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Volumn , Issue 148, 2000, Pages 204-217

An evaluation of through-thickness changes in primary damage production in commercial reactor pressure vessels

Author keywords

Damage attenuation; Displacement cascades; Ferritic steels; Modeling; Molecular dynamics; Point defects; Pressure vessels; Radiation damage

Indexed keywords

IRRADIATION; MOLECULAR DYNAMICS; NUCLEAR REACTORS; POINT DEFECTS; RADIATION DAMAGE; STATISTICAL METHODS; STEEL;

EID: 0034462329     PISSN: 03070492     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper
Times cited : (9)

References (27)
  • 1
    • 0005552070 scopus 로고
    • Radiation embrittlement of reactor vessel materials
    • U.S. Nuclear Regulatory Commission, May, available from the U.S. National Technical Information Service, Springfield, VA
    • (1988) Regulatory Guide 1.99, Revision 2
  • 4
    • 0003192250 scopus 로고
    • Recommendations of IAEA specialists meeting on radiation damage units in graphite and ferritic and austenitic steels
    • (1975) Nuclear Engineering and Design , vol.33 , pp. 48
  • 12
    • 0034481941 scopus 로고    scopus 로고
    • An evaluation of neutron energy spectrum effects based on molecular dynamics displacement cascade simulations
    • M. L. Hamilton, A. S. Kumar, S. T. Rosinski, and M. L. Grossbeck, Eds., American Society for Testing and Materials, West Conshohocken, PA
    • (2000) Effects of Radiation on Materials, STP , vol.1366 , pp. 548-559
    • Stoller, R.E.1    Greenwood, L.R.2
  • 21
    • 0032591786 scopus 로고    scopus 로고
    • Kinetic lattice Monte Carlo simulations of cascade aging in iron and dilute iron-copper alloys
    • V. V. Butalov, T. Diaz de la Rubia, P. Phillips, E. Kaxiras, and N. Ghoniem, Eds., Materials Research Society, Pittsburgh, PA
    • (1999) Multiscale Modeling of Materials , pp. 211-216
    • Wirth, B.D.1    Odette, G.R.2


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.