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Volumn 240, Issue 7, 2010, Pages 1714-1727

Synopsis and outcome of the QUENCH experimental program

Author keywords

[No Author keywords available]

Indexed keywords

ANALYTICAL DATA; CHEMICAL REDUCTION; CLADDING ALLOYS; CLADDING MATERIAL; CODE SYSTEM; DEBRIS COOLABILITY; DEGRADATION MECHANISM; EXPERIMENTAL PROGRAM; FUEL RODS; HYDROGEN ABSORPTION; HYDROGEN DISTRIBUTION; LARGE BREAK LOSS OF COOLANT ACCIDENTS; LOW TEMPERATURES; NEUTRON ABSORBER MATERIAL; NONDESTRUCTIVE METHODS; ORDERS OF MAGNITUDE; OXIDATION KINETICS; PRE-OXIDATION; PROTECTIVE OXIDES; QUENCH PROGRAMS; RESEARCH CENTER; RESEARCH PROGRAMS; SEVERE ACCIDENT; STEAM STARVATION; TEMPERATURE BOUNDARY; TEMPERATURE EXCURSIONS; TEMPERATURE RANGE; TEST PROGRAM; ZIRCALOY-4;

EID: 77955308193     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.nucengdes.2010.03.021     Document Type: Article
Times cited : (134)

References (62)
  • 1
    • 19944426202 scopus 로고    scopus 로고
    • Core loss during severe accident (COLOSS)
    • B. Adroguer Core loss during severe accident (COLOSS) Nucl. Eng. Design 235 2005 173
    • (2005) Nucl. Eng. Design , vol.235 , pp. 173
    • Adroguer, B.1
  • 2
    • 77955303551 scopus 로고    scopus 로고
    • A. Amri, B. Clement, OECD/NEA Headquarters, Issy-les-Moulineaux, France, 12-14 October
    • A. Amri, B. Clement, Joint OECD/NEA-EC/SARNET2 Workshop on In-Vessel Coolability OECD/NEA Headquarters, Issy-les-Moulineaux, France, 12-14 October 2009 (CDROM)
    • (2009) Joint OECD/NEA-EC/SARNET2 Workshop on In-Vessel Coolability
  • 4
    • 0024707768 scopus 로고
    • A scenario of the three mile island unit 2 accident
    • J.M. Broughton, P. Kuan, and D.S. Petti A scenario of the three mile island unit 2 accident Nucl. Technol. 87 1989 34
    • (1989) Nucl. Technol. , vol.87 , pp. 34
    • Broughton, J.M.1    Kuan, P.2    Petti, D.S.3
  • 5
    • 19244368145 scopus 로고    scopus 로고
    • LWR Severe accident simulation: Synthesis of the results and interpretation of the first Phebus FP experiment FPT 0
    • B. Clement LWR Severe accident simulation: synthesis of the results and interpretation of the first Phebus FP experiment FPT 0 Nucl. Eng. Design 226 2003 5 82
    • (2003) Nucl. Eng. Design , vol.226 , pp. 5-82
    • Clement, B.1
  • 6
    • 0026714213 scopus 로고
    • Hydrogen generation behaviour in the LOFT FP-2 and other experiments: Comparative assessment for migrated severe accident conditions
    • A.W. Cronenberg Hydrogen generation behaviour in the LOFT FP-2 and other experiments: comparative assessment for migrated severe accident conditions Nucl. Technol. 97 1992 97 112
    • (1992) Nucl. Technol. , vol.97 , pp. 97-112
    • Cronenberg, A.W.1
  • 7
    • 39549092299 scopus 로고    scopus 로고
    • Investigation of boron carbide oxidation for nuclear reactor safety: Experiments in highly oxidising conditions
    • C. Dominguez, N. Cocuaud, D. Drouan, A. Constant, and D. Jacquemain Investigation of boron carbide oxidation for nuclear reactor safety: experiments in highly oxidising conditions J. Nucl. Mater. 374 2008 473 481
    • (2008) J. Nucl. Mater. , vol.374 , pp. 473-481
    • Dominguez, C.1    Cocuaud, N.2    Drouan, D.3    Constant, A.4    Jacquemain, D.5
  • 8
    • 49549119550 scopus 로고    scopus 로고
    • Kinetics of hydrogen absorption and release in zirconium alloys during steam oxidation
    • M. Grosse, M. Steinbrück, E. Lehmann, and P. Vontobel Kinetics of hydrogen absorption and release in zirconium alloys during steam oxidation Oxid. Met. 70 2008 149 162
    • (2008) Oxid. Met. , vol.70 , pp. 149-162
    • Grosse, M.1    Steinbrück, M.2    Lehmann, E.3    Vontobel, P.4
  • 10
    • 61749094227 scopus 로고    scopus 로고
    • Influence of oxide layer morphology on hydrogen concentration in tin and niobium containing zirconium alloys after high temperature steam oxidation
    • M. Große, E. Lehmann, M. Steinbrück, G. Kühne, and J. Stuckert Influence of oxide layer morphology on hydrogen concentration in tin and niobium containing zirconium alloys after high temperature steam oxidation J. Nucl. Mater. 385 2009 339 345
    • (2009) J. Nucl. Mater. , vol.385 , pp. 339-345
    • Große, M.1    Lehmann, E.2    Steinbrück, M.3    Kühne, G.4    Stuckert, J.5
  • 15
    • 36348974141 scopus 로고    scopus 로고
    • Degraded core reflood: Present understanding based on experimental and analytical database and its impact on LWRs
    • W. Hering, and C. Homann Degraded core reflood: present understanding based on experimental and analytical database and its impact on LWRs Nucl. Eng. Design 237 2007 2315 2321
    • (2007) Nucl. Eng. Design , vol.237 , pp. 2315-2321
    • Hering, W.1    Homann, C.2
  • 17
    • 77955309598 scopus 로고    scopus 로고
    • Status of experimental and analytical investigations on degraded core reflood
    • Issy-les-Moulineaux, F, October 12-14, 2009
    • W. Hering, C. Homann, and W. Tromm Status of experimental and analytical investigations on degraded core reflood NEA/SARNET2 Workshop on In-Vessel Coolability Issy-les-Moulineaux, F, October 12-14, 2009 2009
    • (2009) NEA/SARNET2 Workshop on In-vessel Coolability
    • Hering, W.1    Homann, C.2    Tromm, W.3
  • 18
    • 0031168048 scopus 로고    scopus 로고
    • Chemical-physical behaviour of light water reactor core components tested under severe reactor accident conditions in the CORA facility
    • P. Hofmann, S. Hagen, V. Noack, G. Schanz, and L. Sepold Chemical-physical behaviour of light water reactor core components tested under severe reactor accident conditions in the CORA facility Nucl. Technol. 118 1997 200
    • (1997) Nucl. Technol. , vol.118 , pp. 200
    • Hofmann, P.1    Hagen, S.2    Noack, V.3    Schanz, G.4    Sepold, L.5
  • 26
    • 75449094600 scopus 로고    scopus 로고
    • Aerosol behavior during SIC control rod failure in QUENCH-13 test
    • T. Lind, A. Pintér, I. Nagy, and J. Stuckert Aerosol behavior during SIC control rod failure in QUENCH-13 test J. Nucl. Mater. 397 2010 92 100
    • (2010) J. Nucl. Mater. , vol.397 , pp. 92-100
    • Lind, T.1    Pintér, A.2    Nagy, I.3    Stuckert, J.4
  • 28
    • 84885240631 scopus 로고    scopus 로고
    • The PARAMETER test series
    • Nesseber, Bulgaria, 23-25 September
    • V. Nalivaev The PARAMETER test series ERMSAR-2008 Nesseber, Bulgaria, 23-25 September 2008
    • (2008) ERMSAR-2008
    • Nalivaev, V.1
  • 30
    • 70450225477 scopus 로고    scopus 로고
    • 4C oxidation modeling in severe accident codes: Application to PHEBUS and QUENCH experiments
    • 4C oxidation modeling in severe accident codes: application to PHEBUS and QUENCH experiments Progr. Nucl. Energy 52 2010 37 45
    • (2010) Progr. Nucl. Energy , vol.52 , pp. 37-45
    • Repetto, G.1
  • 32
    • 40449141452 scopus 로고    scopus 로고
    • Investigations on boron carbide oxidation for nuclear reactors safety - general modelling for ICARE/CATHARE code applications
    • N. Seiler, F. Bertrand, O. Marchand, G. Repetto, and S. Ederli Investigations on boron carbide oxidation for nuclear reactors safety - general modelling for ICARE/CATHARE code applications Nucl. Eng. Design 238 2008 820 836
    • (2008) Nucl. Eng. Design , vol.238 , pp. 820-836
    • Seiler, N.1    Bertrand, F.2    Marchand, O.3    Repetto, G.4    Ederli, S.5
  • 37
    • 35348895611 scopus 로고    scopus 로고
    • Severe fuel damage experiments performed in the QUENCH facility with 21-rod bundles of LWR-type
    • L. Sepold, W. Hering, G. Schanz, W. Scholtyssek, M. Steinbrück, and J. Stuckert Severe fuel damage experiments performed in the QUENCH facility with 21-rod bundles of LWR-type Nucl. Eng. Design 237 2007 2157 2164
    • (2007) Nucl. Eng. Design , vol.237 , pp. 2157-2164
    • Sepold, L.1    Hering, W.2    Schanz, G.3    Scholtyssek, W.4    Steinbrück, M.5    Stuckert, J.6
  • 38
    • 70249091505 scopus 로고    scopus 로고
    • Severe fuel damage experiments with advanced cladding materials to be performed in the QUENCH facility (QUENCH-ACM)
    • Orlando, Fla., May 11-15, 2008, Paper ICONE16-48074 ASME New York, NY
    • L. Sepold, M. Große, M. Steinbrück, and J. Stuckert Severe fuel damage experiments with advanced cladding materials to be performed in the QUENCH facility (QUENCH-ACM) Proc. of the 16th Internat. Conf. on Nuclear Engineering (ICONE-16) Orlando, Fla., May 11-15, 2008, Paper ICONE16-48074 2008 ASME New York, NY ISBN 0-7918-3820-X
    • (2008) Proc. of the 16th Internat. Conf. on Nuclear Engineering (ICONE-16)
    • Sepold, L.1    Große, M.2    Steinbrück, M.3    Stuckert, J.4
  • 45
    • 3342949520 scopus 로고    scopus 로고
    • Hydrogen absorption by zirconium alloys at high temperatures
    • M. Steinbrück Hydrogen absorption by zirconium alloys at high temperatures J. Nucl. Mater. 334 2004 58 64
    • (2004) J. Nucl. Mater. , vol.334 , pp. 58-64
    • Steinbrück, M.1
  • 49
    • 12344331617 scopus 로고    scopus 로고
    • Oxidation of boron carbide at high temperatures
    • M. Steinbrück Oxidation of boron carbide at high temperatures J. Nucl. Mater. 336 2005 185
    • (2005) J. Nucl. Mater. , vol.336 , pp. 185
    • Steinbrück, M.1
  • 52
    • 70349959748 scopus 로고    scopus 로고
    • Single-rod experiments on failure of SIC control rods
    • Forschungszentrum Karlsruhe, 20-22 November 2007
    • M. Steinbrück, M. Große, and U. Stegmaier Single-rod experiments on failure of SIC control rods 13th Int. QUENCH Workshop Forschungszentrum Karlsruhe, 20-22 November 2007 2007 ISBN 978-3-923704-63-7
    • (2007) 13th Int. QUENCH Workshop
    • Steinbrück, M.1    Große, M.2    Stegmaier, U.3
  • 53
    • 59849123820 scopus 로고    scopus 로고
    • Oxidation of zirconium alloys in oxygen at high temperatures up to 1600 °C
    • M. Steinbrück Oxidation of zirconium alloys in oxygen at high temperatures up to 1600 °C Oxid. Met. 70 2008 317 329
    • (2008) Oxid. Met. , vol.70 , pp. 317-329
    • Steinbrück, M.1
  • 54
    • 67650999149 scopus 로고    scopus 로고
    • Prototypical experiments relating to air oxidation of Zircaloy-4 at high temperatures
    • M. Steinbrück Prototypical experiments relating to air oxidation of Zircaloy-4 at high temperatures J. Nucl. Mater. 392 2009 531 544
    • (2009) J. Nucl. Mater. , vol.392 , pp. 531-544
    • Steinbrück, M.1
  • 55
    • 70450252204 scopus 로고    scopus 로고
    • High-temperature oxidation and quench behaviour of Zircaloy-4 and E110 cladding alloys
    • M. Steinbrück High-temperature oxidation and quench behaviour of Zircaloy-4 and E110 cladding alloys Progr. Nucl. Energy 52 2010 19 36
    • (2010) Progr. Nucl. Energy , vol.52 , pp. 19-36
    • Steinbrück, M.1
  • 60
    • 0032099886 scopus 로고    scopus 로고
    • Modelling of hydrogen absorption by zirconium alloys during high temperature oxidation in steam
    • M.S. Veshchunov, and A.V. Berdyshev Modelling of hydrogen absorption by zirconium alloys during high temperature oxidation in steam J. Nucl. Mater. 255 1998 250 262
    • (1998) J. Nucl. Mater. , vol.255 , pp. 250-262
    • Veshchunov, M.S.1    Berdyshev, A.V.2
  • 62
    • 48149112783 scopus 로고    scopus 로고
    • Application of mechanistic criteria of cladding oxide shell failure to the analysis of core degradation simulated in bundle meltdown tests
    • M.S. Veshchunov, A.V. Boldyrev, and B. Toth Application of mechanistic criteria of cladding oxide shell failure to the analysis of core degradation simulated in bundle meltdown tests Nucl. Eng. Design 238 2008 2219 2229
    • (2008) Nucl. Eng. Design , vol.238 , pp. 2219-2229
    • Veshchunov, M.S.1    Boldyrev, A.V.2    Toth, B.3


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