Program LATTICE for Calculation of Parameters of Targets with Heterogeneous (Lattice) Structure

Program LATTICE, with which help it is possible to describe lattice structure for the program complex CASCAD, is created in the C++ language. It is shown that for model-based electronuclear system on a basis of molten salt reactor with graphite moderator at transition from homogeneous structure to heterogeneous at preservation of a chemical compound there is a growth of k_{eff} by approximately 6 %

MonteCarlo Modeling of Parameters of a Subcritical Cascade Reactor Based on MSBR and LMFBR Technologies

Parameters of a subcritical cascade reactor driven by a proton accelerator and based on a primary leadbismuth target, main reactor constructed analogously to the molten salt breeder (MSBR) reactor core and a boosterreactor analogous to the core of the BN350 liquid metal cooled fast breeder reactor (LMFBR). It is shown by means of MonteCarlo modeling that the reactor under study provides safe operation modes (k_{eff}=0.940.98), is apable to transmute effectively radioactive nuclear waste and reduces by an order of magnitude the requirements on the accelerator beam current. Calculations show that the maximal neutron flux in the thermal zone is 10^{14} cm^{12}\cdot s^_{1}, in the fast booster zone is 5.12\cdot10^{15} cm^{12}\cdot s{1} at k_{eff}=0.98 and proton beam current I=2.1 mA

Monte Carlo Modeling Electronuclear Processes in Cascade Subcritical Reactor

Accelerator driven subcritical cascade reactor composed of the main thermal neutron reactor constructed analogous to the core of the VVER1000 reactor and a boosterreactor, which is constructed similar to the core of the BN350 fast breeder reactor, is taken as a model example. It is shown by means of Monte Carlo calculations that such system is a safe energy source (k_{eff}=0.940.98) and it is capable of transmuting produced radioactive wastes (neutron flux density in the thermal zone is PHI^{max} (r,z)=10^{14} n/(cm^{2} s^{1}), neutron flux in the fast zone is respectively equal PHI^{max} (r,z)=2.25 cdot 10^{15} n/(cm^{2} s^{1}) if the beam current of the proton accelerator is k_{eff}=0.98 and I=5.3 mA). Suggested configuration of the "cascade" reactor system essentially reduces the requirements on the proton accelerator current

The Application of the TRANSURANUS Fuel Performance Code to WWER Fuel: An Overview

The present review paper outlines the collaborative efforts for the establishment of the TRANSURANUS version for the simulation of VVER fuel pin behavior, which has been presented at this series of international conferences organized by the INRNE since 1994. The paper therefore starts with very briefly reviewing the development of the TRANSURANUS fuel performance code in collaboration with various organizations from EU member states operating VVER reactors. The development started with the application to normal operating conditions in the frame of different bilateral agreements supported by the European Commission and the IAEA (e.g. PHARE and PECO projects), followed by the specific project dedicated to its application to the loss of coolant type accidents (EXTRA). In the second part of the paper, a summary will be given of the verification, validation and benchmarking efforts, on the basis of the experimental data included in the IFPE database of the NEA, as well as in the frame of the co-ordinated research projects of the IAEA (e.g. FUMEX, FUMAC), and most recently also the Euratom project ESSANUF co-ordinated by Westinghouse Electric Sweden. Finally, we will outline the current plans for further improving the simulation capabilities of VVER fuels by means of TRANSURANUS