-402.
    • (1999) tn International Symposium, ASTMSTP , vol.1325 , pp. 388-402
    • Rosinski, S.T.1    Hawthorne, J.R.2    Rocheau, G.E.3
  • 8
    • 0030217368 scopus 로고    scopus 로고
    • On the Effect of flux and Composition on Irradiation Hardening at 60°C
    • D. S. Gelles, et al., Eds., American Society for Testing and Materials, West Conshohocken, PA
    • th International Symposium, ASTMSTP 1270, D. S. Gelles, et al., Eds., American Society for Testing and Materials, West Conshohocken, PA, 1996 pp 547-568.
    • (1996) th International Symposium, ASTMSTP , vol.1270 , pp. 547-568
    • Odette, G.R.1    Lucas, G.2    Klingensmith, D.3
  • 13
    • 0005644892 scopus 로고
    • Quantification of Microstructural Effects on Thermal Aging of Induced Embrittlement in Pressure Vessel Steels
    • Vatter, I. A., Hippsley, C. A., "Quantification of Microstructural Effects on Thermal Aging of Induced Embrittlement in Pressure Vessel Steels." AEA Technology Report AEA-RS-4464, 1993.
    • (1993) AEA Technology Report AEA-RS-4464
    • Vatter, I.A.1    Hippsley, C.A.2
  • 15
    • 0033313628 scopus 로고    scopus 로고
    • Temper Embrittlement, Irradiation Induced Phosphorus Segregation and Implications for Post-Irradiation Annealing of Reactor Pressure Vessels
    • R.K.Nanstad, M.L.Hamilton, F.A.Garner and A.S.Kumar, Eds., American Society for Testing and Materials, West Conshohocken, PA
    • th International Symposium, ASTMSTP 1325, R.K.Nanstad, M.L.Hamilton, F.A.Garner and A.S.Kumar, Eds., American Society for Testing and Materials, West Conshohocken, PA, 1999, pp296-316.
    • (1999) th International Symposium, ASTMSTP , vol.1325 , pp. 296-316
    • McElroy, R.J.1    English, C.A.2    Foreman, A.J.E.3    Gage, G.4    Hyde, J.M.5    Ray, P.H.N.6    Vatter, I.A.7
  • 16
    • 0003849486 scopus 로고    scopus 로고
    • Initial Evaluation of the Heat-Affected-Zone, Local Embrittlement Phenomenon As It Applies To Nuclear Reactor Vessels
    • September ORNL/NRC/LTR-99/10
    • McCabe, D. E., "Initial Evaluation of the Heat-Affected-Zone, Local Embrittlement Phenomenon As It Applies To Nuclear Reactor Vessels." Letter report, September 1999, ORNL/NRC/LTR-99/10.
    • (1999) Letter report
    • McCabe, D.E.1
  • 17
    • 85146742154 scopus 로고    scopus 로고
    • Investigation of Temper Embrittlement in Reactor Pressure Vessel Steels Following Thermal Aging, Irradiation, and Thermal Annealing
    • S. T. Rosinski, M.L. Grossbeck, T. R. Allen, and A.S. Kumar, Eds, American Society for Testing and Materials, West Conshohocken, PA, This
    • McCabe D. E., Nanstad R K., English C A., Ortner S R., "Investigation of Temper Embrittlement in Reactor Pressure Vessel Steels Following Thermal Aging, Irradiation, and Thermal Annealing, " Effects of radiation on Materials: 20™ International Symposium, ASTMSTP 1405, S. T. Rosinski, M.L. Grossbeck, T. R. Allen, and A.S. Kumar, Eds, American Society for Testing and Materials, West Conshohocken, PA, 2002. This volume.
    • (2002) Effects of radiation on Materials: 20™ International Symposium, ASTMSTP , vol.1405
    • McCabe, D.E.1    Nanstad, R.K.2    English, C.A.3    Ortner, S.R.4
  • 19
    • 0030218388 scopus 로고    scopus 로고
    • The Modelling Of Irradiation-Enhanced Phosphorus Segregation In Neutron-Irradiated Reactor Pressure Vessel Submerged Arc Welds
    • D. S. Gelles, et al., Eds., American Society for Testing and Materials, West Conshohocken, PA
    • Druce, S. G., English, C. A., Foreman, A. J. E., McElroy, R. J., Vatter, I. A., Bolton, C. J., Buswell, J. T., and Jones, R. B., "The Modelling Of Irradiation-Enhanced Phosphorus Segregation In Neutron-Irradiated Reactor Pressure Vessel Submerged Arc Welds", Effects Of Radiation On Materials: 17™ International Symposium, ASTMSTP 1270, D. S. Gelles, et al., Eds., American Society for Testing and Materials, West Conshohocken, PA, 1996.pp. 119-137.
    • (1996) Effects Of Radiation On Materials: 17™ International Symposium, ASTMSTP , vol.1270 , pp. 119-137
    • Druce, S.G.1    English, C.A.2    Foreman, A.J.E.3    McElroy, R.J.4    Vatter, I.A.5    Bolton, C.J.6    Buswell, J.T.7    Jones, R.B.8
  • 20
    • 0005559907 scopus 로고    scopus 로고
    • Palisades Annealing Recovery and Irradiation Program Evaluation of the Recovery of Hardness and the incidence of Intergranular Fracture after Post-Irradiation Annealing
    • July
    • Gage, G., Atkins, T., Lane, C, Ray, P. H. N., and Wigham, D., "Palisades Annealing Recovery and Irradiation Program Evaluation of the Recovery of Hardness and the incidence of Intergranular Fracture after Post-Irradiation Annealing". AEA Technology Report AEA-T 1696, July 1997.
    • (1997) AEA Technology Report AEA-T 1696
    • Gage, G.1    Atkins, T.2    Lane, C.3    Ray, P.H.N.4    Wigham, D.5
  • 22
    • 0028257339 scopus 로고
    • An APFIM Survey of Grain Boundary Segregation and Precipitation in Irradiated Pressure Vessel Steels
    • A. S. Kumar, et al., Eds., American Society for Testing and Materials, West Conshohocken, PA
    • th International Symposium, ASTMSTP 1175, A. S. Kumar, et al., Eds., American Society for Testing and Materials, West Conshohocken, PA, 1993, pp. 492-502.
    • (1993) th International Symposium, ASTMSTP , vol.1175 , pp. 492-502
    • Miller, M.K.1    Burke, G.2
  • 23
    • 0033335061 scopus 로고    scopus 로고
    • Irradiation Embrittlement of Reactor Pressure Vessel Steels due to Mechanisms other than Radiation Hardening
    • R.K.Nanstad, M.L.Hamilton, F.A.Garner and A.S.Kumar, Eds., American Society for Testing and Materials, West Conshohocken, PA
    • th International Symposium, ASTMSTP 1325, 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 271-295.
    • (1999) th International Symposium, ASTMSTP , vol.1325 , pp. 271-295
    • Gurovich, B.A.1    Korolev, Y.N.2    Kuleshova, E.A.3    Nikolaev, Y.A.4    Shtrombakh, Y.I.5
  • 25
    • 0027149273 scopus 로고
    • Temper Embrittlement of Phosphorus on thermal and Neutron embrittlement of Pressure vessel steels
    • ASTM1170, Lendell E., Steele, Ed., American Society for Testing and Materials, Philadelphia
    • Soulat, P., Miannay, D., and Horowitz, H., "Temper Embrittlement of Phosphorus on thermal and Neutron embrittlement of Pressure vessel steels." Radiation EmbrittlementofNuclearPressureVesselSteels:AnInternationalReview (Fourth Volume), ASTM1170, Lendell E., Steele, Ed., American Society for Testing and Materials, Philadelphia, 1993, pp. 283-299.
    • (1993) Radiation EmbrittlementofNuclearPressureVesselSteels:AnInternationalReview (Fourth Volume) , pp. 283-299
    • Soulat, P.1    Miannay, D.2    Horowitz, H.3
  • 26
    • 0027188054 scopus 로고
    • Analysis of radiation Embrittlement Results from a French Forging Examined in the Second Phase of an IAEA-Co-ordinated Research Program
    • ASTM1170, Lendell E., Steele, Ed., American Society for Testing and Materials, Philadelphia
    • Soulat, P., Houssin, B., Bocquet, P., and Bethmont, M., "Analysis of radiation Embrittlement Results from a French Forging Examined in the Second Phase of an IAEA-Co-ordinated Research Program". Radiation embrittlement of Nuclear Pressure Vessel Steels: An International Review (Fourth Volume), ASTM1170, Lendell E., Steele, Ed., American Society for Testing and Materials, Philadelphia, 1993, pp. 249-265.
    • (1993) Radiation embrittlement of Nuclear Pressure Vessel Steels: An International Review (Fourth Volume) , pp. 249-265
    • Soulat, P.1    Houssin, B.2    Bocquet, P.3    Bethmont, M.4
  • 28
    • 0034476064 scopus 로고    scopus 로고
    • Comparison Of Observed and Predicted Data On Radiation Induced Grain Boundary Phosphorus Segregation In VVER Steels
    • M.L.Hamilton, A.S. Kumar, S.T.Rosinski and M.L.Grossbeck, Eds, American Society for Testing and Materials, West Conshohocken, PA
    • th International Symposium, ASTMSTP 1366, M.L.Hamilton, A.S. Kumar, S.T.Rosinski and M.L.Grossbeck, Eds, American Society for Testing and Materials, West Conshohocken, PA, 1999, pp. 399-414.
    • (1999) th International Symposium, ASTMSTP , vol.1366 , pp. 399-414
    • Nikolaeva, A.V.1    Kevorkyan, Y.R.2    Nikolaev, Y.A.3
  • 29
    • 27844604585 scopus 로고    scopus 로고
    • Embrittlement, Hardening, and Grain Boundary Composition in an Irradiated and Thermally Aged Fe-P-C Alloy, Effects of Radiation on Materials, 19
    • M.L.Hamilton, A.S. Kumar, S.T.Rosinski and M.L.Grossbeck, Eds, American Society for Testing and Materials, West Conshohocken, PA
    • Jones, R. B., Cowan, J. R., Corcoran, R. C, and Walmsley, J. C, "Embrittlement, Hardening, and Grain Boundary Composition in an Irradiated and Thermally Aged Fe-P-C Alloy, Effects of Radiation on Materials, 19*" International Symposium, ASTMSTP 1366, M.L.Hamilton, A.S. Kumar, S.T.Rosinski and M.L.Grossbeck, Eds, American Society for Testing and Materials, West Conshohocken, PA, 1999. pp. 473-491.
    • (1999) International Symposium, ASTMSTP , vol.1366 , pp. 473-491
    • Jones, R.B.1    Cowan, J.R.2    Corcoran, R.C.3    Walmsley, J.C.4


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.