Behavior of Zr 1%Nb fuel cladding under accident conditions

American Nuclear Society - 2007 LWR Fuel Performance/Top Fuel

Volumn , Issue , 2007, Pages 536-542

  Perez Fero E ^a   Hozer Z ^a   Windberg, P ^a   Nagy, I ^a   Vimi, A ^a   Ver N ^a   Matus, L ^a   Kunstar M ^a   Novotny, T ^a   Horvath M ^a   Gyori, Cs ^b  

^a KFKI ATOMIC ENERGY RESEARCH INSTITUTE   (Hungary)

^b JOINT RESEARCH CENTRE   (Italy)

Author keywords

[No Author keywords available]

Indexed keywords

BIODEGRADATION; CESIUM; CHEMICAL OXYGEN DEMAND; EMBRITTLEMENT; EXPERIMENTS; FUELS; HYDROGEN; HYDROGEN EMBRITTLEMENT; LIGHT WATER REACTORS; MICROFLUIDICS; MULTITASKING; NIOBIUM; NONMETALS; OXIDATION; QUENCHING; REACTOR CORES; ROUGHNESS MEASUREMENT; STEAM; SULFATE MINERALS; TANKS (CONTAINERS); TESTING; ZIRCONIUM;

(I ,J) CONDITIONS; ACCIDENT CONDITIONS; BRITTLE TRANSITIONS; CLEANING TANK INCIDENT (CTI); CORE DEGRADATION; FUEL CLADDING; FUEL PERFORMANCE; HIGH-TEMPERATURE OXIDATION; HYDROGEN UPTAKE; IN ORDER; INTERNATIONAL (CO); LARGE SCALE TESTING; ROD BUNDLES; SMALL SCALE TESTING; TEST PROGRAMME;

CLADDING (COATING);

EID: 44949185319     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper

References (9)

1. CS. GYORI, M Horváth, Z. Hózer, L. Matus, I. Nagy, O. Prokopiev and P. Windberg: "Experimental Database of Zr1 %Nb Cladding Alloy for Model Development and Code Validation;" EVOL-EXTRAD-1 (August 2002).
2. Z. HÓZER, Cs. Gyori: "Derivation of LOCA Ductility Limit from AEKI Ring Compression Tests," SEGFSM Topical Meeting on LOCA Issues, ANL (May 2004).
3. CS. GYORI, P. Van Uffelen, A. Schubert and J. van de Laar, Z. Hózer: "Implementing Experimental Data on the Accidental Behaviour of the WWER Cladding obtained at the AEKI in the TRANSURANUS Fuel Performance Code," 6th Int. Conf. on WWER Fuel Performance, Modelling and Experimental Support, Albena (September 2005).
4. CS. GYORI, Z. Hózer, K. Lassmann, A. Schubert, J. van de Laar, M. Cvan, B. Hatala: "Extension of the TRANSURANUS Code Applicability with Niobium Containing Cladding Models (EXTRA);" FISA 2003: Symposium on EU Research in Reactor Safety, Luxembourg, (November 2003). Proceedings p. 589-594.
5. Z. HÓZER et al.: Experimental Database of E110 Cladding Oxidised in Hydrogen Rich Steam; Int. Meet, on LWR Fuel Performance, "Nuclear fuel: addressing the future", Topfuel, Salamanca, Spain, 22-27 Oct, 2006.
6. Event Report to OAH-NBI, B20301, Paks, 2003.
7. M. MOALEM, D. R. Olander: Oxidation of Zircaloy by Steam; Journal of Nuclear Materials v. 182 (1991), p. 170-194.
8. th International Symposium on Zirconium in the Nuclear Industry, 1982, ASTM 04-824000-35.
9. YEON soo Kim et al.: High Pressure Oxidation of Sponge-Zr in Steam/Hydrogen Mixtures; Journal of Nuclear Materials v. 245 (1997), p. 152-160.