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Volumn 126, Issue 1, 1997, Pages 80-93

Physics study on direct use of spent pressurized water reactor fuel in CANDU (DUPIC)

Author keywords

[No Author keywords available]

Indexed keywords


EID: 0002943852     PISSN: 00295639     EISSN: None     Source Type: Journal    
DOI: 10.13182/NSE97-A24459     Document Type: Article
Times cited : (59)

References (25)
  • 4
    • 4243049072 scopus 로고
    • Effect of CANFLEX Bundle Design on CANDU-6 Reactor Safety
    • Pembroke, Canada
    • D. J. OH et al., "Effect of CANFLEX Bundle Design on CANDU-6 Reactor Safety," Proc. 4th Int. Conf. CANDU Fuel, Pembroke, Canada, 1995.
    • (1995) Proc. 4th Int. Conf. CANDU Fuel
    • Oh, D.J.1
  • 9
    • 0026254319 scopus 로고
    • Evaluation of Liquid-Metal Reactor Design Options for Reduction of Sodium Void Worth
    • H. S. KHALIL and R. N. HILL, "Evaluation of Liquid-Metal Reactor Design Options for Reduction of Sodium Void Worth," Nucl. Sci. Eng., 109, 221 (1991).
    • (1991) Nucl. Sci. Eng. , vol.109 , pp. 221
    • Khalil, H.S.1    Hill, R.N.2
  • 16
    • 0342889777 scopus 로고
    • Fuel Management and DUPIC Fuel Performance
    • H. B. CHOI, B. W. RHEE, and H. PARK, "Fuel Management and DUPIC Fuel Performance," Trans. Am. Nucl. Soc., 73, 162 (1995).
    • (1995) Trans. Am. Nucl. Soc. , vol.73 , pp. 162
    • Choi, H.B.1    Rhee, B.W.2    Park, H.3
  • 17
    • 0001463956 scopus 로고
    • Overview of Current RFSP-Code Capabilities for CANDU Core Analysis
    • B. ROUBEN, "Overview of Current RFSP-Code Capabilities for CANDU Core Analysis," Trans. Am. Nucl. Soc., 72, 339 (1995).
    • (1995) Trans. Am. Nucl. Soc. , vol.72 , pp. 339
    • Rouben, B.1
  • 19
    • 0026984216 scopus 로고
    • Behaviour of Bruce NGS-A Fuel Irradiated to a Burnup of ∼500 MWh/kgU
    • Chalk River, Canada
    • M. R. FLOYD et al., "Behaviour of Bruce NGS-A Fuel Irradiated to a Burnup of ∼500 MWh/kgU," Proc. 3rd Int. Conf. CANDU Fuel, Chalk River, Canada, 1992.
    • (1992) Proc. 3rd Int. Conf. CANDU Fuel
    • Floyd, M.R.1
  • 22
    • 0017368124 scopus 로고
    • CANDU Fuel-Power Ramp Performance Criteria
    • W. J. PENN, R. K. LO, and J. C. WOOD, "CANDU Fuel-Power Ramp Performance Criteria," Nucl. Technol., 34, 249 (1977).
    • (1977) Nucl. Technol. , vol.34 , pp. 249
    • Penn, W.J.1    Lo, R.K.2    Wood, J.C.3


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.