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Development of a technology and a pilot plant for treatment of small volumes of liquid radioactive waste

Abstract

The development of technology for treatment of liquid radioactive waste is described. Waste arisings are estimated. Liquid wastes of concern are mainly low active wastes according to the Bulgarian legislation. The activity is determined by the presence of {sup 134}Cs, {sup 137}Cs, {sup 60}Co, {sup 90}Sr, {sup 144}Ce, {sup 65}Zc, {sup 54}Mn, {sup 110m}Ag. Different precipitation processes are compared. The mixed iron hydroxide - calcium phosphate precipitation is determined as suitable for decontamination of the liquid radioactive waste. Effective decontamination is achieved when precipitation is followed by ion exchange. Additional increase of the decontamination is possible when sorbents are added during the precipitation step. The sorption and desorption of radionuclides on zeolites are studied. Cement solidification and thermal treatment of zeolites are studied for immobilization of radioactive material from precipitation and ion exchange. Both methods produce stable waste forms suitable for containment of the radionuclides. (author). 17 refs, 3 figs, 12 tabs.
Authors:
Stefanova, I G; Gradev, G D [1] 
  1. Bulgarian Academy of Sciences, Sofia (Bulgaria). Inst. for Nuclear Research and Nuclear Energy
Publication Date:
Feb 01, 1997
Product Type:
Technical Report
Report Number:
IAEA-TECDOC-929
Reference Number:
SCA: 052001; PA: AIX-28:034838; EDB-97:060103; SN: 97001775326
Resource Relation:
Other Information: PBD: Feb 1997; Related Information: Is Part Of Treatment technologies for low and intermediate level waste from nuclear applications. Final report of a co-ordinated research programme 1991-1996; PB: 207 p.
Subject:
05 NUCLEAR FUELS; LIQUID WASTES; DECONTAMINATION; LOW-LEVEL RADIOACTIVE WASTES; RADIOACTIVE WASTE PROCESSING; CESIUM 134; COBALT 60; EXPERIMENTAL DATA; ION EXCHANGE; PRECIPITATION; SORPTION
OSTI ID:
462476
Research Organizations:
International Atomic Energy Agency, Vienna (Austria)
Country of Origin:
IAEA
Language:
English
Other Identifying Numbers:
Journal ID: ISSN 1011-4289; Other: ON: DE97622561; TRN: XA9743748034838
Availability:
INIS; OSTI as DE97622561
Submitting Site:
INIS
Size:
pp. 163-178
Announcement Date:

Citation Formats

Stefanova, I G, and Gradev, G D. Development of a technology and a pilot plant for treatment of small volumes of liquid radioactive waste. IAEA: N. p., 1997. Web.
Stefanova, I G, & Gradev, G D. Development of a technology and a pilot plant for treatment of small volumes of liquid radioactive waste. IAEA.
Stefanova, I G, and Gradev, G D. 1997. "Development of a technology and a pilot plant for treatment of small volumes of liquid radioactive waste." IAEA.
@misc{etde_462476,
title = {Development of a technology and a pilot plant for treatment of small volumes of liquid radioactive waste}
author = {Stefanova, I G, and Gradev, G D}
abstractNote = {The development of technology for treatment of liquid radioactive waste is described. Waste arisings are estimated. Liquid wastes of concern are mainly low active wastes according to the Bulgarian legislation. The activity is determined by the presence of {sup 134}Cs, {sup 137}Cs, {sup 60}Co, {sup 90}Sr, {sup 144}Ce, {sup 65}Zc, {sup 54}Mn, {sup 110m}Ag. Different precipitation processes are compared. The mixed iron hydroxide - calcium phosphate precipitation is determined as suitable for decontamination of the liquid radioactive waste. Effective decontamination is achieved when precipitation is followed by ion exchange. Additional increase of the decontamination is possible when sorbents are added during the precipitation step. The sorption and desorption of radionuclides on zeolites are studied. Cement solidification and thermal treatment of zeolites are studied for immobilization of radioactive material from precipitation and ion exchange. Both methods produce stable waste forms suitable for containment of the radionuclides. (author). 17 refs, 3 figs, 12 tabs.}
place = {IAEA}
year = {1997}
month = {Feb}
}