Dose Calculations for the Co-Disposal WP-of HLW-Glass and the Triga SNF
This calculation is prepared by the Monitored Geologic Repository (MGR) Waste Package Operations (WPO). The purpose of this calculation is to determine the surface dose rates of a codisposal waste package (WP) containing a centrally located Department of Energy (DOE) standardized 18-in. spent nuclear fuel (SNF) canister, loaded with the TRIGA (Training, Research, Isotopes, General Atomics) SNF. This canister is surrounded by five 3-m long canisters, loaded with Savannah River Site (SRS) high-level waste (HLW) glass. The results are to support the WP design and radiological analyses.
- Research Organization:
- Yucca Mountain Project, Las Vegas, Nevada
- Sponsoring Organization:
- USDOE
- OSTI ID:
- 895068
- Report Number(s):
- BBAC00000-01717-0210-00015, Rev. 00; MOL.19990830.0375, DC# 22728
- Country of Publication:
- United States
- Language:
- English
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