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Title: Performance Criteria for Capture and/or Immobilization Technologies

The capture and subsequent immobilization of the four volatile radionuclides (3H, 14C, 85Kr, and 129I) from the off-gas streams of a used nuclear fuel reprocessing facility has been a topic of substantial research interest for the US DOE and international colleagues. Regulations set forth by the US EPA direct that some or all of these radionuclides (based upon fuel burnup, fuel type, cooling time, etc.) will require removal, to some extent, from the plant effluent streams prior to discharge to the environment. Upon removal, the radionuclide, as well as any associated sorbent, is destined for waste. Research of separation and capture methodologies has included a wide range of technologies including liquid caustic scrubbing systems, solid adsorbents, and cryogenic distillation. The studies of waste forms have been correspondingly diverse. In considering the technologies available for future development and implementation of both sorbents and waste forms, it will be necessary to use benchmarked measures of performance to objectively evaluate each sorbent system or waste form. This document is intended to provide initial guidance on the types of performance criteria for capture materials and waste forms intended for use in the recycling removal and disposal of UNF and, where possible, the minimum acceptablemore » values for those criteria.« less
Authors:
 [1] ;  [1] ;  [2] ;  [3] ;  [1] ;  [4]
  1. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
  2. Strata-G, LLC, Knoxville, TN (United States)
  3. Idaho National Lab. (INL), Idaho Falls, ID (United States)
  4. Pacific Northwest National Lab. (PNNL), Richland, WA (United States)
Publication Date:
OSTI Identifier:
1261239
Report Number(s):
INL/EXT--16-38035; ORNL/TM--2016-73
TRN: US1601583
DOE Contract Number:
AC07-05ID14517
Resource Type:
Technical Report
Research Org:
Idaho National Lab. (INL), Idaho Falls, ID (United States); Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Sponsoring Org:
USDOE Office of Nuclear Energy (NE)
Contributing Orgs:
Pacific Northwest National Lab. (PNNL), Richland, WA (United States)
Country of Publication:
United States
Language:
English
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; WASTE FORMS; SPENT FUELS; CARBON 14; IODINE 129; KRYPTON 85; TRITIUM; PERFORMANCE; REMOVAL; DISTILLATION; FUEL REPROCESSING PLANTS; ADSORBENTS; SCRUBBING; GASEOUS WASTES; OFF-GAS SYSTEMS gaseous fission products; used fuel reprocessing facility offgas