Neutronics calculation of the conceptual TRISO duplex fuel rod design
| Autor: | Aznan Fazli Ismail, Mohamad Hairie Rabir, Mohd Syukri Yahya |
|---|---|
| Jazyk: | angličtina |
| Rok vydání: | 2021 |
| Předmět: |
Nuclear and High Energy Physics
Neutron transport Materials science Thorium reactor Materials Science (miscellaneous) Nuclear engineering chemistry.chemical_element Blanket 01 natural sciences Rod 010305 fluids & plasmas TRISO-duplex Breeder (animal) 0103 physical sciences Burnup 010302 applied physics Fissile material TK9001-9401 Micro modular reactor Plutonium Nuclear Energy and Engineering Criticality chemistry Nuclear engineering. Atomic power sense organs High temperature reactor |
| Zdroj: | Nuclear Materials and Energy, Vol 27, Iss, Pp 101005-(2021) |
| ISSN: | 2352-1791 |
| Popis: | The duplex fuel pellet includes UO2 components as seed and ThO2 blanket, originally designed to increase the breeding rate of fissile materials in light water breeder reactors. However, the seed portion alone concentrates most of the energy released from the fission reaction, which can make the seed temperature too high. The duplex fuel potential for the high-temperature reactor (HTR) using TRISO fuel has never been researched. MCNPX simulation was conducted to compare the neutronics performance of normal TRISO fuel with that of TRISO duplex fuel. Two types of HTR fuel rod, the cylinder and the annular rod, were simulated and compared to see whether the duplex neutron characteristics would be better in the cylinder or annular fuel compact design. The TRISO duplex rods produced higher burnup than normal rods up to 5% higher for cylinder and 6% for annular rods. The TRISO duplex rod is also capable of maintaining longer criticality, producing smaller kinf changes and reducing the potential for plutonium build-up. The proposed TRISO duplex conceptual fuel design has an interesting neutronic properties, which offers possibilities for future studies. |
| Databáze: | OpenAIRE |
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