메뉴 건너뛰기




Volumn 239, Issue 8, 2009, Pages 1531-1543

Neutronic design of hydride fueled BWRs

Author keywords

[No Author keywords available]

Indexed keywords

AXIAL POWER DISTRIBUTION; BUNDLE DESIGN; BURNABLE ABSORBER; CONTROL ELEMENTS; CORE DESIGN; DISCHARGE BURN-UP; FUEL BUNDLE; FUEL RODS; HYDRIDE FUEL; IN-BETWEEN; NEUTRONIC; NEUTRONIC ANALYSIS; NEUTRONIC DESIGN; OXIDE FUELS; PIN POWER DISTRIBUTION; POWER DENSITIES; REACTIVITY COEFFICIENTS; REACTIVITY WORTH; THERMAL HYDRAULICS; URANIUM ENRICHMENT; VIBRATION CHARACTERISTICS; WATER RODS;

EID: 67349259608     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.nucengdes.2009.01.016     Document Type: Article
Times cited : (19)

References (18)
  • 3
    • 67349282205 scopus 로고    scopus 로고
    • Cullen, D.E., Hansen, L.F., Lent, E.M., Plechaty E.F., 2003. Thermal Scattering Law Data: Implementation and Testing using the Monte Carlo neutron transport codes COG, MCNP and TART. UCRL-ID-153656.
    • Cullen, D.E., Hansen, L.F., Lent, E.M., Plechaty E.F., 2003. Thermal Scattering Law Data: Implementation and Testing using the Monte Carlo neutron transport codes COG, MCNP and TART. UCRL-ID-153656.
  • 6
    • 33847243332 scopus 로고    scopus 로고
    • Optimal hydride fueled BWR assembly designs. Advances in nuclear analysis and simulation
    • Vancouver, BC, Canada
    • Fratoni M., and Greenspan E. Optimal hydride fueled BWR assembly designs. Advances in nuclear analysis and simulation. Proceedings of the PHYSOR 2006. Vancouver, BC, Canada (2006)
    • (2006) Proceedings of the PHYSOR 2006
    • Fratoni, M.1    Greenspan, E.2
  • 9
    • 67349087189 scopus 로고
    • BWR fuel assembly having oxide and hydride fuel
    • US Patent 5,349,618
    • Greenspan, E., 1994. BWR fuel assembly having oxide and hydride fuel. US Patent 5,349,618.
    • (1994)
    • Greenspan, E.1
  • 13
    • 67349170250 scopus 로고    scopus 로고
    • X-5 Monte Carlo Team, 2003. MCNP-a general Monte Carlo N-particle transport code, Version 5. LA-CP-03-1987/0245/0284
    • X-5 Monte Carlo Team, 2003. MCNP-a general Monte Carlo N-particle transport code, Version 5. LA-CP-03-1987/0245/0284.
  • 14
    • 67349284600 scopus 로고    scopus 로고
    • Moore, R.L., Schnitzler, B.G., Wemple, C.A., Babcock, R.S., Wessel, D.E., 1995. MOCUP: MCNP-ORIGEN2 Coupled Utility Program. INEL-95/0523.
    • Moore, R.L., Schnitzler, B.G., Wemple, C.A., Babcock, R.S., Wessel, D.E., 1995. MOCUP: MCNP-ORIGEN2 Coupled Utility Program. INEL-95/0523.
  • 17
    • 2942628232 scopus 로고    scopus 로고
    • Performance improvement analysis of boiling water reactors by incorporation of hydride fuel
    • Wang K., and Greenspan E. Performance improvement analysis of boiling water reactors by incorporation of hydride fuel. Nuclear Engineering and Design 231 (2004) 163-175
    • (2004) Nuclear Engineering and Design , vol.231 , pp. 163-175
    • Wang, K.1    Greenspan, E.2


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.