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Iaea-tecdoc-1450
Iaea-tecdoc-1450












iaea-tecdoc-1450

Experiments have been made on power reactors that were successfully operated using ThO 2-UO 2 fuel in light water reactors (LWRs). Thorium is made up mainly of “fertile” isotope ( 232Th). In fact, thorium is three times more abundant than uranium, and the feasibility of loading the core with thorium uranium fuel was carried out. The reactor includes international safety standards with evolutionary design improvement in the areas of fuel technology, modularized construction, safety systems, and standardized designs. The core is filled with 163 enriched uranium (UO 2) fuel assemblies (FAs). The VVER-1000 is a 3000 MW thermal power nuclear power plant which is cooled and moderated by light water.

iaea-tecdoc-1450

The VVER-1200 is the predecessor of the VVER-1000 reactor. IntroductionĬountries are building nuclear power plants to meet their energy needs the site of nuclear power plant in Egypt is El Dabaa. Results indicated that thorium has lower production of minor actinides (MAs) and transuranic elements (mainly plutonium isotopes) compared with the relatively large amounts produced from the uranium-based fuel UO 2.

iaea-tecdoc-1450

The moderator temperature coefficients of the uranium-thorium core are found to be higher than those of the uranium core. It is found that the core loaded with uranium and thorium has lower delayed neutron fraction than the uranium oxide core. β eff and the Doppler coefficient (DC) are found to be in agreement with the design values. The calculations determine the delayed neutron fraction β eff, the temperature reactivity coefficients, the fuel consumption, and the production of the transuranic elements during reactor operation. The reference core was initially filled with enriched uranium oxide fuel and then fueled with uranium-thorium fuel. The effect of thorium introduction on the neutronic parameters of the VVER-1000 reactor was discussed. In this paper, neutronic calculations and the core analysis of the VVER-1000 reactor were performed using MCNP6 code together with both ENDF/B-VII.1 and ENDF/B-VIII libraries.














Iaea-tecdoc-1450