Protocol for development of authorized release limits for concrete at U.S. Department of Energy sites
Abstract
The purpose of this protocol is to assist US Department of Energy (DOE) sites in releasing concrete for reuse. Current regulations allow the sites to release surface-contaminated materials if their radioactivity falls below certain levels and to possibly release materials with volumetric contamination or higher levels of surface contamination on a case-by-case basis. In all cases, an ALARA (as low as reasonably achievable) analysis that evaluates the risks of releasing volumetrically contaminated concrete or concrete with higher levels of surface contamination is required as a basis for proposing and setting new release limits that allow for reuse of the concrete material. To evaluate the dose impacts of reusing radioactively contaminated material, the measured radiation levels (pCi/g or disintegrations per minute [dpm]/100 cm{sup 2}) must be converted to the estimated dose (mrem/yr) that would be received by affected individuals. The dose depends on the amounts and types of isotopes present and the time, distance, and method of exposure (e.g., inhalation or external exposure). For each disposition alternative, the protocol provides a systematic method to evaluate the impact of the dose on the affected individuals. The cost impacts of reusing concrete also need to be evaluated. They too depend on the dispositionmore »
- Authors:
- Publication Date:
- Research Org.:
- Argonne National Lab., IL (US)
- Sponsoring Org.:
- US Department of Energy (US)
- OSTI Identifier:
- 764202
- Report Number(s):
- ANL/EAD/TM-92
TRN: US0004925
- DOE Contract Number:
- W-31109-ENG-38
- Resource Type:
- Technical Report
- Resource Relation:
- Other Information: PBD: 22 Aug 2000
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 12 MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; CONCRETES; CONTAMINATION; COST; MAXIMUM ACCEPTABLE CONTAMINATION; INHALATION; RADIOACTIVITY; REGULATIONS; SURFACE CONTAMINATION; RECYCLING; LOW-LEVEL RADIOACTIVE WASTES
Citation Formats
Arnish, J, Kamboj, S, Chen, S -Y, Parker, F L, Smith, A M, Meservey, R H, and Tripp, J L. Protocol for development of authorized release limits for concrete at U.S. Department of Energy sites. United States: N. p., 2000.
Web. doi:10.2172/764202.
Arnish, J, Kamboj, S, Chen, S -Y, Parker, F L, Smith, A M, Meservey, R H, & Tripp, J L. Protocol for development of authorized release limits for concrete at U.S. Department of Energy sites. United States. https://doi.org/10.2172/764202
Arnish, J, Kamboj, S, Chen, S -Y, Parker, F L, Smith, A M, Meservey, R H, and Tripp, J L. 2000.
"Protocol for development of authorized release limits for concrete at U.S. Department of Energy sites". United States. https://doi.org/10.2172/764202. https://www.osti.gov/servlets/purl/764202.
@article{osti_764202,
title = {Protocol for development of authorized release limits for concrete at U.S. Department of Energy sites},
author = {Arnish, J and Kamboj, S and Chen, S -Y and Parker, F L and Smith, A M and Meservey, R H and Tripp, J L},
abstractNote = {The purpose of this protocol is to assist US Department of Energy (DOE) sites in releasing concrete for reuse. Current regulations allow the sites to release surface-contaminated materials if their radioactivity falls below certain levels and to possibly release materials with volumetric contamination or higher levels of surface contamination on a case-by-case basis. In all cases, an ALARA (as low as reasonably achievable) analysis that evaluates the risks of releasing volumetrically contaminated concrete or concrete with higher levels of surface contamination is required as a basis for proposing and setting new release limits that allow for reuse of the concrete material. To evaluate the dose impacts of reusing radioactively contaminated material, the measured radiation levels (pCi/g or disintegrations per minute [dpm]/100 cm{sup 2}) must be converted to the estimated dose (mrem/yr) that would be received by affected individuals. The dose depends on the amounts and types of isotopes present and the time, distance, and method of exposure (e.g., inhalation or external exposure). For each disposition alternative, the protocol provides a systematic method to evaluate the impact of the dose on the affected individuals. The cost impacts of reusing concrete also need to be evaluated. They too depend on the disposition alternative and the extent and type of contamination. The protocol provides a method to perform a detailed analysis of these factors and evaluate the dose and cost impacts for various disposition alternatives. Once the dose and cost impacts of the various alternatives have been estimated, the protocol outlines the steps required to propose new release standards that allow release and reuse of the concrete material.},
doi = {10.2172/764202},
url = {https://www.osti.gov/biblio/764202},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Tue Aug 22 00:00:00 EDT 2000},
month = {Tue Aug 22 00:00:00 EDT 2000}
}