Radiation Damage in Fast Reactors
Fundamental Research on Radiation Damage Mechanisms for Application to Fast Breeder Reactors or Future Nuclear Fusion Reactors.
Tech Area / Field
8 Project completed
Senior Project Manager
Kurchatov Research Center / Institute of General and Nuclear Physics, Russia, Moscow
- VNIITF, Russia, Chelyabinsk reg., Snezhinsk
- Science University of Tokyo, Japan, Tokyo
Project summaryThe project is aimed at theoretical and experimental investigation of physical mechanisms of one of the most important effects defining radiation stability and thus the choice of the most perspective structural materials for the first wall of the future fusion reactors. The results of investigations can be used in order to prolong the lifetime of fission reactor constructions.
A model of swelling of structural materials under the effect of 14-MeV neutron irradiation is supposed to be developed, based on the models of radiation damage kinetics proposed and studied in RRC Kurchatov Institute. The model will take into account the effects of primary radiation damage (point defects, clusters) formation in collision cascades created by 14-MeV neutrons, the effect of crystal lattice type and the variation of chemical and phase composition under irradiation (new phase precipitation; the effect of gas atoms: helium, hydrogen; variations of dislocation density, etc.). The kinetics of some effects, such as the influence of precipitates and helium atoms on swelling, will be studied by computer simulation effect of swelling will be estimated and checked in simulation experiments with the help of the material sample irradiation with 60-MeV helium ions and 10-MeV protons on charged particleaccelerators and with up to 1 MeV electrons. The analysis of swelling willbe performed during subsequent structural investigations of irradiated samples by transmission electron microscopy (TEM).
The parameters to be varied during investigation are the irradiating particle type and energy, irradiation dose and temperature, the impurity and chemical composition of materials studied and the dislocation structure (by thermal-mechanical pretrearment). The effect of helium accumulation in materials will besimulated by the sample preimplantation with up to 60 MeV helium ion beam on a cyclotron. The subsequent irradiation of helium-free and helium-preimplanted samples with protons and fast electrons will allow to elucidate the effects of gas impurities (helium) and defect cluster formation in cascades on swelling in the broad range of irradiation doses (up to 10 displacements per atom (dpa) and temperatures (20 C < T < 700 C). The results of test experiments will be compared to those obtained under neutron irradiation.
The International Science and Technology Center (ISTC) is an intergovernmental organization connecting scientists from Kazakhstan, Armenia, Tajikistan, Kyrgyzstan, and Georgia with their peers and research organizations in the EU, Japan, Republic of Korea, Norway and the United States.
ISTC facilitates international science projects and assists the global scientific and business community to source and engage with CIS and Georgian institutes that develop or possess an excellence of scientific know-how.