메뉴 건너뛰기




Volumn 130, Issue 2, 1998, Pages 239-253

A high-conversion water reactor design

Author keywords

[No Author keywords available]

Indexed keywords

MACHINE DESIGN; MIXED OXIDE FUELS; NUCLEAR FUEL ELEMENTS; PLUTONIUM; REACTOR CORES; URANIUM;

EID: 0032180230     PISSN: 00295639     EISSN: None     Source Type: Journal    
DOI: 10.13182/NSE98-A2003     Document Type: Article
Times cited : (2)

References (21)
  • 2
    • 0023962816 scopus 로고
    • On the Reactivity Void Response of an Advanced Pressurized Water Reactor
    • Y. RONEN, M. J. LEIBSON, and A. RADKOWSKY, "On the Reactivity Void Response of an Advanced Pressurized Water Reactor," Nucl. Technol., 80, 225 (1988).
    • (1988) Nucl. Technol. , vol.80 , pp. 225
    • Ronen, Y.1    Leibson, M.J.2    Radkowsky, A.3
  • 3
    • 0023960973 scopus 로고
    • Analytical Methods in the High Conversion Reactor Core Design
    • Z. WILFRIED and O. WERNER, "Analytical Methods in the High Conversion Reactor Core Design, Nucl. Technol., 80. 292 (1988).
    • (1988) Nucl. Technol. , vol.80 , pp. 292
    • Wilfried, Z.1    Werner, O.2
  • 4
    • 0024621910 scopus 로고
    • Pancake Core High Conversion Light Water Reactor Concept
    • Y. ISHIGURO and K. OKUMURA, "Pancake Core High Conversion Light Water Reactor Concept," Nucl. Technol, 84, 331 (1989).
    • (1989) Nucl. Technol , vol.84 , pp. 331
    • Ishiguro, Y.1    Okumura, K.2
  • 6
    • 0023859384 scopus 로고
    • NEPTUN-III Reflooding and Boiloff Experiments with an LWHCR Fuel Bundle Simulator: Experimental Results and Initial Code Assessment Efforts
    • J. DREIER, G. ANALYTIS, and R. CHAWLA, "NEPTUN-III Reflooding and Boiloff Experiments with an LWHCR Fuel Bundle Simulator: Experimental Results and Initial Code Assessment Efforts," Nucl. Technol., 80, 93 (1988).
    • (1988) Nucl. Technol. , vol.80 , pp. 93
    • Dreier, J.1    Analytis, G.2    Chawla, R.3
  • 7
    • 11644320290 scopus 로고
    • NUREG/CR-4312, U.S. Nuclear Regulatory Commission
    • V. RANSOM et al., "RELAP 5/MOD 2 Code Manual," NUREG/CR-4312, Vols. 1 and 2, U.S. Nuclear Regulatory Commission (1985).
    • (1985) RELAP 5/MOD 2 Code Manual , vol.1-2
    • Ransom, V.1
  • 8
    • 0023861120 scopus 로고
    • Experimental Investigations on the Reflooding and Deformation Behavior of an Advanced Pressurized Water Reactor Tight-Lattice Fuel Rod Bundle in a Loss-of-Coolant Accident
    • F. J. ERBACHER and K. WIEHR, "Experimental Investigations on the Reflooding and Deformation Behavior of an Advanced Pressurized Water Reactor Tight-Lattice Fuel Rod Bundle in a Loss-of-Coolant Accident," Nucl. Technol., 80, 153 (1988).
    • (1988) Nucl. Technol. , vol.80 , pp. 153
    • Erbacher, F.J.1    Wiehr, K.2
  • 9
    • 0023825997 scopus 로고
    • Thermohydraulic Optimization of Homogeneous and Heterogeneous Advanced Pressurized Water Reactors
    • M. CIGARINI and M. DALLE DONNE, "Thermohydraulic Optimization of Homogeneous and Heterogeneous Advanced Pressurized Water Reactors, Nucl. Technol., 80, 107 (1988).
    • (1988) Nucl. Technol. , vol.80 , pp. 107
    • Cigarini, M.1    Dalle Donne, M.2
  • 11
    • 0020501266 scopus 로고
    • Untersuchungern zur Flutphase nach einem Külmittelverlust bei hochkonvertierenden fortgeschrittenen Druckwasserreaktoren (FDWR)
    • S. SCHUMANN and W. OLDEKOP, "Untersuchungern zur Flutphase nach einem Külmittelverlust bei hochkonvertierenden fortgeschrittenen Druckwasserreaktoren (FDWR)," Atomkernenergie-Kerntechnik, 42, 2, 80 (1983).
    • (1983) Atomkernenergie-Kerntechnik , vol.42 , Issue.2 , pp. 80
    • Schumann, S.1    Oldekop, W.2
  • 13
    • 11644262018 scopus 로고
    • Emergency Core Cooling Examinations for the Light Water High Conversion Reactor (LWCR)
    • Vienna, Austria, November 26-29
    • S. SCHUMANN, "Emergency Core Cooling Examinations for the Light Water High Conversion Reactor (LWCR)," presented at IAEA Technical Committee Mtg. Advanced Light and Heavy Water Reactor Technology, Vienna, Austria, November 26-29, 1984.
    • (1984) IAEA Technical Committee Mtg. Advanced Light and Heavy Water Reactor Technology
    • Schumann, S.1
  • 14
    • 0023847334 scopus 로고
    • Loss-of-Coolant-Accident and Anticipated Transient Without Scram Calculations for Homogeneous and Heterogeneous Advanced Pressurized Water Reactors
    • M. DALLE DONNE and C. FERRERO, "Loss-of-Coolant-Accident and Anticipated Transient Without Scram Calculations for Homogeneous and Heterogeneous Advanced Pressurized Water Reactors," Nucl. Technol., 80, 133 (1988).
    • (1988) Nucl. Technol. , vol.80 , pp. 133
    • Dalle Donne, M.1    Ferrero, C.2
  • 17
    • 0022137137 scopus 로고
    • Critical Heat Flux Correlation for Triangular Arrays of Rod Bundles with Tight Lattices, Including the Spiral Spacer Effect
    • M. DALLE DONNE and W. HAME, "Critical Heat Flux Correlation for Triangular Arrays of Rod Bundles with Tight Lattices, Including the Spiral Spacer Effect," Nucl. Technol., 71, 111 (1985).
    • (1985) Nucl. Technol. , vol.71 , pp. 111
    • Dalle Donne, M.1    Hame, W.2
  • 19
    • 0001337819 scopus 로고
    • A General Description of the Lattice Code WIMS
    • J. R. ASKEW et al., "A General Description of the Lattice Code WIMS," J. Br. Nucl. Energy Soc., 5, 564 (1966).
    • (1966) J. Br. Nucl. Energy Soc. , vol.5 , pp. 564
    • Askew, J.R.1


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.