Extended Burnup: Ex-Core and Accident Considerations
Conference
·
· Transactions of the American Nuclear Society
OSTI ID:7125119
- Duke Power Co., Charlotte, NC (United States)
Original design-basis cycle average burnup referenced for fuel discharged from Duke Power Company's Catawba and McGuire units in safety analysis calculations is 11 450 MWd/ton U. Due to changes in the fuel cycle that have developed since the initial design of these units, significant economic benefits can be realized by extending cycle burnup beyond 11 450 MWd/ton. These benefits include decreases spent-fuel discharge rates, increased plant capacity factors, reduced spent-fuel storage and disposal requirements, and reduced worker radiation exposures. In order to achieve the benefits of extended burnup, numerous in-core thermal-hydraulic and reactivity safety analyses must be performed and documented in a Reload Safety Evaluation Report submitted to the US Nuclear Regulatory Commission NRC. Other technical concerns associated with extending fuel discharge burnups not addressed as part of the reload reports include fuel storage capability (both fresh and spent) and safety analysis report (SAR) off-site accident dose calculation impacts. This paper describes Duke Power Company's approach in addressing these accident and ex-core concerns in support of the McGuire and Catawba extended burnup programs.
- Research Organization:
- Duke Power Co., Charlotte, NC (United States)
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
- OSTI ID:
- 7125119
- Report Number(s):
- CONF-861102-
- Conference Information:
- Journal Name: Transactions of the American Nuclear Society Journal Volume: 53
- Country of Publication:
- United States
- Language:
- English
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Nuclear Criticality Safety Program (NCSP)
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