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Volumn 37, Issue 5, 2010, Pages 629-638

Transmutation of americium in a medium size sodium cooled fast reactor design

Author keywords

[No Author keywords available]

Indexed keywords

CONCENTRATION OF; CONSUMPTION RATES; FUEL FAILURE; GEOMETRICAL MODELS; MAXIMUM FUEL TEMPERATURES; MEDIUM SIZE; MONTE CARLO CODES; MOX FUEL; POWER PENALTY; SAFETY PARAMETERS; SODIUM COOLED FAST REACTOR; SODIUM COOLED REACTOR;

EID: 77950299511     PISSN: 03064549     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.anucene.2009.12.014     Document Type: Review
Times cited : (24)

References (43)
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    • Boltax, A. et al., 1991. Reliability of Fast Reactor Mixed-oxide Fuel During Operational Transients, ANL/CP-73613, DE91-018633, Materials and Components Technology Division, Argonne National Laboratory, Illinois.
  • 6
    • 33645268017 scopus 로고
    • Transient and static mechanical properties of D9 fuel pin cladding and duct material irradiated to high fluence
    • Philadelphia, pp
    • Cannon, N.S. et al., 1992. Transient and static mechanical properties of D9 fuel pin cladding and duct material irradiated to high fluence. In: Effects of Radiation on Materials: 15th Int. Symposium, Philadelphia, pp. 1071-1082.
    • (1992) Effects of Radiation on Materials: 15th Int. Symposium , pp. 1071-1082
    • Cannon, N.S.1
  • 10
    • 77950298843 scopus 로고    scopus 로고
    • Danilytchev, A. et al., 2003. Reactivity Coefficients in Test Model IAEA (Phase 4), IAEA-RC-803.4, TWG-FR/113, Obninsk, pp. 245-271.
    • Danilytchev, A. et al., 2003. Reactivity Coefficients in Test Model IAEA (Phase 4), IAEA-RC-803.4, TWG-FR/113, Obninsk, pp. 245-271.
  • 11
    • 77950296500 scopus 로고    scopus 로고
    • Nuclear technology-bridging the Millennia
    • Wyoming
    • Delpech, M. et al., 1999. Nuclear technology-bridging the Millennia. In: Proc. Int. Conf. Global 1999, Wyoming.
    • (1999) Proc. Int. Conf. Global
    • Delpech, M.1
  • 17
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    • Advanced nuclear fuel cycles and systems
    • Idaho
    • Fazio, C. et al., 2007. Advanced nuclear fuel cycles and systems. In: Proc. Int. Conf. Global 2007, Idaho.
    • (2007) Proc. Int. Conf. Global
    • Fazio, C.1
  • 20
    • 31744442262 scopus 로고    scopus 로고
    • Nuclear Power Technology Development Section, IAEA-TECDOC-866, IAEA
    • Nuclear Power Technology Development Section, 1996. Fast Reactor Database, IAEA-TECDOC-866, IAEA.
    • (1996) Fast Reactor Database
  • 22
    • 77950296883 scopus 로고    scopus 로고
    • Nuclear technology-bridging the Millennia
    • Wyoming
    • Ikeda, K. et al., 1999. Nuclear technology-bridging the Millennia. In: Proc. Int. Conf. Global 1999, Wyoming.
    • (1999) Proc. Int. Conf. Global
    • Ikeda, K.1
  • 23
    • 77950295920 scopus 로고    scopus 로고
    • JEFF-3.0 Nuclear Data Library, NEA Data Bank, 2002.
    • JEFF-3.0 Nuclear Data Library, NEA Data Bank, 2002.
  • 25
    • 77950299755 scopus 로고    scopus 로고
    • Kim, Young-In, 2004. BN600 Fully MOX Fuelled Core Benchmark Analysis, IAEA-RC-803.5, TWG-FR/120, Vienna.
    • Kim, Young-In, 2004. BN600 Fully MOX Fuelled Core Benchmark Analysis, IAEA-RC-803.5, TWG-FR/120, Vienna.
  • 34
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    • Intercomparison of systems for TRU recycle at equilibrium
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  • 36
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    • Physics and safety studies of low conversion ratio sodium cooled fast reactors
    • New Orleans
    • Smith, M.A. et al., 2003. Physics and safety studies of low conversion ratio sodium cooled fast reactors. In: Proc. Int. Conf. GLOBAL 2003, New Orleans.
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    • Smith, M.A.1


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.