Conveners
6.3 Neutronics - 1
- Andrei Rineiski (Karlsruhe Institute of Technology (KIT))
- Dmitry KLINOV (IPPE)
Prof.
Gerald Rimpault
(CEA)
27/06/2017, 10:20
Track 6. Test Reactors, Experiments and Modeling and Simulations
ORAL
ASTRID (Advanced Sodium Technological Reactor for Industrial Demonstration) is a Sodium Fast Reactor design that will be France's Flagship 4th Generation Reactor.
Its innovative core contains many axial and radial heterogeneities (in order to obtain a negative void coefficient) and interfaces that are challenging for current deterministic codes to simulate correctly. Hence there is the need...
Ms
Olga Andrianova
(IPPE JSC “SSC RF –IPPE”, 1, Bondarenko sq., Obninsk, Kaluga reg. 249033)
27/06/2017, 10:40
Track 6. Test Reactors, Experiments and Modeling and Simulations
ORAL
The paper presents the results of a computational and experimental analysis of a systematized and revised series of experiments carried out between 1990-2013 on measurements of absolute fission rate of minor actinides (from 237Np to 245Cm) in different neutron spectra at the BFS-1,2 facilities. A total of 25 critical configurations, i.e., reactor core models with different fuels and coolants...
Mr
Vyacheslav Pershukov
(ROSATOM)
27/06/2017, 11:00
Track 6. Test Reactors, Experiments and Modeling and Simulations
ORAL
This report intended to provide an update on the International research center (IRC) based on the fast sodium research reactor MBIR development. The report will include the proposed IRC structure, key terms of participation, proposed areas for multilateral research, etc. It will also present the R&D possibilities that IRC members will have on the closed nuclear fuel cycle due to the...
Dr
Armando Miguel Gomez Torres
(Instituto Nacional de Investigaciones Nucleares)
27/06/2017, 11:20
Track 6. Test Reactors, Experiments and Modeling and Simulations
ORAL
AZNHEX is a neutron diffusion code for hexagonal-z geometry currently under development as part of the AZTLAN project in which a Mexican platform for nuclear core simulations is being developed. The diffusion solver is based on the RTN0 (Raviart-Thomas-Nédélec of index 0) nodal finite element method together with the Gordon-Hall transfinite interpolation which is used to convert, in the radial...
Dr
Tatiana Ivanova
(OECD Nuclear Energy Agency)
27/06/2017, 11:40
Track 6. Test Reactors, Experiments and Modeling and Simulations
ORAL
Historic measurements of actinide samples in the Dounreay Prototype Fast Reactor (PFR) are of interest for modern nuclear data and simulation validation. Samples of uranium, neptunium, plutonium, americium, curium, and californium isotopes were irradiated for 492 effective full-power days and radiochemically assayed at Oak Ridge National Laboratory (ORNL) and Japan Atomic Energy Agency...
