Core loss during a severe accident (COLOSS)

Nuclear Engineering and Design

Volumn 221, Issue 1-3 SPEC., 2003, Pages 55-76

  Adroguer, B ^a   Chatelard, P ^a   Van Dorsselaere, J P ^a   Duriez, C ^a   Cocuaud, N ^a   Bellenfant, L ^a   Bottomley, D ^b   Vrtilkova, V ^c   Mueller, K ^b   Hering, W ^d   Homann, C ^d   Krauss, W ^d   Miassoedov, A ^d   Steinbruck M ^d   Stuckert, J ^d   Hozer, Z ^e   Bandini, G ^f   Birchley, J ^g   Berlepsch, T V ^h   Buck, M ⁱ   Benitez, J A F ^j   Virtanen, E ^k   Marguet, S ^l   Azarian, G ^m   Plank, H ⁿ   Veshchunov, M ^o   Zvonarev, Y ^p   Goryachev, A ^q   more..

^a INSTITUT DE RADIOPROTECTION ET DE SÛRETÉ NUCLÉAIRE IRSN   (France)

^b JOINT RESEARCH CENTRE   (Italy)

^c UJP Prague   (Czech Republic)

^d KARLSRUHE INSTITUTE OF TECHNOLOGY   (Germany)

^e AEKI   (Hungary)

^f ENEA   (Italy)

^g PAUL SCHERRER INSTITUTE   (Switzerland)

^h RUHR UNIVERSITY BOCHUM   (Germany)

ⁱ Germany   (Germany)

^j UNIVERSIDAD POLITÉCNICA DE MADRID   (Spain)

^k LTKK Uv   (Finland)

^l EDF R AND D   (France)

^m AREVA NP   (France)

ⁿ FRAMATOME ANP GMBH   (Germany)

^o NUCLEAR SAFETY INSTITUTE   (Russian Federation)

^p NSI   (Russian Federation)

^q RESEARCH INSTITUTE OF ATOMIC REACTORS   (Russian Federation)

more..

Author keywords

Boron carbide; Core degradation; Fuel dissolution; Modelling; Oxidation of Zr rich mixtures; Plant calculations

Indexed keywords

BORON CARBIDE; DEGRADATION; DISSOLUTION; NUCLEAR FUELS; OXIDATION;

PLANT CALCULATIONS;

REACTOR CORES;

EID: 0037375598     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0029-5493(02)00344-8     Document Type: Conference Paper

References (11)

1. Adroguer, B., et al., 1999. In: Proceedings of the CIT project on the Corium Interactions and Thermochemistry in FISA-99 Symposium, EUR 19532 EN. Luxembourg, November 1999.
2. Adroguer, B., et al., 2000. Status Report on Dissolution of Fuel Rods and Related Effects, CIT project, INV-CIT(99)-D004, July 2000.
3. Allelein, H.J., et al., 2001. European Validation of the Integral Code ASTEC (EVITA), FISA 01, Lux., November 2001.
4. 4C-filled control rod segments above 1000°C under transient conditions. ICONE-2184, May 1997.
5. Clément, B., Repetto, G., 2000. Survey of FPT3 objectives and pre-test analyses. In: Proceedings of the Fourthth Technical Seminar on the Phébus FP Programme. Marseille, 20-22 March 2000.
6. Firnhaber, M., et al., 1993. OECD/NEA CSNI International Standard Problem No 31: CORA-13 Experiment on Severe Fuel Damage. Comparison Report, NEA/CSNI/R(93°17, July 1993).
7. 2 Dissolution by Molten Zry. New Experimental Results and Modelling. Report FZKA 6379, INV-CIT(99)-P029, Karlsruhe, Germany.
8. Hering, W., et al., 2002. Comparison and Interpretation Report of the OECD International Standard, Problem No. 45. Exercise (QUENCH-06), FZKA 6722, June 2002.
9. Miassoedov, A., et al., 2000. Results of the QUENCH-07 Experiment. In: Proceedings of the 10th International Conference on Nuclear Engineering, ICONE10-22137. Arlington, VA, April 2000.
10. Prater, J.T., Courtright, E.L., 1987. Properties of Reactor Fuel Rod Materials at High Temperatures. NUREG/CR-4891.
11. Shepherd, I., et al., 1999. In: Proceedings of the FISA-99 Symposium on the Investigation of Core Degradation on COBE project, EUR 19532 EN. Luxembourg, November 1999.