Reactor physics calculations for {sup 99}Mo production at the Annular Core Research Reactor
Conference
·
OSTI ID:100094
The isotope {sup 99}Mo would be produced at Sandia using ACRR and the collocated Hot Cell Facility. {sup 99}Mo would be produced by irradiating targets coated with {sup 235}U in the form of highly enriched U{sub 3}O{sub 8}; after 7 days, the target would be removed and the isotope extracted using the Cintichem process. The Monte Carlo neutronics computer code MCNP was used to determine the optimum configuration for production, using various fractions of the US demand. Although ACRR operates at a low power level, the US demand for {sup 99}Mo can be easily met using a reasonable number of targets.
- Research Organization:
- Sandia National Labs., Albuquerque, NM (United States)
- Sponsoring Organization:
- USDOE, Washington, DC (United States)
- DOE Contract Number:
- AC04-94AL85000
- OSTI ID:
- 100094
- Report Number(s):
- SAND--95-1511C; CONF-951135--10; ON: DE95015092
- Country of Publication:
- United States
- Language:
- English
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