skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: Geochemistry Model Validation Report: Material Degradation and Release Model

Abstract

The purpose of this Analysis and Modeling Report (AMR) is to validate the Material Degradation and Release (MDR) model that predicts degradation and release of radionuclides from a degrading waste package (WP) in the potential monitored geologic repository at Yucca Mountain. This AMR is prepared according to ''Technical Work Plan for: Waste Package Design Description for LA'' (Ref. 17). The intended use of the MDR model is to estimate the long-term geochemical behavior of waste packages (WPs) containing U. S . Department of Energy (DOE) Spent Nuclear Fuel (SNF) codisposed with High Level Waste (HLW) glass, commercial SNF, and Immobilized Plutonium Ceramic (Pu-ceramic) codisposed with HLW glass. The model is intended to predict (1) the extent to which criticality control material, such as gadolinium (Gd), will remain in the WP after corrosion of the initial WP, (2) the extent to which fissile Pu and uranium (U) will be carried out of the degraded WP by infiltrating water, and (3) the chemical composition and amounts of minerals and other solids left in the WP. The results of the model are intended for use in criticality calculations. The scope of the model validation report is to (1) describe the MDR model, andmore » (2) compare the modeling results with experimental studies. A test case based on a degrading Pu-ceramic WP is provided to help explain the model. This model does not directly feed the assessment of system performance. The output from this model is used by several other models, such as the configuration generator, criticality, and criticality consequence models, prior to the evaluation of system performance. This document has been prepared according to AP-3.10Q, ''Analyses and Models'' (Ref. 2), and prepared in accordance with the technical work plan (Ref. 17).« less

Authors:
Publication Date:
Research Org.:
Yucca Mountain Project, Las Vegas, Nevada (US)
Sponsoring Org.:
US Department of Energy (US)
OSTI Identifier:
837043
Report Number(s):
ANL-EBS-GS-000001, REV 00
MOL.20011017.0091, DC 28774; TRN: US0502247
Resource Type:
Technical Report
Resource Relation:
Other Information: PBD: 28 Sep 2001
Country of Publication:
United States
Language:
English
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; 12 MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; CERAMICS; CHEMICAL COMPOSITION; CORROSION; CRITICALITY; GADOLINIUM; GEOCHEMISTRY; GLASS; NUCLEAR FUELS; PLUTONIUM; RADIOISOTOPES; SIMULATION; URANIUM; WASTES; YUCCA MOUNTAIN; SPENT FUELS

Citation Formats

H. Stockman. Geochemistry Model Validation Report: Material Degradation and Release Model. United States: N. p., 2001. Web. doi:10.2172/837043.
H. Stockman. Geochemistry Model Validation Report: Material Degradation and Release Model. United States. doi:10.2172/837043.
H. Stockman. Fri . "Geochemistry Model Validation Report: Material Degradation and Release Model". United States. doi:10.2172/837043. https://www.osti.gov/servlets/purl/837043.
@article{osti_837043,
title = {Geochemistry Model Validation Report: Material Degradation and Release Model},
author = {H. Stockman},
abstractNote = {The purpose of this Analysis and Modeling Report (AMR) is to validate the Material Degradation and Release (MDR) model that predicts degradation and release of radionuclides from a degrading waste package (WP) in the potential monitored geologic repository at Yucca Mountain. This AMR is prepared according to ''Technical Work Plan for: Waste Package Design Description for LA'' (Ref. 17). The intended use of the MDR model is to estimate the long-term geochemical behavior of waste packages (WPs) containing U. S . Department of Energy (DOE) Spent Nuclear Fuel (SNF) codisposed with High Level Waste (HLW) glass, commercial SNF, and Immobilized Plutonium Ceramic (Pu-ceramic) codisposed with HLW glass. The model is intended to predict (1) the extent to which criticality control material, such as gadolinium (Gd), will remain in the WP after corrosion of the initial WP, (2) the extent to which fissile Pu and uranium (U) will be carried out of the degraded WP by infiltrating water, and (3) the chemical composition and amounts of minerals and other solids left in the WP. The results of the model are intended for use in criticality calculations. The scope of the model validation report is to (1) describe the MDR model, and (2) compare the modeling results with experimental studies. A test case based on a degrading Pu-ceramic WP is provided to help explain the model. This model does not directly feed the assessment of system performance. The output from this model is used by several other models, such as the configuration generator, criticality, and criticality consequence models, prior to the evaluation of system performance. This document has been prepared according to AP-3.10Q, ''Analyses and Models'' (Ref. 2), and prepared in accordance with the technical work plan (Ref. 17).},
doi = {10.2172/837043},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Fri Sep 28 00:00:00 EDT 2001},
month = {Fri Sep 28 00:00:00 EDT 2001}
}

Technical Report:

Save / Share: