Fission Product Release from Spent Nuclear Fuel During Melting
- 1. Westinghouse Savannah River Company, AIKEN, SC (United States)
Description
The Melt-Dilute process consolidates aluminum-clad spent nuclear fuel by melting the fuel assemblies and diluting the 235U content with depleted uranium to lower the enrichment. During the process, radioactive fission products whose boiling points are near the proposed 850 degrees C melting temperature can be released. This paper presents a review of fission product release data from uranium-aluminum alloy fuel developed from Severe Accident studies. In addition, scoping calculations using the ORIGEN-S computer code were made to estimate the radioactive inventories in typical research reactor fuel as a function of burnup, initial enrichment, and reactor operating history and shutdown time.Ten elements were identified from the inventory with boiling points below or near the 850 degrees C reference melting temperature. The isotopes 137Cs and 85Kr were considered most important. This review serves as basic data to the design and development of a furnace off-gas system for containment of the volatile species
Availability note (English)
Available from INIS in electronic form; ALSO AVAILABLE FROM OSTI AS DE98057313; NTIS; INIS; US GOVT. PRINTING OFFICE DEP.
Files
Additional details
Publishing Information
- Imprint Pagination
- 11 p.
- Report number
- WSRC-MS--98-00282
Conference
- Title
- 3. American Nuclear Society (ANS) topical meeting on DOE spent nuclear fuel and fissile materials management
- Dates
- 8-11 Sep 1998
- Place
- Charleston, SC (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 30040537
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- FISSION PRODUCT RELEASE; MELTING; SPENT FUELS
- Descriptors DEC
- ENERGY SOURCES; FUELS; MATERIALS; NUCLEAR FUELS; PHASE TRANSFORMATIONS; REACTOR MATERIALS
Optional Information
- Contract/Grant/Project number
- Contract AC09-96SR18500
- Funding organization
- USDOE, Washington, DC (United States)
- Secondary number(s)
- CONF-980906--