LEADER 02926nam 22004453 450 001 9911026174603321 005 20240309060216.0 010 $a9789201086242 010 $a9201086245 035 $a(MiAaPQ)EBC31201349 035 $a(Au-PeEL)EBL31201349 035 $a(OCoLC)1425790970 035 $a(CKB)30788147800041 035 $a(BIP)108295415 035 $a(BIP)110223901 035 $a(EXLCZ)9930788147800041 100 $a20240309d2024 uy 0 101 0 $aeng 135 $aurcnu|||||||| 181 $ctxt$2rdacontent 182 $cc$2rdamedia 183 $acr$2rdacarrier 200 10$aAdvancing the State of the Practice in Uncertainty and Sensitivity Methodologies for Severe Accident Analysis in Water Cooled Reactors in the QUENCH-06 Experiment $eFinal Report of a Coordinated Research Project 205 $a1st ed. 210 1$aVienna :$cInternational Atomic Energy Agency,$d2024. 210 4$d©2024. 215 $a1 online resource (142 pages) 225 1 $aIAEA TECDOC Series No Series ;$vv.2045 311 08$a9789201085245 311 08$a9201085249 330 $aThe IAEA facilitated the co-operation on research and development among its Member States on the development and validation of computer codes for the design and safety analysis of nuclear power plants. The main objective of this effort was to bring together the current state-of­knowledge on uncertainty propagation in severe accident analyses that has been accumulated by experienced analysts with the aim of increasing the sophistication and competency of the practitioners in this field. This publication provides the contributions from four individual organizations from four Member States describing their employed uncertainty and sensitivity assessment methods applied in simulating the QUENCH-06 experiment performed at the Karlsruhe Institute of Technology (Germany) in December 2000. The QUENCH-06 experiment was designed to explore the behavior of nuclear fuel under oxidizing and quenching conditions during severe accident scenarios in light water nuclear reactors. Due to its comprehensive nature, this experiment was chosen as the benchmark for evaluating the performance of severe accident codes employed by participants in this coordinated research project. This publication is intended for nuclear engineers, researchers, code developers, experimentalists in nuclear energy fields, reactor vendors and developers, university professors and students, regulatory experts, and nuclear power plant planners. 410 0$aIAEA TECDOC Series No Series 700 $aIAEA$01594159 801 0$bMiAaPQ 801 1$bMiAaPQ 801 2$bMiAaPQ 906 $aBOOK 912 $a9911026174603321 996 $aAdvancing the State of the Practice in Uncertainty and Sensitivity Methodologies for Severe Accident Analysis in Water Cooled Reactors in the QUENCH-06 Experiment$94434785 997 $aUNINA