On the uncertainity of neutron transport calculations for reactor pressure vessel surveillance
Journal Article
·
· Transactions of the American Nuclear Society
OSTI ID:436886
- Oak Ridge National Laboratory, TN (United States)
One of the primary concerns of the aging nuclear power plants is the radiation-induced embrittlement of the reactor pressure vessels (PVs). In the current methodology, the PV material embrittlement is determined from the prescribed (regulatory) or plant-specific trend curves, which give the increase of reference nil-ductility transition (NDT) temperature ({Delta}RT{sub NDT}) of the materials as a function of material chemical composition and fast (E > 1 MeV) neutron fluence. Therefore, accurate and reliable fast fluence values in the PV and surveillance capsule locations must be known.
- OSTI ID:
- 436886
- Report Number(s):
- CONF-9606116--
- Journal Information:
- Transactions of the American Nuclear Society, Journal Name: Transactions of the American Nuclear Society Vol. 74; ISSN 0003-018X; ISSN TANSAO
- Country of Publication:
- United States
- Language:
- English
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