Nuclear feasibility of carbon-coated particle fuels in PWRs
- Kyung Hee Univ., Kyungki-Do (Korea, Republic of)
- Korea Advanced Energy Research Inst., Seoul (Korea, Republic of)
In this paper, a design concept of new fuel pellets for pressurized water reactors (PWRs) is introduced and its nuclear feasibility is examined. Pyrocarbon-coated fuel particles used in modular high-temperature gas-cooled reactor (MHTGR) fuel rods have features with the potential for enhancing fuel rod safety when they are packed in PWR fuel pellets. The UCO fuel composition closely packed in a carbon matrix increases thermal conductivity and provides fuel cycle flexibility by the controlled packing of various fissile/fertile particles. A carbon coating layer and graphite matrix on the outside of the particles would give additional vacancies for fission product retention as well as another fission product barrier and neutron moderation within the fuel. They also increase the mechanical strength of the fuel pellet. A manufacturing technique used for MHTGR fuel blocks can be directly applied to pressing composite into a PWR-sized pellet. When these pellets are packed into the cladding tubes, the reactor is expected to be operated at higher power density with longer cycle burnup. On the contrary, this fuel has a potential risk in case of cladding failure because carbon is very reactive with steam. Another concern with this design is the economic feasibility of complex manufacturing processes and high fissile enrichment requirement. In the first stage of the feasibility study, only the nuclear characteristics were checked.
- OSTI ID:
- 426533
- Report Number(s):
- CONF-961103--
- Journal Information:
- Transactions of the American Nuclear Society, Journal Name: Transactions of the American Nuclear Society Vol. 75; ISSN TANSAO; ISSN 0003-018X
- Country of Publication:
- United States
- Language:
- English
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