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Title: Waste Stream Treatment and Waste Form Fabrication for Pyroprocessing of Used Nuclear Fuel

Abstract

This report summarizes treatment and waste form options being evaluated for waste streams resulting from the electrochemical/pyrometallurgical (pyro ) processing of used oxide nuclear fuel. The technologies that are described are South Korean (Republic of Korea – ROK) and United States of America (US) ‘centric’ in the approach to treating pyroprocessing wastes and are based on the decade long collaborations between US and ROK researchers. Some of the general and advanced technologies described in this report will be demonstrated during the Integrated Recycle Test (IRT) to be conducted as a part of the Joint Fuel Cycle Study (JFCS) collaboration between US Department of Energy (DOE) and ROK national laboratories. The JFCS means to specifically address and evaluated the technological, economic, and safe guard issues associated with the treatment of used nuclear fuel by pyroprocessing. The IRT will involve the processing of commercial, used oxide fuel to recover uranium and transuranics. The recovered transuranics will then be fabricated into metallic fuel and irradiated to transmutate, or burn the transuranic elements to shorter lived radionuclides. In addition, the various process streams will be evaluated and tested for fission product removal, electrolytic salt recycle, minimization of actinide loss to waste streams and wastemore » form fabrication and characterization. This report specifically addresses the production and testing of those waste forms to demonstrate their compatibility with treatment options and suitability for disposal.« less

Authors:
 [1];  [2];  [2];  [3];  [4]
  1. Idaho National Lab. (INL), Idaho Falls, ID (United States)
  2. Korea Atomic Energy Research Institute (KAERI), Daejeon (Korea)
  3. Argonne National Lab. (ANL), Argonne, IL (United States)
  4. Pacific Northwest National Lab. (PNNL), Richland, WA (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:
1178065
Report Number(s):
INL/EXT-14-34014
DOE Contract Number:  
DE-AC07-05ID14517
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; 12 MGMT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; Electrochemical Waste Stream Processing; Electrochemical/Pyrometallurgical; Pyrometallurgical Waste Stream Processing; Waste Form Fabrication

Citation Formats

Frank, Steven, Park, Hwan Seo, Cho, Yung Zun, Ebert, William, and Riley, Brian. Waste Stream Treatment and Waste Form Fabrication for Pyroprocessing of Used Nuclear Fuel. United States: N. p., 2014. Web. doi:10.2172/1178065.
Frank, Steven, Park, Hwan Seo, Cho, Yung Zun, Ebert, William, & Riley, Brian. Waste Stream Treatment and Waste Form Fabrication for Pyroprocessing of Used Nuclear Fuel. United States. https://doi.org/10.2172/1178065
Frank, Steven, Park, Hwan Seo, Cho, Yung Zun, Ebert, William, and Riley, Brian. 2014. "Waste Stream Treatment and Waste Form Fabrication for Pyroprocessing of Used Nuclear Fuel". United States. https://doi.org/10.2172/1178065. https://www.osti.gov/servlets/purl/1178065.
@article{osti_1178065,
title = {Waste Stream Treatment and Waste Form Fabrication for Pyroprocessing of Used Nuclear Fuel},
author = {Frank, Steven and Park, Hwan Seo and Cho, Yung Zun and Ebert, William and Riley, Brian},
abstractNote = {This report summarizes treatment and waste form options being evaluated for waste streams resulting from the electrochemical/pyrometallurgical (pyro ) processing of used oxide nuclear fuel. The technologies that are described are South Korean (Republic of Korea – ROK) and United States of America (US) ‘centric’ in the approach to treating pyroprocessing wastes and are based on the decade long collaborations between US and ROK researchers. Some of the general and advanced technologies described in this report will be demonstrated during the Integrated Recycle Test (IRT) to be conducted as a part of the Joint Fuel Cycle Study (JFCS) collaboration between US Department of Energy (DOE) and ROK national laboratories. The JFCS means to specifically address and evaluated the technological, economic, and safe guard issues associated with the treatment of used nuclear fuel by pyroprocessing. The IRT will involve the processing of commercial, used oxide fuel to recover uranium and transuranics. The recovered transuranics will then be fabricated into metallic fuel and irradiated to transmutate, or burn the transuranic elements to shorter lived radionuclides. In addition, the various process streams will be evaluated and tested for fission product removal, electrolytic salt recycle, minimization of actinide loss to waste streams and waste form fabrication and characterization. This report specifically addresses the production and testing of those waste forms to demonstrate their compatibility with treatment options and suitability for disposal.},
doi = {10.2172/1178065},
url = {https://www.osti.gov/biblio/1178065}, journal = {},
number = ,
volume = ,
place = {United States},
year = {Mon Dec 01 00:00:00 EST 2014},
month = {Mon Dec 01 00:00:00 EST 2014}
}