DYN3D is an best estimate advanced code for the three-dimensional simulation of steady-states and transients in light water reactor cores with quadratic and hexagonal fuel assemblies. Burnup and poison-dynamic calculations can be performed. For the investigation of wide range transients, DYN3D is coupled with system codes as ATHLET and RELAP5. The neutron kinetic model is based on the solution of the three-dimensional two-group neutron diffusion equation by nodal expansion methods. The thermal-hydraulics comprises a one- or two-phase coolant flow model on the basis of four differential balance equations for mass, energy and momentum of the two-phase mixture and the mass balance for the vapour phase. Various cross section libraries are linked with DYN3D. Systematic code validation is performed by FZR and independent organizations.

Dans le cadre des études neutroniques d'innovation sur les cœurs de Réacteurs à Eau légère Pressurisée (REP) de 3ème génération, la recherche de l'économie des ressources naturelles est fondamentale afin de pérenniser la filière électronucléaire. Cette étude consiste à rechercher l'économie des ressources par la conception de cœurs de réacteurs à hauts facteurs de conversion, s'appuyant sur des combustibles oxydes mixtes à base de thorium / uranium / plutonium, ainsi que d'élaborer des stratégies de multi-recyclage des matières fissiles (plutonium et 233U). La démarche s'est déroulée en quatre étapes. Deux domaines d'étude ont tout d'abord été identifiés, le premier concerne les faibles rapports de modération (RM) et un combustible ThPuO2, le second les RM standards à accrus et un combustible ThUO2. La première voie a conduit à l'étude de Réacteurs Sous-Modérés (RSM) selon les critères de production d'233U accrue et de consommation limitée de plutonium. Deux concepts ont été retenus en particulier, à partir desquels des stratégies de multi-recyclage des matières fissiles ont été élaborées. La production et le recyclage de l'233U exclusivement en RSM limitent l'économie annuelle d'Unat à 30% environ. Il a été mis en évidence que le besoin en plutonium des RSM producteurs d'233U est le facteur limitant. C'est pourquoi un dernier chapitre évalue comment la production d'233U au sein de REP, dès 2020, permet de favoriser la transition vers un cycle symbiotique REP/RSM en relâchant la contrainte sur les inventaires de plutonium. Cette stratégie laisse présager une économie annuelle de l'ordre de 65% d'Unat par rapport à la poursuite du mono-recyclage du MOX en REP. / Within the framework of innovative neutronic conception of Pressurized Light Water Reactors (PWR) of 3rd generation, saving of natural resources is of paramount importance for sustainable nuclear energy production. This study consists in the one hand to design high Conversion Reactors exploiting mixed oxide fuels composed of thorium / uranium / plutonium, and in the other hand, to elaborate multirecycling strategies of both plutonium and 233U, in order to maximize natural resources economy. This study has two main objectives: first the design of High Conversion PWR (HCPWR) with mixed oxide fuels composed of thorium / uranium / plutonium, and secondly the setting up of multirecycling strategies of both plutonium and 233U, to better natural resources economy. The approach took place in four stages. Two ways of introducing thorium into PWR have been identified: the first is with low moderator to fuel volume ratios (MR) and ThPuO2 fuel, and the second is with standard or high MR and ThUO2 fuel. The first way led to the design of under-moderated HCPWR following the criteria of high 233U production and low plutonium consumption. This second step came up with two specific concepts, from which multirecycling strategies have been elaborated. The exclusive production and recycling of 233U inside HCPWR limits the annual economy of natural uranium to approximately 30%. It was brought to light that the strong need in plutonium in the HCPWR dedicated to 233U production is the limiting factor. That is why it was eventually proposed to study how the production of 233U within PWR (with standard MR), from 2020. It was shown that the anticipated production of 233U in dedicated PWR relaxes the constraint on plutonium inventories and favours the transition toward a symbiotic reactor fleet composed of both PWR and HCPWR loaded with thorium fuel. This strategy is more adapted and leads to an annual economy of natural uranium of about 65%.

DYN3D is an best estimate advanced code for the three-dimensional simulation of steady-states and transients in light water reactor cores with quadratic and hexagonal fuel assemblies. Burnup and poison-dynamic calculations can be performed. For the investigation of wide range transients, DYN3D is coupled with system codes as ATHLET and RELAP5. The neutron kinetic model is based on the solution of the three-dimensional two-group neutron diffusion equation by nodal expansion methods. The thermal-hydraulics comprises a one- or two-phase coolant flow model on the basis of four differential balance equations for mass, energy and momentum of the two-phase mixture and the mass balance for the vapour phase. Various cross section libraries are linked with DYN3D. Systematic code validation is performed by FZR and independent organizations.

The nuclear industry has long relied upon bounding parametric analyses in predicting the safety margins of reactor designs undergoing design-basis accidents. These methods have been known to return highly-conservative results, limiting the operating conditions of the reactor. The Best-Estimate Plus Uncertainty (BEPU) method using a modernized version of the Code-Scaling, Applicability, and Uncertainty (CSAU) methodology has been applied to more accurately predict the safety margins of the Oregon State University Advanced Plant Experiment (APEX) facility experiencing a Loss-of-Feedwater Accident (LOFA). The statistical advantages of the Bayesian paradigm of probability was utilized to incorporate prior knowledge when determining the analysis required to justify the safety margins. RELAP5 Mod 3.3 was used to accurately predict the thermal-hydraulics of a primary Feed-and-Bleed response to the accident using assumptions to accompany the lumped-parameter calculation approach. A novel coupling of thermal-hydraulic and statistical software was accomplished using the Symbolic Nuclear Analysis Package (SNAP). Uncertainty in Peak Cladding Temperature (PCT) was calculated at the 95/95 probability/confidence levels under a series of four separate sensitivity studies. / Graduation date: 2013