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Volumn 50, Issue 2-6, 2008, Pages 377-381

Decay heat production in a TRU burner

Author keywords

ADS; Decay heat; Minor actinides; Nuclear reactor; TRU burner

Indexed keywords

COMPUTATION THEORY; NUCLEAR FUELS; NUCLEAR REACTORS; RESEARCH AND DEVELOPMENT MANAGEMENT;

EID: 39549103041     PISSN: 01491970     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.pnucene.2007.11.020     Document Type: Article
Times cited : (14)

References (8)
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    • 39549094471 scopus 로고    scopus 로고
    • Alcouffe, R.E., Baker, R.S., Brinkley, F.W., Marr, D.R., O'Dell, R.D., Walters, W.F., 1995. DANTSYS: a Diffusion Accelerated Neutral Particle Transport Code System, Los Alamos National Laboratory Report LA-12969-M.
    • Alcouffe, R.E., Baker, R.S., Brinkley, F.W., Marr, D.R., O'Dell, R.D., Walters, W.F., 1995. DANTSYS: a Diffusion Accelerated Neutral Particle Transport Code System, Los Alamos National Laboratory Report LA-12969-M.
  • 2
    • 0026135647 scopus 로고
    • Current status and proposed improvements to the ANSI/ANS-5.1 American National Standard for decay heat power in light water reactors
    • Dickens J.K., England T.R., and Schenter R.E. Current status and proposed improvements to the ANSI/ANS-5.1 American National Standard for decay heat power in light water reactors. Nuclear Safety 32 (1992) 209
    • (1992) Nuclear Safety , vol.32 , pp. 209
    • Dickens, J.K.1    England, T.R.2    Schenter, R.E.3
  • 3
    • 22344445867 scopus 로고    scopus 로고
    • Kim, Y.I., Hill, R., Grimm, K., Rimpault, G., Newton, T., Li, Z.H., Rineiski, A., Mohanakrishan, P., Ishikawa, M., Lee, K.B., Danilytchev, A., Stogov, V., 2004. BN-600 full MOX core benchmark analysis. In: Proceedings of the International Conference on Physics of Fuel Cycles and Advanced Nuclear Systems, PHYSOR 2004, Chicago, 25-29 April.
    • Kim, Y.I., Hill, R., Grimm, K., Rimpault, G., Newton, T., Li, Z.H., Rineiski, A., Mohanakrishan, P., Ishikawa, M., Lee, K.B., Danilytchev, A., Stogov, V., 2004. BN-600 full MOX core benchmark analysis. In: Proceedings of the International Conference on Physics of Fuel Cycles and Advanced Nuclear Systems, PHYSOR 2004, Chicago, 25-29 April.
  • 5
    • 33745211394 scopus 로고    scopus 로고
    • Heterogeneous cores for improved safety performance. A case study: the supercritical water fast reactor
    • Mori Mg., Maschek W., and Rineiski A. Heterogeneous cores for improved safety performance. A case study: the supercritical water fast reactor. Nuclear Engineering and Design 236 (2006) 1573
    • (2006) Nuclear Engineering and Design , vol.236 , pp. 1573
    • Mori, Mg.1    Maschek, W.2    Rineiski, A.3
  • 6
    • 39549110843 scopus 로고    scopus 로고
    • Rineiski, A., Sinitsa, V., Maschek, W., Wang, S., 2005. Kinetics and cross-section developments for analyses of reactor transmutation concepts with SIMMER. In: Proceedings of the International Conference on Mathematics and Computations, M&C 2005, Avignon, 12-15 September.
    • Rineiski, A., Sinitsa, V., Maschek, W., Wang, S., 2005. Kinetics and cross-section developments for analyses of reactor transmutation concepts with SIMMER. In: Proceedings of the International Conference on Mathematics and Computations, M&C 2005, Avignon, 12-15 September.
  • 7
    • 39549094042 scopus 로고    scopus 로고
    • Rowlands, J., 2000. Decay Heat Validation Studies, the JEF2.2 Nuclear Data Library. OECD/NEA Data Bank Report, JEFF Report 17 (Chapter 9).
    • Rowlands, J., 2000. Decay Heat Validation Studies, the JEF2.2 Nuclear Data Library. OECD/NEA Data Bank Report, JEFF Report 17 (Chapter 9).
  • 8
    • 39549108886 scopus 로고    scopus 로고
    • Wiese, H.W., 2002. Status und Weiterentwicklung des Inventarcodes KORIGEN, der Szenariocodes KORREC und SOLEQ sowie des Nachwärmecodes CALOR. Forschungszentrum Karlsruhe, Report FZKA 6741.
    • Wiese, H.W., 2002. Status und Weiterentwicklung des Inventarcodes KORIGEN, der Szenariocodes KORREC und SOLEQ sowie des Nachwärmecodes CALOR. Forschungszentrum Karlsruhe, Report FZKA 6741.


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.