Conveners
6.5 Uncertainty Analysis and Tools
- Gerald Rimpault (CEA)
- Arkadii Kiselev
Prof.
Augusto Gandini
(Sapienza University of Rome)
27/06/2017, 15:30
Track 6. Test Reactors, Experiments and Modeling and Simulations
ORAL
**Recent and potential advances of the Heuristically based Generalized Perturbation Theory (HGPT) methodology are discussed:**
- *The subcriticality monitoring method*
Basing on the HGPT methodology applied to subcritical systems, a procedure is described for the online monitoring of the subcriticality level of ADS reactors with minimal interaction with the plant normal operation.
The...
Prof.
Gerald Rimpault
(CEA)
27/06/2017, 15:50
Track 6. Test Reactors, Experiments and Modeling and Simulations
ORAL
The use of the Iterated Fission Probability method in the Monte Carlo code Tripoli4® gives credit to deterministic codes such as ERANOS for calculating βeff. The asset of Tripoli4® is the possibility to get a better representation of experimental cores, especially the R2 experimental core which exhibit more experimental canals for hosting large fission chambers. The BERENICE measurements...
Dr
Gennady Manturov
(PhD)
27/06/2017, 16:10
Track 6. Test Reactors, Experiments and Modeling and Simulations
ORAL
Designing of neutronics characteristics of fast reactor cores and fuel cycle requires to use certified and qualified sets of computer codes and nuclear data. The calculation codes should be related to the modern state of computational techniques. The used nuclear constants should be adequate to the most reliable evaluations, adopted in modern libraries of evaluated nuclear data.
The paper...
Jaeseok Heo
(Korea Atomic Energy Research Institute)
27/06/2017, 16:30
Track 6. Test Reactors, Experiments and Modeling and Simulations
ORAL
In this research, uncertainty analyses for multiple safety parameters were performed for Unprotected Loss of Flow (ULOF) for the Prototype Gen-IV Sodium-cooled Fast Reactor (PGSFR) by using the PArallel Computing Platform IntegRated for Uncertainty and Sensitivity analysis (PAPIRUS). The objective of the global uncertainty analysis is to evaluate all safety parameters of the system in the...
Prof.
Gerald Rimpault
(CEA)
27/06/2017, 16:50
Track 6. Test Reactors, Experiments and Modeling and Simulations
ORAL
An OECD/NEA sub-group on Uncertainty Analysis in Modelling (UAM) for Design, Operation and Safety Analysis of Sodium-cooled Fast Reactors (SFR-UAM) has been formed under the NSC/WPRS/EGUAM and is currently undertaking preliminary studies after having specified a series of benchmarks.
The incentive for launching the SFR-UAM task force comes from the desire to utilize current understanding of...
