Thorium based fuel loading pattern for PWR reactor
نویسندگان
چکیده
منابع مشابه
Improved PWR Core Characteristics with Thorium-containing Fuel
Thorium is an element for possible use as nuclear fuel, because of the fertile property of Th-232, which could convert into U-233 after neutron capture and beta decays. However, thorium based fuels have not been successfully implemented, because of the high cost and the higher complexity compared with once-through uranium fuel. Therefore, the focus of this thesis is on thorium for use in tradit...
متن کاملThorium Blended and Regular Mox Burn-up Studies for Fast Reactor Fuel Cycle Safeguards
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 کاملStudy 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...
متن کاملCritical Assessment of Thorium Reactor Technology
Thorium-based fuels for nuclear reactors are being considered for use with current and future designs in both large and small-scale energy production. Thorium-232 is as abundant on Earth as lead, far more common than all isotopes of uranium, leading to its greatly reduced cost. Thorium itself offers a significantly greater neutron absorption cross-section than uranium at thermal energies, resul...
متن کاملFission Gas Release Comparison for PWR Duplex Fuel Pellets
Current research has identified Duplex pellets as an effective strategy for decreasing the centerline temperature of the fuel. However, before this design can be widely utilized several areas, including fission gas release, need to be better characterized. Therefore, this paper seeks to ascertain the relative difference in fission gas release between a standard solid UO2 reference design and a ...
متن کاملذخیره در منابع من
با ذخیره ی این منبع در منابع من، دسترسی به آن را برای استفاده های بعدی آسان تر کنید
ژورنال
عنوان ژورنال: E3S Web of Conferences
سال: 2019
ISSN: 2267-1242
DOI: 10.1051/e3sconf/201910801028