Conveners
6.4 Neutronics – 2
- Evgeny Seleznev (NUCLEAR SAFETY INSTITUTE OF RUSSIAN ACADEMY OF SCIENCES)
- Robert Jacqmin (CEA- Cadarache)
Dr
Branislav Vrban
(B&J NUCLEAR ltd.)
27/06/2017, 13:30
Track 6. Test Reactors, Experiments and Modeling and Simulations
ORAL
Under specific transients, fast reactor cores often show significant deviation in their power distribution which leads to spatial instability. As a quantitative indication of these decoupling characteristics, the λ-mode eigenvalue separation has been frequently employed. The physical interpretation of eigenvalue separation provides a measure of the spatial neutronic coupling among various...
Dr
Robert Jacqmin
(CEA, Cadarache)
27/06/2017, 13:50
Track 6. Test Reactors, Experiments and Modeling and Simulations
ORAL
As part of a bilateral agreement on the study of large axially-heterogeneous oxide-fueled SFR cores, CEA and IPPE have recently performed neutron physics experiments in the BFS facility. The configurations of interest are pancake-shape cores with a split fissile column and a sodium plenum, designed to favor a high inner plutonium conversion ratio and a low sodium void worth. Separate effect...
Mr
Xingkai Huo
(China Institute of Atomic Energy)
27/06/2017, 14:10
Track 6. Test Reactors, Experiments and Modeling and Simulations
ORAL
China Experimental Fast Reactor (abbr. CEFR) is a pool-type sodium-cooled fast reactor in China Institute of Atomic Energy (abbr. CIAE), with a thermal power of 65MW and an electric power of 20MW. The construction started in 2000 and the first criticality was reached in July 2010. On December 15th 2014, CEFR reached full power for the first time and was successfully operated for 72 hours....
Prof.
Claubia Pereira
(Universidade Federal de Minas Gerais)
27/06/2017, 14:30
Track 6. Test Reactors, Experiments and Modeling and Simulations
ORAL
A GFR core model with 100 MWt was evaluated using three different fuel compositions: conventional (U, Pu)C and two reprocessed fuels with transuranic (TRU) (Pu, Am, Np, Cm). One reprocessed by UREX+ technique and spiked with depleted uranium, (U,TRU)C, and the other reprocessed by the same technique but spiked with thorium, (Th,TRU)C. The reprocessed fuel came from a PWR standard fuel (33,000...
Prof.
EDMUNDO DEL VALLE GALLEGOS
(Instituto Nacional de Investigaciones Nucleares (On Sabbatical Leave from IPN-Mexico))
27/06/2017, 14:50
Track 6. Test Reactors, Experiments and Modeling and Simulations
ORAL
The AZTLAN Platform project is a Mexican national initiative led by the National Institute for Nuclear Research of Mexico, which brings together nuclear institutions of higher education in Mexico: the National Polytechnic Institute, the National Autonomous University of Mexico and the Autonomous Metropolitan University, in an effort to take a significant step towards positioning Mexico, in the...
