A methodology for addressing particulate content in DOE SNF containers
- Idaho National Engineering and Environmental Lab., Idaho Falls, ID (United States)
Herein the authors provide guidance on evaluating particulate content limits for packaging of US Department of Energy (DOE) spent nuclear fuel (SNF). The SNF should remain in the original standardized canister throughout the interim storage period. At the end of interim storage, it must be acceptable for transportation in the public domain to the monitored geologic repository (MGR) and for disposal at the MGR without repackaging. Conformance to radioactive waste requirements at the MGR must be demonstrated at the time of receipt. Requirements for disposal of SNF in a monitored geologic repository are contained in the Waste Acceptance System Requirements document. The primary concern is the MGR; however, interim storage and transport (not necessarily to the repository) safety issues must also be addressed. Each site responsible for packaging DOE SNF for interim storage, transportation, and disposal has its own mission and requirements.
- OSTI ID:
- 678104
- Report Number(s):
- CONF-990605--
- Journal Information:
- Transactions of the American Nuclear Society, Journal Name: Transactions of the American Nuclear Society Vol. 80; ISSN 0003-018X; ISSN TANSAO
- Country of Publication:
- United States
- Language:
- English
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