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Title: DHLW Glass Waste Package Criticality Analysis (SCPB:N/A)

Abstract

This analysis is prepared by the Mined Geologic Disposal System (MGDS) Waste Package Development Department (WPDD) to determine the viability of the Defense High-Level Waste (DHLW) Glass waste package concept with respect to criticality regulatory requirements in compliance with the goals of the Waste Package Implementation Plan (Ref. 5.1) for conceptual design. These design calculations are performed in sufficient detail to provide a comprehensive comparison base with other design alternatives. The objective of this evaluation is to show to what extent the concept meets the regulatory requirements or indicate additional measures that are required for the intact waste package.

Authors:
Publication Date:
Research Org.:
Office of Scientific and Technical Information, Oak Ridge, TN
Sponsoring Org.:
USDOE
OSTI Identifier:
875318
Report Number(s):
BBAC00000-01717-0200-0001
TRN: US0600917
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
12 MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; 42 ENGINEERING; WASTE FORMS; CRITICALITY; DESIGN; GLASS; HIGH-LEVEL RADIOACTIVE WASTES; SAFETY ANALYSIS; RADIOACTIVE WASTE DISPOSAL

Citation Formats

J.W. Davis. DHLW Glass Waste Package Criticality Analysis (SCPB:N/A). United States: N. p., 1996. Web. doi:10.2172/875318.
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J.W. Davis. DHLW Glass Waste Package Criticality Analysis (SCPB:N/A). United States. doi:10.2172/875318.
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J.W. Davis. Fri . "DHLW Glass Waste Package Criticality Analysis (SCPB:N/A)". United States. doi:10.2172/875318. https://www.osti.gov/servlets/purl/875318.
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@article{osti_875318,
title = {DHLW Glass Waste Package Criticality Analysis (SCPB:N/A)},
author = {J.W. Davis},
abstractNote = {This analysis is prepared by the Mined Geologic Disposal System (MGDS) Waste Package Development Department (WPDD) to determine the viability of the Defense High-Level Waste (DHLW) Glass waste package concept with respect to criticality regulatory requirements in compliance with the goals of the Waste Package Implementation Plan (Ref. 5.1) for conceptual design. These design calculations are performed in sufficient detail to provide a comprehensive comparison base with other design alternatives. The objective of this evaluation is to show to what extent the concept meets the regulatory requirements or indicate additional measures that are required for the intact waste package.},
doi = {10.2172/875318},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Fri Mar 29 00:00:00 EST 1996},
month = {Fri Mar 29 00:00:00 EST 1996}
}
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Technical Report:
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DOI:  10.2172/875318
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  • A preliminary analysis was performed to determine if the dissolution resistance of Defense High-Level Waste (DHLW) glass in silicia-saturated brine is sufficient to meet the Nuclear Regulatory Commission (NRC) fractional release rate requirement for nuclear waste repositories. The sensitivities of fractional release to variations in temperature, surface area, and matrix solubility were also examined. Results indicate that a waste form dissolution resistance strategy is potentially viable for demonstrating compliance with the NRC regulatory requirement. However, major uncertainties exist in two areas: demonstrating that the brine contacting the glass is saturated in silica, and predicting the exposed glass surface area. 12more » refs., 4 figs.« less

  • The objective of this calculation was to determine the structural response of multi-canister overpacks (MCO) and the 2-MCO/2-Defense High-Level Waste (DHLW) Waste Package (WP) subjected to tip-over onto an unyielding surface (US). The scope of this calculation was limited to reporting the calculation results in terms of maximum stress intensities. This calculation is associated with the waste package design and was performed by the Waste Package Design Section in accordance with the DOE SNF Analysis Plan for FY 2000.

  • The objective of this calculation is to determine the dose rates on the external surfaces of the waste package (WP) containing two Hanford defense high-level waste (DHLW) glass canisters and two Hanford multi-canister overpacks (MCO). Each MCO is loaded with the N Reactor spent nuclear fuel (SNF). The information provided by the sketches attached to this calculation is that of the potential design for the WP type considered in this calculation. The scope of this calculation is limited to reporting dose rates averaged over segments of the WP radial and axial surfaces and of surfaces 1 m and 2 mmore » from the WP. The results of this calculation will be used to assess the shielding performance of the 2-MC012-DHLW WP engineering design.« less

  • ;
    This report presents the results of transient thermal analyses performed to determine temperatures in the near- and far-field, vicinity of a defense high-level waste container and an emplacement drift. Three different drift/waste package configurations were modeled; one containing nitrogen gas, another crushed salt, and the last bentonite/sand as the backfill material between the container and the borehole wall. The thermal conductivity of the salt formation was assumed to be temperature dependent while both the density and specific heat were assumed to be constant. Analyses were undertaken using a four node, bilinear, quadrilateral finite element nonlinear heat transfer program, COYOTE, andmore » a finite difference thermal analyzer code, SINDA. Typical temporal and spatial distributions of temperature are presented for each case. The temperature profiles and histories of the backfill material and host rock salt are used to assess their thermal behaviors and to guide future material test analyses. The near-field temperatures obtained from these thermal analyses are compared with measured experimental data. 17 refs., 26 figs., 3 tabs.« less

  • The TiCode-12 container is a waste package design proposed for Defense High Level Waste (DHLW) by Sandia National Laboratories. The TiCode-12 container is cylindrical in shape with a spherical (dome-shaped) top. There is concern about the structural integrity of the dome-shaped top of the TiCode-12 container during the waste isolation period. This report investigates the normal stresses that may be induced on the dome of the TiCode-12 DHLW container, as well as the radial stresses on the cylindrical portion of the container, during the waste isolation period. At the time of emplacement of the TiCode-12 container in a potential repository,more » the container is lowered into a vertical borehole in the floor of the disposal room. There will be an open space (annulus) between the container and the wall of the drilled borehole. In this study, this annulus was considered open, as well as backfilled with ''crushed salt'' material and also ''a blend of bentonite and silica sand'' material. Several different annuli sizes were also considered in this study. Results show that the normal stresses on the dome of the TiCode-12 container are spatially nonuniform and time dependent. The maximum normal stresses predicted are similar for the two APDs considered; however, the time of occurrence of the maxima is significantly different. When backfill material is used, it appears for the conditions studied, an optimum annulus size is approximately 0.05 m. There are indications that an open annulus (no backfill) provides an opportunity to reduce the maximum normal stresses on the dome of the TiCode-12 container, as well as the radial stresses on the cylindrical portion of the container, to magnitudes lower than those predicted when backfill material is present. 17 refs., 58 figs., 7 tabs.« less