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Title: Preparation of plutonium waste forms with ICPP calcined high-level waste

Abstract

Glass and glass-ceramic forms developed for the immobilization of calcined high-level wastes generated by Idaho Chemical Processing Plant (ICPP) fuel reprocessing activities have been investigated for ability to immobilize plutonium and to simultaneously incorporate calcined waste as an anti-proliferation barrier. Within the forms investigated, crystallization of host phases result in an increased loading of plutonium as well as its incorporation into potentially more durable phases than the glass. The host phases were initially formed and characterized with cerium (Ce{sup +4}) as a surrogate for plutonium (Pu{sup +4}) and samarium as a neutron absorber for criticality control. Verification of the surrogate testing results were then performed replacing cerium with plutonium. All testing was performed with surrogate calcined high-level waste. The results of these tests indicated that a potentially useful host phase, based on zirconia, can be formed either by devitrification or solid state reaction in the glass studied. This phase incorporates plutonium as well as samarium and the calcined waste becomes part of the matrix. Its ease of formation makes it potentially useful in excess plutonium dispositioning. Other durable host phases for plutonium and samarium, including zirconolite and zircon have been formed from zirconia or alumina calcine through cold press-sintering techniquesmore » and hot isostatic pressing. Host phase formation experiments conducted through vitrification or by cold press-sintering techniques are described and the results discussed. Recommendations are given for future work that extends the results of this study.« less

Authors:
;  [1];  [2]
  1. Lockheed Idaho Technologies Co., Idaho Falls, ID (United States)
  2. Argonne National Lab.-West, Idaho Falls, ID (United States); and others
Publication Date:
Research Org.:
Lockheed Idaho Technologies Co., Idaho Falls, ID (United States)
Sponsoring Org.:
USDOE Office of Environmental Restoration and Waste Management, Washington, DC (United States)
OSTI Identifier:
554797
Report Number(s):
INEEL/EXT-97-00496
ON: DE98050303; TRN: 98:008766
DOE Contract Number:  
AC07-94ID13223
Resource Type:
Technical Report
Resource Relation:
Other Information: PBD: May 1997
Country of Publication:
United States
Language:
English
Subject:
05 NUCLEAR FUELS; 36 MATERIALS SCIENCE; PLUTONIUM; WASTE FORMS; IDAHO CHEMICAL PROCESSING PLANT; HIGH-LEVEL RADIOACTIVE WASTES; GLASS; CERAMICS; PHASE STUDIES; VITRIFICATION; COLD PRESSING; SINTERING; NEUTRON ABSORBERS; ZIRCONIUM OXIDES; CERIUM OXIDES; PLUTONIUM OXIDES

Citation Formats

Staples, B A, Knecht, D A, and O`Holleran, T P. Preparation of plutonium waste forms with ICPP calcined high-level waste. United States: N. p., 1997. Web. doi:10.2172/554797.
Staples, B A, Knecht, D A, & O`Holleran, T P. Preparation of plutonium waste forms with ICPP calcined high-level waste. United States. doi:10.2172/554797.
Staples, B A, Knecht, D A, and O`Holleran, T P. Thu . "Preparation of plutonium waste forms with ICPP calcined high-level waste". United States. doi:10.2172/554797. https://www.osti.gov/servlets/purl/554797.
@article{osti_554797,
title = {Preparation of plutonium waste forms with ICPP calcined high-level waste},
author = {Staples, B A and Knecht, D A and O`Holleran, T P},
abstractNote = {Glass and glass-ceramic forms developed for the immobilization of calcined high-level wastes generated by Idaho Chemical Processing Plant (ICPP) fuel reprocessing activities have been investigated for ability to immobilize plutonium and to simultaneously incorporate calcined waste as an anti-proliferation barrier. Within the forms investigated, crystallization of host phases result in an increased loading of plutonium as well as its incorporation into potentially more durable phases than the glass. The host phases were initially formed and characterized with cerium (Ce{sup +4}) as a surrogate for plutonium (Pu{sup +4}) and samarium as a neutron absorber for criticality control. Verification of the surrogate testing results were then performed replacing cerium with plutonium. All testing was performed with surrogate calcined high-level waste. The results of these tests indicated that a potentially useful host phase, based on zirconia, can be formed either by devitrification or solid state reaction in the glass studied. This phase incorporates plutonium as well as samarium and the calcined waste becomes part of the matrix. Its ease of formation makes it potentially useful in excess plutonium dispositioning. Other durable host phases for plutonium and samarium, including zirconolite and zircon have been formed from zirconia or alumina calcine through cold press-sintering techniques and hot isostatic pressing. Host phase formation experiments conducted through vitrification or by cold press-sintering techniques are described and the results discussed. Recommendations are given for future work that extends the results of this study.},
doi = {10.2172/554797},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1997},
month = {5}
}