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Title: Experimental plan for DPC/overpack performance in a repository.

Abstract

Abstract not provided.

Authors:
; ; ; ;
Publication Date:
Research Org.:
Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)
Sponsoring Org.:
USDOE National Nuclear Security Administration (NNSA)
OSTI Identifier:
1162056
Report Number(s):
SAND2014-18321R
537894
DOE Contract Number:
AC04-94AL85000
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English

Citation Formats

Ilgen, Anastasia Gennadyevna, Enos, David George, Bryan, Charles R., Rechard, Robert P., and Hardin, Ernest. Experimental plan for DPC/overpack performance in a repository.. United States: N. p., 2014. Web. doi:10.2172/1162056.
Ilgen, Anastasia Gennadyevna, Enos, David George, Bryan, Charles R., Rechard, Robert P., & Hardin, Ernest. Experimental plan for DPC/overpack performance in a repository.. United States. doi:10.2172/1162056.
Ilgen, Anastasia Gennadyevna, Enos, David George, Bryan, Charles R., Rechard, Robert P., and Hardin, Ernest. Wed . "Experimental plan for DPC/overpack performance in a repository.". United States. doi:10.2172/1162056. https://www.osti.gov/servlets/purl/1162056.
@article{osti_1162056,
title = {Experimental plan for DPC/overpack performance in a repository.},
author = {Ilgen, Anastasia Gennadyevna and Enos, David George and Bryan, Charles R. and Rechard, Robert P. and Hardin, Ernest},
abstractNote = {Abstract not provided.},
doi = {10.2172/1162056},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Wed Oct 01 00:00:00 EDT 2014},
month = {Wed Oct 01 00:00:00 EDT 2014}
}

Technical Report:

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  • This document describes an integrated laboratory testing and model development effort for the seal system for a high-level nuclear waste repository in salt. The testing and modeling efforts are designed to determine seal material response in the repository environment, to provide models of seal system components for performance assessment, and to assist in the development of seal system designs. A code/model development and performance analysis program will be performed to predict the short- and long-term response of seal materials and seal components. The results from these analyses will be used to support the material testing activities on this contract andmore » to support performance assessment activities that are conducted in other parts of the Salt Repository Project (SRP). 48 refs., 15 figs., 4 tabs.« less
  • This report presents theoretical and experimental results, which demonstrate the feasibility of a new class of thermophotovoltaic (TPV) energy converters with greatly improved power density and efficiency. Performance improvements are based on the utilization of the enhanced photon concentrations within high refractive index materials. Analysis demonstrates that the maximum achievable photon flux for TPV applications is limited by the lowest index in the photonic cavity, and scales as the minimum refraction index squared, n{sup 2}. Utilization of the increased photon levels within high index materials greatly expands the design space limits of TPV systems, including: a 10x increase in powermore » density, a 50% fractional increase in conversion efficiency, or alternatively reduced radiator temperature requirements to as low as {approx} 1000 F.« less
  • The projected environmental history of a Tuff repository sited in an unsaturated hydrologic setting is evaluated to identify the potentially most severe corrosion conditions for Zircaloy spent fuel cladding. Three distinct corrosion periods are identified over the projected history. In two of those, liquid water may be present which is believed to produce the most severe corrosive environment for Zircaloy spent fuel cladding. In the time interval 100 to 1000 years after emplacement in the repository, the most severe condition is exposure to 170{sup 0}C water at about 100 psi in an unbreached canister. This condition will be reproduced experimentallymore » in an autoclave. For times after 1000 years, the most severe condition is exposure to 90{sup 0}C water that is equilibrated with the tuff and invades breached canisters. This condition will be reproduced with a water bath system.« less
  • The potential for degradation or corrosion of spent fuel cladding in a tuff repository is examined, and an initial experimental plan to determine corrosion mechanisms and to estimate long-term corrosion rates is presented. The environmental history of a tuff repository at Yucca Mountain is evaluated for the potentially most severe corrosion conditions for Zircaloy spent fuel cladding. In two of the three distinct periods identified, liquid water can be present. An overview of the corrosion characteristics of zirconium and its alloys indicates that conditions in which liquid water is present should be the most corrosive conditions for spent fuel cladding.more » The experimental program will model the chemical, physical and geometrical aspects of spent fuel disposal as precisely as possible. The corrosion specimens will be examined by standard techniques such as optical microscopy and SEM and by state-of-the-art techniques such as using the STEM in a SEM mode to achieve much higher resolution that normally obtained with a standard SEM. A key aspect is the comparative examination that will be needed to help establish mechanisms and estimate or bound low corrosion rates. This plan presents an initial program schedule for these studies, as well as proposed schedules for the future. It also spells out what information will be provided in reports, starting at the end of FY 1985. 46 refs., 9 figs., 6 tabs.« less
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