Published September 1998 | Version v1
Report Restricted

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.

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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--