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Conceptual design study and evaluation of an advanced treatment process applying a submerged combustion technique for spent solvents

Technical Report:

Abstract

An advanced treatment process based on a submerged combustion technique was proposed for spent solvents and the distillation residues containing transuranium (TRU) nuclides. A conceptual design study and the preliminary cost estimation of the treatment facility applying the process were conducted. Based on the results of the study, the process evaluation on the technical features, such as safety, volume reduction of TRU waste and economics was carried out. The key requirements for practical use were also summarized. It was shown that the process had the features as follows: the simplified treatment and solidification steps will not generate secondary aqueous wastes, the volume of TRU solid waste will be reduced less than one tenth of that of a reference technique (pyrolysis process), and the facility construction cost is less than 1 % of the total construction cost of a future large scale reprocessing plant. As for the low level wastes of calcium phosphate, it was shown that the further removal of {beta} {center_dot} {gamma} nuclides with TRU nuclides from the wastes would be required for the safety in interim storage and transportation and for the load of shielding. (author).
Authors:
Uchiyama, Gunzo; Maeda, Mitsuru; Fijine, Sachio; [1]  Chida, Mitsuhisa; Kirishima, Kenji
  1. Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment
Publication Date:
Oct 01, 1993
Product Type:
Technical Report
Report Number:
JAERI-M-93-213
Reference Number:
SCA: 052001; PA: JPN-93:011216; EDB-94:011922; ERA-19:003169; NTS-94:014127; SN: 93001119432
Resource Relation:
Other Information: PBD: Oct 1993
Subject:
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; ALPHA-BEARING WASTES; RADIOACTIVE WASTE PROCESSING; COST ESTIMATION; WASTE PROCESSING PLANTS; DESIGN; LIQUID WASTES; COMBUSTION; ORGANIC WASTES; TRANSURANIUM ELEMENTS; TBP; DISTILLATION; REPROCESSING; 052001; WASTE PROCESSING
OSTI ID:
10110181
Research Organizations:
Japan Atomic Energy Research Inst., Tokyo (Japan)
Country of Origin:
Japan
Language:
Japanese
Other Identifying Numbers:
Other: ON: DE94727629; TRN: JP9311216
Availability:
OSTI; NTIS; INIS
Submitting Site:
JPN
Size:
217 p.
Announcement Date:
Jun 30, 2005

Technical Report:

Citation Formats

Uchiyama, Gunzo, Maeda, Mitsuru, Fijine, Sachio, Chida, Mitsuhisa, and Kirishima, Kenji. Conceptual design study and evaluation of an advanced treatment process applying a submerged combustion technique for spent solvents. Japan: N. p., 1993. Web.
Uchiyama, Gunzo, Maeda, Mitsuru, Fijine, Sachio, Chida, Mitsuhisa, & Kirishima, Kenji. Conceptual design study and evaluation of an advanced treatment process applying a submerged combustion technique for spent solvents. Japan.
Uchiyama, Gunzo, Maeda, Mitsuru, Fijine, Sachio, Chida, Mitsuhisa, and Kirishima, Kenji. 1993. "Conceptual design study and evaluation of an advanced treatment process applying a submerged combustion technique for spent solvents." Japan.
@misc{etde_10110181,
title = {Conceptual design study and evaluation of an advanced treatment process applying a submerged combustion technique for spent solvents}
author = {Uchiyama, Gunzo, Maeda, Mitsuru, Fijine, Sachio, Chida, Mitsuhisa, and Kirishima, Kenji}
abstractNote = {An advanced treatment process based on a submerged combustion technique was proposed for spent solvents and the distillation residues containing transuranium (TRU) nuclides. A conceptual design study and the preliminary cost estimation of the treatment facility applying the process were conducted. Based on the results of the study, the process evaluation on the technical features, such as safety, volume reduction of TRU waste and economics was carried out. The key requirements for practical use were also summarized. It was shown that the process had the features as follows: the simplified treatment and solidification steps will not generate secondary aqueous wastes, the volume of TRU solid waste will be reduced less than one tenth of that of a reference technique (pyrolysis process), and the facility construction cost is less than 1 % of the total construction cost of a future large scale reprocessing plant. As for the low level wastes of calcium phosphate, it was shown that the further removal of {beta} {center_dot} {gamma} nuclides with TRU nuclides from the wastes would be required for the safety in interim storage and transportation and for the load of shielding. (author).}
place = {Japan}
year = {1993}
month = {Oct}
}