Distribution and Solubility of Radionuclides in Waste Forms for Disposition of Plutonium and Spent Nuclear Fuels: Preliminary Results
Abstract
Successful immobilization of actinides (Am, Cm, Th, Pu, U, Np, etc.) in crystalline and amorphous host matrices with appropriate neutron absorbers (B, Hf, Gd, etc.) requires sound scientific knowledge of the local chemical environments of both the actinides (An) and the neutron absorbers and their interaction with the host matrices. This understanding leads to a more systematic and efficient approach to predicting solubilities than the strictly empirical approach currently used. The goals of this ongoing research are to determine solubility limits of representative actinides (Pu and U) and neutron absorbers (Hf and Gd) in crystalline and amorphous matrices and to determine solution mechanisms of these species in the two types of systems. Understanding of the chemical systematics of in the two systems will make it possible to calculate the solubility of actinides, neutron absorbers, and, we would suggest, other metal species in glass and ceramic waste form, which have been determined empirically for the past. The research results of the ongoing project will be presented, including solubility of neutron absorbers, Hf(IV) and Gd(III), and local structures of these species in comparison to those of Pu(IV) and Pu(III) in glass. Effect of glass composition, in terms of peralkallinity, Na2O/(Na2O+Al2O3), on dissolutionmore »
- Authors:
-
- PNNL,ETD
- PNNL
- GENERAL ELECTRIC CO.
- BATTELLE (PACIFIC NW LAB)
- Lawrence Livermore National Laboratory
- Lawrence Berkeley National Laboratory
- Michigan, Univ Of - Ann Arbor
- VISITORS
- Publication Date:
- Research Org.:
- Pacific Northwest National Lab., Richland, WA (US)
- Sponsoring Org.:
- US Department of Energy (US)
- OSTI Identifier:
- 15001780
- Report Number(s):
- PNNL-SA-33027-A
TRN: US0400496
- DOE Contract Number:
- AC06-76RL01830
- Resource Type:
- Conference
- Resource Relation:
- Conference: Environmental Issues and Waste Management Technologies in the Ceramic and Nuclear Industries IV,Ceramic Transactions, Conference location not given, Conference dates not given; Other Information: PBD: 1 Jan 1999
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; 12 MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; ACTINIDES; CERAMICS; DISSOLUTION; DISTRIBUTION; GLASS; MATRICES; MICROSTRUCTURE; NEUTRON ABSORBERS; NUCLEAR FUELS; PLUTONIUM; RADIOISOTOPES; SOLUBILITY; WASTE FORMS; WASTE MANAGEMENT
Citation Formats
Feng, Xiangdong, Li, Hong, Davis, L L, Li, Liyu, Darab, John G, Schweiger, Michael J, Vienna, John D, Bunker, Bruce C, Allen, P G, Bucher, J J, Craig, I M, Edelstein, Norman M, Shuh, David K, Ewing, R C, Wang, L M, Vance, Eric R, and James C. Marra, Gregory T. Chandler. Distribution and Solubility of Radionuclides in Waste Forms for Disposition of Plutonium and Spent Nuclear Fuels: Preliminary Results. United States: N. p., 1999.
Web.
Feng, Xiangdong, Li, Hong, Davis, L L, Li, Liyu, Darab, John G, Schweiger, Michael J, Vienna, John D, Bunker, Bruce C, Allen, P G, Bucher, J J, Craig, I M, Edelstein, Norman M, Shuh, David K, Ewing, R C, Wang, L M, Vance, Eric R, & James C. Marra, Gregory T. Chandler. Distribution and Solubility of Radionuclides in Waste Forms for Disposition of Plutonium and Spent Nuclear Fuels: Preliminary Results. United States.
Feng, Xiangdong, Li, Hong, Davis, L L, Li, Liyu, Darab, John G, Schweiger, Michael J, Vienna, John D, Bunker, Bruce C, Allen, P G, Bucher, J J, Craig, I M, Edelstein, Norman M, Shuh, David K, Ewing, R C, Wang, L M, Vance, Eric R, and James C. Marra, Gregory T. Chandler. 1999.
"Distribution and Solubility of Radionuclides in Waste Forms for Disposition of Plutonium and Spent Nuclear Fuels: Preliminary Results". United States.
@article{osti_15001780,
title = {Distribution and Solubility of Radionuclides in Waste Forms for Disposition of Plutonium and Spent Nuclear Fuels: Preliminary Results},
author = {Feng, Xiangdong and Li, Hong and Davis, L L and Li, Liyu and Darab, John G and Schweiger, Michael J and Vienna, John D and Bunker, Bruce C and Allen, P G and Bucher, J J and Craig, I M and Edelstein, Norman M and Shuh, David K and Ewing, R C and Wang, L M and Vance, Eric R and James C. Marra, Gregory T. Chandler},
abstractNote = {Successful immobilization of actinides (Am, Cm, Th, Pu, U, Np, etc.) in crystalline and amorphous host matrices with appropriate neutron absorbers (B, Hf, Gd, etc.) requires sound scientific knowledge of the local chemical environments of both the actinides (An) and the neutron absorbers and their interaction with the host matrices. This understanding leads to a more systematic and efficient approach to predicting solubilities than the strictly empirical approach currently used. The goals of this ongoing research are to determine solubility limits of representative actinides (Pu and U) and neutron absorbers (Hf and Gd) in crystalline and amorphous matrices and to determine solution mechanisms of these species in the two types of systems. Understanding of the chemical systematics of in the two systems will make it possible to calculate the solubility of actinides, neutron absorbers, and, we would suggest, other metal species in glass and ceramic waste form, which have been determined empirically for the past. The research results of the ongoing project will be presented, including solubility of neutron absorbers, Hf(IV) and Gd(III), and local structures of these species in comparison to those of Pu(IV) and Pu(III) in glass. Effect of glass composition, in terms of peralkallinity, Na2O/(Na2O+Al2O3), on dissolution of Hf(IV) and Gd(III)and glass microstructure development will be also presented.},
doi = {},
url = {https://www.osti.gov/biblio/15001780},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Fri Jan 01 00:00:00 EST 1999},
month = {Fri Jan 01 00:00:00 EST 1999}
}