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Volumn 37, Issue 5, 2010, Pages 753-761

Xenon transient simulation of the VVER-1000 nuclear reactor using adiabatic approximation

Author keywords

[No Author keywords available]

Indexed keywords

ADIABATIC APPROXIMATIONS; CALCULATION CODE; CORE CALCULATIONS; CRITICALITY CALCULATIONS; EFFECTIVE MULTIPLICATION FACTOR; FUEL ASSEMBLY; FUEL BURN-UPS; GROUP CONSTANT; NEUTRONICS; POWER DISTRIBUTIONS; SAFETY ANALYSIS REPORTS; START-UPS; THERMAL ABSORPTIONS; THERMAL REACTORS; TIME STEP; TRANSIENT SIMULATION; VISUAL BASIC PROGRAMS;

EID: 77950298366     PISSN: 03064549     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.anucene.2010.01.005     Document Type: Article
Times cited : (10)

References (12)
  • 1
    • 31144454856 scopus 로고    scopus 로고
    • Effect of different cross-section data sets on reflectors of a typical material test research reactor
    • Ahmad S.I., Ahmad N., and Aslam. Effect of different cross-section data sets on reflectors of a typical material test research reactor. Progress in Nuclear Energy 48 (2006) 155-164
    • (2006) Progress in Nuclear Energy , vol.48 , pp. 155-164
    • Ahmad, S.I.1    Ahmad, N.2    Aslam3
  • 2
    • 77950300893 scopus 로고    scopus 로고
    • Bushehr Safety Analysis Report, 2003, Nuclear Power Plant Division, Atomic Energy Organization of Iran.
    • Bushehr Safety Analysis Report, 2003, Nuclear Power Plant Division, Atomic Energy Organization of Iran.
  • 3
    • 0016057427 scopus 로고
    • Simulation studies of a practical reactor control system providing time optimal shutdown
    • Corran E., and Stapleton C.A. Simulation studies of a practical reactor control system providing time optimal shutdown. Nuclear Science and Engineering 54 (1974) 47-54
    • (1974) Nuclear Science and Engineering , vol.54 , pp. 47-54
    • Corran, E.1    Stapleton, C.A.2
  • 5
    • 33845613550 scopus 로고    scopus 로고
    • Reactivity coefficients simulation of the Iranian VVER-1000 nuclear reactor using WIMS and CITATION codes
    • Faghihi F., Fadaie A.H., and Sayareh R. Reactivity coefficients simulation of the Iranian VVER-1000 nuclear reactor using WIMS and CITATION codes. Progress in Nuclear Energy. 49 (2007) 68-78
    • (2007) Progress in Nuclear Energy. , vol.49 , pp. 68-78
    • Faghihi, F.1    Fadaie, A.H.2    Sayareh, R.3
  • 6
    • 77950295947 scopus 로고    scopus 로고
    • Fowler, T.B., Vondy, D.R., Cunningham, G.W., 1971. Nuclear Reactor Core Analysis Code: CITATION. ORNL-TM-2496, Rev. 2, Suppl. 1, 2, and 3.
    • Fowler, T.B., Vondy, D.R., Cunningham, G.W., 1971. Nuclear Reactor Core Analysis Code: CITATION. ORNL-TM-2496, Rev. 2, Suppl. 1, 2, and 3.
  • 7
    • 77950301087 scopus 로고    scopus 로고
    • Gulati M.M.L. et al., 1958. In: Proceedings of Second United Nations Conference for Peaceful Uses of Atomic Energy, Geneva, Switzerland, 8-15 September, Session A-14, P/1627, pp. 540-552.
    • Gulati M.M.L. et al., 1958. In: Proceedings of Second United Nations Conference for Peaceful Uses of Atomic Energy, Geneva, Switzerland, 8-15 September, Session A-14, P/1627, pp. 540-552.
  • 8
    • 77950296012 scopus 로고    scopus 로고
    • Halsall, M.J., 1980. A Summary of WIMS-D4 Input Options. AEEW-M 1327, Winfrith.
    • Halsall, M.J., 1980. A Summary of WIMS-D4 Input Options. AEEW-M 1327, Winfrith.
  • 9
    • 0040687539 scopus 로고
    • The application of analogue methods to compute and predict xenon poisoning in a high flux nuclear reactor
    • Maclusky G.J.R., and Sc B. The application of analogue methods to compute and predict xenon poisoning in a high flux nuclear reactor. Journal of the British Nuclear Energy Conference 2 (1957) 361-370
    • (1957) Journal of the British Nuclear Energy Conference , vol.2 , pp. 361-370
    • Maclusky, G.J.R.1    Sc, B.2
  • 11
    • 0033102249 scopus 로고    scopus 로고
    • A method to avoid spatial treatment in xenon poisoning calculation while providing conservative reactivity estimates
    • Tashinsky Vladimir.G., et al. A method to avoid spatial treatment in xenon poisoning calculation while providing conservative reactivity estimates. Annals of Nuclear Energy 26 (1999) 373-385
    • (1999) Annals of Nuclear Energy , vol.26 , pp. 373-385
    • Tashinsky, Vladimir.G.1


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.