Perspectives on Thorium Fuel Cycle Study
نویسندگان
چکیده
منابع مشابه
Study of thorium advanced fuel cycle utilization in light water reactor VVER-440
The first step in investigation of thorium fuel is evaluation of the results obtained from the spectral code for this type of fuel. The benchmark summarized by IAEA in 2003 was used for partial validation of the code HELIOS 1.9. The benchmark was focused on a comparison of the methods and basic nuclear data. Acceptable results of benchmark comparison allowed examining and comparing different ad...
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It has long been known that thorium-232 is a fertile radioactive material that can produce energy in nuclear reactors for conversion to electricity. Thorium-232 is well suited to a variety of reactor types including molten fluoride salt designs, heavy water CANDU configurations, and helium-cooled TRISO-
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The need for proliferation-resistance, longer fuel cycles, higher burn up and improvedwaste form characteristics has led to a renewed worldwide interest in thorium-based fuels and fuel cycles. In this paper the GEANT4 Monte Carlo code has been used to simulate the Thorium-Uranium fuel cycle. The accelerator driven fertile to fissile conversion rates have been calculated for various geometries. ...
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Fast reactor fuel cycle (FRFC) is regaining importance because of its vital role in the long term development of nuclear power. The safety issues associated with the fast reactors are now well understood and newer designs can address those from the lessons learned in the past. The same cannot be ascertained about their safeguards issues. Primary reason being the presence of special nuclear mate...
متن کاملInvestigation of the required thickness of thorium spent fuel lead transport cask depending on different fuel burnups and cooling times
Thorium fuels have attracted researcher’s attention due to the reduction of uranium deposits in the world, more abundances than uranium, and the ability to be breeding in thermal and fast reactors. This study aimed to investigate the radiation safety and the amount of necessary shielding for the transportation of spent thorium fuel in the Tehran Research Reactor. The ORIGEN and MCNPX computatio...
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ژورنال
عنوان ژورنال: TRENDS IN THE SCIENCES
سال: 1997
ISSN: 1884-7080,1342-3363
DOI: 10.5363/tits.2.11_61