skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: Dissolution of two NWCF calcines: Extent of dissolution and characterization of undissolved solids

Abstract

A study was undertaken to determine the dissolution characteristics of two NWCF calcine types. A two-way blended calcine made from 4 parts nonradioactive aluminum nitrate and one part WM-102 was studied to determine the extent of dissolution for aluminum-type calcines. A two-way blend of 3.5 parts fluorinel waste from WM-187 and 1 part sodium waste from WM-185 was used to determine the extent of dissolution for zirconium-type calcines. This study was necessary to develop suitable aqueous separation flowsheets for the partitioning of actinides and fission products from ICPP calcines and to determine the disposition of the resulting undissolved solids (UDS). The dissolution flowsheet developed by Herbst was used to dissolve these two NWCF calcine types. Results show that greater than 95 wt% of aluminum and zirconium calcine types were dissolved after a single batch contact with 5 M HNO{sub 3}. A characterization of the UDS indicates that the weight percent of TRU elements in the UDS resulting from both calcine type dissolutions increases by approximately an order of magnitude from their concentrations prior to dissolution. Substantial activities of cesium and strontium are also present in the UDS resulting from the dissolution of both calcine types. Multiple TRU, Cs, and Srmore » analyses of both UDS types show that these solids are relatively homogeneous. From this study, it is estimated that between 63.5 and 635 cubic meters of UDS will be generated from the dissolution of 3800 M{sub 3} of calcine. The significant actinide and fission product activities in these UDS will preclude their disposal as low-level waste. If the actinide and fission activity resulting from the UDS is the only considered source in the dissolved calcine solutions, an estimated 99.9 to 99.99 percent of the solids must be removed from this solution for it to meet non-TRU Class A low-level waste.« less

Authors:
; ;  [1]
  1. and others
Publication Date:
Research Org.:
EG and G Idaho, Inc., Idaho Falls, ID (United States)
Sponsoring Org.:
USDOE, Washington, DC (United States)
OSTI Identifier:
152645
Report Number(s):
INEL-95/0098
ON: DE96004069; TRN: 96:001556
DOE Contract Number:  
AC07-94ID13223
Resource Type:
Technical Report
Resource Relation:
Other Information: PBD: Jan 1995
Country of Publication:
United States
Language:
English
Subject:
05 NUCLEAR FUELS; IDAHO CHEMICAL PROCESSING PLANT; RADIOACTIVE WASTE MANAGEMENT; HIGH-LEVEL RADIOACTIVE WASTES; RADIOACTIVE WASTE PROCESSING; SEPARATION PROCESSES; CALCINED WASTES; ACTINIDES

Citation Formats

Brewer, K N, Herbst, R S, and Tranter, T J. Dissolution of two NWCF calcines: Extent of dissolution and characterization of undissolved solids. United States: N. p., 1995. Web. doi:10.2172/152645.
Brewer, K N, Herbst, R S, & Tranter, T J. Dissolution of two NWCF calcines: Extent of dissolution and characterization of undissolved solids. United States. https://doi.org/10.2172/152645
Brewer, K N, Herbst, R S, and Tranter, T J. 1995. "Dissolution of two NWCF calcines: Extent of dissolution and characterization of undissolved solids". United States. https://doi.org/10.2172/152645. https://www.osti.gov/servlets/purl/152645.
@article{osti_152645,
title = {Dissolution of two NWCF calcines: Extent of dissolution and characterization of undissolved solids},
author = {Brewer, K N and Herbst, R S and Tranter, T J},
abstractNote = {A study was undertaken to determine the dissolution characteristics of two NWCF calcine types. A two-way blended calcine made from 4 parts nonradioactive aluminum nitrate and one part WM-102 was studied to determine the extent of dissolution for aluminum-type calcines. A two-way blend of 3.5 parts fluorinel waste from WM-187 and 1 part sodium waste from WM-185 was used to determine the extent of dissolution for zirconium-type calcines. This study was necessary to develop suitable aqueous separation flowsheets for the partitioning of actinides and fission products from ICPP calcines and to determine the disposition of the resulting undissolved solids (UDS). The dissolution flowsheet developed by Herbst was used to dissolve these two NWCF calcine types. Results show that greater than 95 wt% of aluminum and zirconium calcine types were dissolved after a single batch contact with 5 M HNO{sub 3}. A characterization of the UDS indicates that the weight percent of TRU elements in the UDS resulting from both calcine type dissolutions increases by approximately an order of magnitude from their concentrations prior to dissolution. Substantial activities of cesium and strontium are also present in the UDS resulting from the dissolution of both calcine types. Multiple TRU, Cs, and Sr analyses of both UDS types show that these solids are relatively homogeneous. From this study, it is estimated that between 63.5 and 635 cubic meters of UDS will be generated from the dissolution of 3800 M{sub 3} of calcine. The significant actinide and fission product activities in these UDS will preclude their disposal as low-level waste. If the actinide and fission activity resulting from the UDS is the only considered source in the dissolved calcine solutions, an estimated 99.9 to 99.99 percent of the solids must be removed from this solution for it to meet non-TRU Class A low-level waste.},
doi = {10.2172/152645},
url = {https://www.osti.gov/biblio/152645}, journal = {},
number = ,
volume = ,
place = {United States},
year = {Sun Jan 01 00:00:00 EST 1995},
month = {Sun Jan 01 00:00:00 EST 1995}
}