Published September 1998 | Version v1
Report Restricted

Parametric Thermal Analysis for Codisposal Waste Package Canister

Description

The engineering viability of disposal of aluminum-clad, aluminum-based spent nuclear fuel (Al-SNF) in a geologic repository requires a thermal analysis to provide the temperature history of the waste form. Calculated temperatures are used to demonstrate compliance with criteria for waste acceptance into the Mined Geologic Disposal System and as input to assess the chemical and physical behavior of the waste form within the waste package (WP).A thermal analysis methodology was developed to calculate peak temperatures and temperature profiles of Al-SNF in the DOE spent nuclear fuel canister within a codisposal WP. A two-dimensional baseline model with conduction and radiation coupled heat transport was developed to evaluate the thermal performance of Al-SNF directly stored in a canister in a codisposal WP over the range of possible heat loads and boundary conditions. In addition, a conduction model and a detailed model which includes convection were developed to identify the dominant cooling mechanism under the present WP configuration, to investigate physical cooling mechanism in detail, and to estimate the conservatism imbedded in the baseline model.The results of the baseline model showed that the direct disposal configuration with a helium-filled WP satisfied the present waste acceptance criteria (WAC) for the WP design in terms of the peak temperature criterion, Tmax < 350 degrees C, under the reference boundary conditions. A period of 10 years' cooling time for the decay heat loads of the SNF and the High-level Waste Glass Log (HWGL) regions was used as one of the reference design conditions

Availability note (English)

Available from INIS in electronic form; ALSO AVAILABLE FROM OSTI AS DE98054748; NTIS; INIS; US GOVT. PRINTING OFFICE DEP.

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Additional details

Publishing Information

Imprint Pagination
11 p.
Report number
WSRC-MS--98-00336

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
30040538
Subject category
S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES;
Resource subtype / Literary indicator
Conference
Descriptors DEI
CONTAINERS; THERMAL ANALYSIS

Optional Information

Contract/Grant/Project number
Contract AC09-96SR18500
Funding organization
USDOE, Washington, DC (United States)
Secondary number(s)
CONF-980906--