메뉴 건너뛰기




Volumn 102, Issue 2, 2007, Pages 94-99

Safety prediction in nuclear power

Author keywords

[No Author keywords available]

Indexed keywords

BOUNDARY CONDITIONS; MONTE CARLO METHODS; NUCLEAR MATERIALS SAFEGUARDS; NUCLEAR REACTOR ACCIDENTS;

EID: 34249911725     PISSN: 10634258     EISSN: None     Source Type: Journal    
DOI: 10.1007/s10512-007-0014-2     Document Type: Article
Times cited : (4)

References (18)
  • 1
    • 9644274157 scopus 로고    scopus 로고
    • Strategy for the development of nuclear power in Russia in the first half of the 21st century
    • "Strategy for the development of nuclear power in Russia in the first half of the 21st century," Byull. Tsentra Obshch. Inf. At. Énerg., No. 6, 4-17 (2000).
    • (2000) Byull. Tsentra Obshch. Inf. At. Énerg , Issue.6 , pp. 4-17
  • 2
    • 34249865432 scopus 로고    scopus 로고
    • A. N. Rumyantsev and Yu. A. Ostroumov, Method of quantile estimates of the uncertainties in the analysis of frequencies, development, and consequences of rare and improbable accidents, Report No. 210.06-04/01 (1993), I. V. Kurchatov Institute of Atomic Energy.
    • A. N. Rumyantsev and Yu. A. Ostroumov, "Method of quantile estimates of the uncertainties in the analysis of frequencies, development, and consequences of rare and improbable accidents," Report No. 210.06-04/01 (1993), I. V. Kurchatov Institute of Atomic Energy.
  • 3
    • 34249899205 scopus 로고    scopus 로고
    • Method of quantile estimates of the uncertainties in the analysis of frequencies, development, and consequences of rare and improbable accidents
    • A. N. Rumyantsev and Yu. A. Ostroumov, "Method of quantile estimates of the uncertainties in the analysis of frequencies, development, and consequences of rare and improbable accidents," Preprint IAÉ-6295/15 (2003).
    • (2003) Preprint IAÉ-6295/15
    • Rumyantsev, A.N.1    Ostroumov, Y.A.2
  • 4
    • 34249897582 scopus 로고    scopus 로고
    • Prediction of the development of nuclear power and analysis of the uncertainties in predictive estimates
    • A. N. Rumyantsev, "Prediction of the development of nuclear power and analysis of the uncertainties in predictive estimates," Preprint IAÉ-6296/15 (2003).
    • (2003) Preprint IAÉ-6296/15
    • Rumyantsev, A.N.1
  • 5
    • 34249889386 scopus 로고
    • Calculation of the sensitivity of reactor characteristics to the constants taking account of the change in the nuclide compostion of the reactor during a run
    • V. B. Glebov, G. G. Kulikov, V. V. Khromov, et al., "Calculation of the sensitivity of reactor characteristics to the constants taking account of the change in the nuclide compostion of the reactor during a run," Vopr. At. Nauk. Tekh., Ser. Fiz. Yad. Reakt., No. 1, 11-17 (1991).
    • (1991) Vopr. At. Nauk. Tekh., Ser. Fiz. Yad. Reakt , Issue.1 , pp. 11-17
    • Glebov, V.B.1    Kulikov, G.G.2    Khromov, V.V.3
  • 7
    • 34249870912 scopus 로고
    • Verification of complex program systems for calculating the dynamics of power reactors based on experimental data
    • A. G. Markitan, V. M. Panin, and L. N. Podlazov, "Verification of complex program systems for calculating the dynamics of power reactors based on experimental data," ibid., No. 5, 22-25 (1991).
    • (1991) Vopr. At. Nauk. Tekh., Ser. Fiz. Yad. Reakt , Issue.5 , pp. 22-25
    • Markitan, A.G.1    Panin, V.M.2    Podlazov, L.N.3
  • 9
    • 0036412483 scopus 로고    scopus 로고
    • Investigation of the safety of RBMK reactors during accidents initiated by partial ruptures of the circulation loop
    • A. I. Dostov and A. Ya. Kramerov, "Investigation of the safety of RBMK reactors during accidents initiated by partial ruptures of the circulation loop," At. Énerg., 92, No. 1, 23-30 (2002).
    • (2002) At. Énerg , vol.92 , Issue.1 , pp. 23-30
    • Dostov, A.I.1    Kramerov, A.Y.2
  • 10
    • 0036914449 scopus 로고    scopus 로고
    • Method for performing a statistical analysis of the uncertainties of thermohydraulic calculations
    • D. A. Afremov, Yu. V. Zhuravleva, Yu. V. Mironov, and V. E. Radkevich, "Method for performing a statistical analysis of the uncertainties of thermohydraulic calculations," At. Énerg., 93, No. 2, 101-109 (2002).
    • (2002) At. Énerg , vol.93 , Issue.2 , pp. 101-109
    • Afremov, D.A.1    Zhuravleva, Y.V.2    Mironov, Y.V.3    Radkevich, V.E.4
  • 11
    • 0028596709 scopus 로고
    • Uncertainty and sensitivity analysis of post-experiment calculation in thermal hydraulics
    • H. Glaeser, E. Hofer, M. Kloss, and T. Skorek, "Uncertainty and sensitivity analysis of post-experiment calculation in thermal hydraulics," Reliability Eng. System Safety, No. 45, 19-33 (1994).
    • (1994) Reliability Eng. System Safety , Issue.45 , pp. 19-33
    • Glaeser, H.1    Hofer, E.2    Kloss, M.3    Skorek, T.4
  • 12
    • 34249871992 scopus 로고    scopus 로고
    • RELAP5/MOD3 Code Manual, NUREG/CR-5535 (1995).
    • RELAP5/MOD3 Code Manual, NUREG/CR-5535 (1995).
  • 13
    • 0003924016 scopus 로고
    • Russian translation, Izd. Inostr. Lit, Moscow
    • S. Wilks, Mathematical Statistics [Russian translation], Izd. Inostr. Lit., Moscow (1967).
    • (1967) Mathematical Statistics
    • Wilks, S.1
  • 15
    • 34249864854 scopus 로고    scopus 로고
    • M. I. Ageev, L. S. Krivonos, and Yu. I. Markov, Algorithms (101-150), Vychislit. Tsentr Akad. Nauk SSSR, Moscow (1966).
    • M. I. Ageev, L. S. Krivonos, and Yu. I. Markov, Algorithms (101-150), Vychislit. Tsentr Akad. Nauk SSSR, Moscow (1966).
  • 16
    • 33644897567 scopus 로고    scopus 로고
    • Estimate of the bias in the results of Monte Carlo calculations of reactors and storage sites for nuclear fuel
    • L. V. Maiorov, "Estimate of the bias in the results of Monte Carlo calculations of reactors and storage sites for nuclear fuel," At. Énerg., 97, No. 4, 243-256 (2004).
    • (2004) At. Énerg , vol.97 , Issue.4 , pp. 243-256
    • Maiorov, L.V.1
  • 18
    • 27744489625 scopus 로고    scopus 로고
    • Analysis of the uncertainties of calculations of loss-of-coolant accidents for the No. 1 unit of the Kursk nuclear power plant
    • D. A. Afremov, Yu. V. Zhuravleva, Yu. V. Mironov, et al., "Analysis of the uncertainties of calculations of loss-of-coolant accidents for the No. 1 unit of the Kursk nuclear power plant," At. Énerg., 98, No. 6, 422-428 (2005).
    • (2005) At. Énerg , vol.98 , Issue.6 , pp. 422-428
    • Afremov, D.A.1    Zhuravleva, Y.V.2    Mironov, Y.V.3


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.