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Title: As-Built Characterization and Monitoring System for the RH-LLW Disposal Facility

Abstract

The performance assessment (PA) for the Idaho National Laboratory (INL) Remote Handled Low Level Waste (RH LLW) disposal facility (U.S. Department of Energy [DOE]-ID 2012) is required to demonstrate that the facility design will meet the performance objectives established for long term protection of the public and the environment following closure of the facility as outlined in DOE Order 435.1, “Radioactive Waste Management.” Protectiveness of the facility in terms of the groundwater pathway is a function of the design features that control the hydrologic and geochemical conditions within and below the vault system. The facility design includes features to promote drainage of infiltrating water to limit accumulation of moisture next to the reinforced concrete disposal vaults and containerized waste. The PA groundwater pathway model accounts for a cement impacted geochemical environment within and below the vault system to inhibit corrosion of stainless steel waste containers (i.e., waste liners), steel reinforcement in the concrete vault, and the effects on release and migration of non anionic radionuclides. Upon closure of the facility, an engineered barrier (i.e., cover) will be placed over the facility to reduce infiltration through the waste zone, retarding the release and migration rate of radionuclides beneath the facility. Creditingmore » the long-term performance of the vault system requires characterization of the hydraulic and concrete performance over time. Verification of the vault performance requires monitoring for radiologic releases from the facility. The purpose of this document is to provide the description of the characterization and monitoring system installed at the facility to accomplish these two objectives.« less

Authors:
 [1]
  1. Idaho National Lab. (INL), Idaho Falls, ID (United States)
Publication Date:
Research Org.:
Idaho National Lab. (INL), Idaho Falls, ID (United States)
Sponsoring Org.:
USDOE Office of Nuclear Energy (NE)
OSTI Identifier:
1468438
Report Number(s):
INL/EXT-17-43081-Rev000
TRN: US1902788
DOE Contract Number:  
AC07-05ID14517
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
99 GENERAL AND MISCELLANEOUS; RH-LLW disposal facility; as-built characterization; monitoring system

Citation Formats

Schafer, Annette L. As-Built Characterization and Monitoring System for the RH-LLW Disposal Facility. United States: N. p., 2017. Web. doi:10.2172/1468438.
Schafer, Annette L. As-Built Characterization and Monitoring System for the RH-LLW Disposal Facility. United States. https://doi.org/10.2172/1468438
Schafer, Annette L. Fri . "As-Built Characterization and Monitoring System for the RH-LLW Disposal Facility". United States. https://doi.org/10.2172/1468438. https://www.osti.gov/servlets/purl/1468438.
@article{osti_1468438,
title = {As-Built Characterization and Monitoring System for the RH-LLW Disposal Facility},
author = {Schafer, Annette L.},
abstractNote = {The performance assessment (PA) for the Idaho National Laboratory (INL) Remote Handled Low Level Waste (RH LLW) disposal facility (U.S. Department of Energy [DOE]-ID 2012) is required to demonstrate that the facility design will meet the performance objectives established for long term protection of the public and the environment following closure of the facility as outlined in DOE Order 435.1, “Radioactive Waste Management.” Protectiveness of the facility in terms of the groundwater pathway is a function of the design features that control the hydrologic and geochemical conditions within and below the vault system. The facility design includes features to promote drainage of infiltrating water to limit accumulation of moisture next to the reinforced concrete disposal vaults and containerized waste. The PA groundwater pathway model accounts for a cement impacted geochemical environment within and below the vault system to inhibit corrosion of stainless steel waste containers (i.e., waste liners), steel reinforcement in the concrete vault, and the effects on release and migration of non anionic radionuclides. Upon closure of the facility, an engineered barrier (i.e., cover) will be placed over the facility to reduce infiltration through the waste zone, retarding the release and migration rate of radionuclides beneath the facility. Crediting the long-term performance of the vault system requires characterization of the hydraulic and concrete performance over time. Verification of the vault performance requires monitoring for radiologic releases from the facility. The purpose of this document is to provide the description of the characterization and monitoring system installed at the facility to accomplish these two objectives.},
doi = {10.2172/1468438},
url = {https://www.osti.gov/biblio/1468438}, journal = {},
number = ,
volume = ,
place = {United States},
year = {2017},
month = {9}
}