Preliminary preclosure radiological safety analysis for normal operations of a prospective Yucca Mountain repository
A preliminary radiological safety analysis was performed for the normal operating conditions during the preclosure period at the prospective Yucca Mountain repository. Since the repository is designed to accommodate spent fuel and defense high-level waste (DHLW), an estimate was made of the offsite doses and onsite occupational doses from (1) anticipated routine releases of airborne radioactive materials and from (2) the handling of the spent fuels and DHLW. This paper summarizes the methodology and calculated offsite doses resulting from the postulated routine releases of airborne radioactive materials from the waste-handling building through inhalation and immersion pathways. The calculated onsite occupational doses from the inhalation, immersion, and direct exposure pathways will be reported elsewhere at a later date. 15 refs. , 4 tabs.
- Research Organization:
- Sandia National Labs., Albuquerque, NM (United States)
- DOE Contract Number:
- AC04-76DP00789
- OSTI ID:
- 60647
- Report Number(s):
- SAND--87-2070C; CONF-880903--47; ON: DE89005208
- Country of Publication:
- United States
- Language:
- English
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