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Title: Evaluation of Tritium Management Approaches on Tritium Waste Volumes in Reprocessing Plants

Abstract

Four radionuclides have been identified as likely to be volatilized during the reprocessing of nuclear fuel in amounts such that their gaseous release needs to be controlled to meet US regulatory requirements. These radionuclides are 3H, 14C, 85Kr, and 129I. While iodine has been the focus of a number of studies due to the high decontamination factor (DF) requirements on multiple off-gas pathways, it is also clear that the control of tritium could also be a significant issue for future reprocessing plants, especially if processing relatively short-cooled fuels (e.g., <10-yr post reactor discharge). Like iodine, tritium contained in a used nuclear fuel (UNF) matrix will be released into the liquid and off-gas streams during fuel reprocessing. The amount released into the process streams is a function of the type and burnup of the fuel processed, and the chemical processes and processing conditions employed within the reprocessing plant. The required DF for 3H could be as high as 200, depending on the age of the fuel processed. This study examines three main cases with a number of subcases for comparative purposes.

Authors:
 [1];  [1]
  1. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Publication Date:
Research Org.:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Sponsoring Org.:
USDOE Office of Nuclear Energy (NE), Fuel Cycle Technologies (NE-5)
OSTI Identifier:
1429208
Report Number(s):
ORNL/TM-2017/308
DOE Contract Number:  
AC05-00OR22725
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES

Citation Formats

Jubin, Robert Thomas, and Spencer, Barry B. Evaluation of Tritium Management Approaches on Tritium Waste Volumes in Reprocessing Plants. United States: N. p., 2017. Web. doi:10.2172/1429208.
Jubin, Robert Thomas, & Spencer, Barry B. Evaluation of Tritium Management Approaches on Tritium Waste Volumes in Reprocessing Plants. United States. doi:10.2172/1429208.
Jubin, Robert Thomas, and Spencer, Barry B. Fri . "Evaluation of Tritium Management Approaches on Tritium Waste Volumes in Reprocessing Plants". United States. doi:10.2172/1429208. https://www.osti.gov/servlets/purl/1429208.
@article{osti_1429208,
title = {Evaluation of Tritium Management Approaches on Tritium Waste Volumes in Reprocessing Plants},
author = {Jubin, Robert Thomas and Spencer, Barry B.},
abstractNote = {Four radionuclides have been identified as likely to be volatilized during the reprocessing of nuclear fuel in amounts such that their gaseous release needs to be controlled to meet US regulatory requirements. These radionuclides are 3H, 14C, 85Kr, and 129I. While iodine has been the focus of a number of studies due to the high decontamination factor (DF) requirements on multiple off-gas pathways, it is also clear that the control of tritium could also be a significant issue for future reprocessing plants, especially if processing relatively short-cooled fuels (e.g., <10-yr post reactor discharge). Like iodine, tritium contained in a used nuclear fuel (UNF) matrix will be released into the liquid and off-gas streams during fuel reprocessing. The amount released into the process streams is a function of the type and burnup of the fuel processed, and the chemical processes and processing conditions employed within the reprocessing plant. The required DF for 3H could be as high as 200, depending on the age of the fuel processed. This study examines three main cases with a number of subcases for comparative purposes.},
doi = {10.2172/1429208},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Fri Jun 30 00:00:00 EDT 2017},
month = {Fri Jun 30 00:00:00 EDT 2017}
}

Technical Report:

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