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Volumn 42, Issue 7, 2005, Pages 608-617

Development of a fbr fuel bundle-duct interaction analysis code-BAMBOO: Analysis model and verification by phenix high burn-up fuel subassemblies

Author keywords

BDI level; Bundle duct interaction; Fast breeder reactor; Fuel subassembly; High burn up; Irradiation creep; Oval distortion; Pin dispersion; Void swelling

Indexed keywords

BDI LEVEL; BUNDLE/DUCT INTERACTION; FAST BREEDER REACTOR; FUEL SUBASSEMBLY; HIGH BURN-UP; IRRADIATION CREEP; OVAL-DISTORTION; PIN DISPERSION; VOID SWELLING;

EID: 24944526293     PISSN: 00223131     EISSN: None     Source Type: Journal    
DOI: 10.1080/18811248.2004.9726428     Document Type: Article
Times cited : (11)

References (5)
  • 1
    • 0035472727 scopus 로고    scopus 로고
    • Development of a fast breeder reactor fuel bundle-duct interaction analysis code-BAMBOO: Analysis model and validation by the out-of-pile compression test
    • T. Uwaba, K. Tanaka, “Development of a fast breeder reactor fuel bundle-duct interaction analysis code-BAMBOO: Analysis model and validation by the out-of-pile compression test,” Nucl. Technol., 136, p. 14-23 (2001).
    • (2001) Nucl. Technol. , vol.136 , pp. 14-23
    • Uwaba, T.1    Tanaka, K.2
  • 2
    • 0010744973 scopus 로고    scopus 로고
    • Thermal-hydraulic analysis of fast reactor fuel subassembly with porous blockages
    • Tokyo
    • H. Ohshima, H. Ninokata, “Thermal-hydraulic analysis of fast reactor fuel subassembly with porous blockages,” Proc. 4th Int. Semin. on Subchannel Analysis (ISSCA-4), Tokyo, p. 323-333 (1997).
    • (1997) Proc. 4Th Int. Semin. On Subchannel Analysis (ISSCA-4) , pp. 323-333
    • Ohshima, H.1    Ninokata, H.2
  • 3
    • 1642343783 scopus 로고    scopus 로고
    • Development of a fast breeder reactor fuel bundle deformation analysis code-BAMBOO: Development of a pin dispersion model and verification by the out-of pile compression test
    • T. Uwaba, M. Ito, S. Ukai, “Development of a fast breeder reactor fuel bundle deformation analysis code-BAMBOO: Development of a pin dispersion model and verification by the out-of pile compression test,” Nucl. Technol., 145, p. 230-237 (2004).
    • (2004) Nucl. Technol. , vol.145 , pp. 230-237
    • Uwaba, T.1    Ito, M.2    Ukai, S.3
  • 4
    • 0000647797 scopus 로고
    • M. Pelletier, The Swelling Behavior of Titanium Stabilized Austenitic Steels Used as Structural Materials of Fissile Subassemblies in Phenix
    • J. L. Seran, H. Touron, A. Maillard, P. Dubuisson, J. P. Hugot, E. Le Boulbin, P. Blanchard, M. Pelletier, The Swelling Behavior of Titanium Stabilized Austenitic Steels Used as Structural Materials of Fissile Subassemblies in Phenix, ASTM STP1046, p. 739-752 (1990).
    • (1990) ASTM STP1046 , pp. 739-752
    • Seran, J.L.1    Touron, H.2    Maillard, A.3    Dubuisson, P.4    Hugot, J.P.5    Le Boulbin, E.6    Blanchard, P.7
  • 5
    • 0027042837 scopus 로고
    • E. Le Boulbin, Behavior under Neutron Irradiation of the 15-15Ti and EM10 Steels Used as Standard Materials of the Phenix Fuel Subassembly
    • J. L. Seran, V. Levy, P. Dubuisson, D. Gilbon, A. Maillard, A. Fissolo, H. Touron, R. Cauvin, A. Chalony, E. Le Boulbin, Behavior under Neutron Irradiation of the 15-15Ti and EM10 Steels Used as Standard Materials of the Phenix Fuel Subassembly, ASTM STP1125, p. 1209-1233 (1992).
    • (1992) ASTM STP1125 , pp. 1209-1233
    • Seran, J.L.1    Levy, V.2    Dubuisson, P.3    Gilbon, D.4    Maillard, A.5    Fissolo, A.6    Touron, H.7    Cauvin, R.8    Chalony, A.9


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.