Denitration of simulated radioactive liquid waste

Mira Ristić, Svetozar Musić, Marijan Marciuš, Stjepko Krehula, Ernő Kuzmann, Zoltán Homonnay

Research output: Contribution to journalArticle

Abstract

Radioactive liquid wastes containing large amounts of nitric acid (approx. 4–7 M) generated in the nuclear fuel cycle are very undesirable by-products. Denitration of highly acidic radioactive liquid wastes with organic reducing agents has several advantages, such as a significant pH increase, possibility of separation of radioisotopes which can be utilized in other technologies, reduction of volatility of radioisotopes and fixation of certain mono- and divalent radioisotopes with zeolite. In the present work some aspects of denitration of simulated radioactive liquid wastes at laboratory level were investigated. Denitration of HNO3 with formic acid was investigated for different [HCOOH]/[HNO3] ratios. The changes in the induction time, pH increase and volume reduction were determined. It was shown that by the denitration of simulated radioactive liquid waste high pH values could be achieved which in real systems would create more possibilities in radioactive waste management. Analysis of solid phases formed after the oxidation of excess HCOOH with H2O2 showed the presence of amorphous fraction as well as goethite and hematite phases, which could remove different radioactive cations from the liquid phase. The immobilization of simulated solid radioactive waste with borosilicate glass matrix was also shown.

Original languageEnglish
JournalJournal of Radioanalytical and Nuclear Chemistry
DOIs
Publication statusAccepted/In press - Jan 1 2019

Fingerprint

Radioactive Waste
Denitrification
Radioisotopes
Liquids
formic acid
Radioactive wastes
Zeolites
Nitric Acid
Borosilicate glass
Waste Management
Formic acid
Hematite
Reducing Agents
Solid Waste
Nuclear fuels
Reducing agents
Solid wastes
Waste management
Nitric acid
Volatilization

Keywords

  • Borosilicate glass
  • Denitration
  • Formic acid
  • Radioactive liquid waste

ASJC Scopus subject areas

  • Analytical Chemistry
  • Nuclear Energy and Engineering
  • Radiology Nuclear Medicine and imaging
  • Pollution
  • Spectroscopy
  • Public Health, Environmental and Occupational Health
  • Health, Toxicology and Mutagenesis

Cite this

Denitration of simulated radioactive liquid waste. / Ristić, Mira; Musić, Svetozar; Marciuš, Marijan; Krehula, Stjepko; Kuzmann, Ernő; Homonnay, Zoltán.

In: Journal of Radioanalytical and Nuclear Chemistry, 01.01.2019.

Research output: Contribution to journalArticle

@article{c9c608459f1f43cab24c0617a2a62a49,
title = "Denitration of simulated radioactive liquid waste",
abstract = "Radioactive liquid wastes containing large amounts of nitric acid (approx. 4–7 M) generated in the nuclear fuel cycle are very undesirable by-products. Denitration of highly acidic radioactive liquid wastes with organic reducing agents has several advantages, such as a significant pH increase, possibility of separation of radioisotopes which can be utilized in other technologies, reduction of volatility of radioisotopes and fixation of certain mono- and divalent radioisotopes with zeolite. In the present work some aspects of denitration of simulated radioactive liquid wastes at laboratory level were investigated. Denitration of HNO3 with formic acid was investigated for different [HCOOH]/[HNO3] ratios. The changes in the induction time, pH increase and volume reduction were determined. It was shown that by the denitration of simulated radioactive liquid waste high pH values could be achieved which in real systems would create more possibilities in radioactive waste management. Analysis of solid phases formed after the oxidation of excess HCOOH with H2O2 showed the presence of amorphous fraction as well as goethite and hematite phases, which could remove different radioactive cations from the liquid phase. The immobilization of simulated solid radioactive waste with borosilicate glass matrix was also shown.",
keywords = "Borosilicate glass, Denitration, Formic acid, Radioactive liquid waste",
author = "Mira Ristić and Svetozar Musić and Marijan Marciuš and Stjepko Krehula and Ernő Kuzmann and Zolt{\'a}n Homonnay",
year = "2019",
month = "1",
day = "1",
doi = "10.1007/s10967-019-06736-x",
language = "English",
journal = "Journal of Radioanalytical and Nuclear Chemistry",
issn = "0022-4081",
publisher = "Elsevier BV",

}

TY - JOUR

T1 - Denitration of simulated radioactive liquid waste

AU - Ristić, Mira

AU - Musić, Svetozar

AU - Marciuš, Marijan

AU - Krehula, Stjepko

AU - Kuzmann, Ernő

AU - Homonnay, Zoltán

PY - 2019/1/1

Y1 - 2019/1/1

N2 - Radioactive liquid wastes containing large amounts of nitric acid (approx. 4–7 M) generated in the nuclear fuel cycle are very undesirable by-products. Denitration of highly acidic radioactive liquid wastes with organic reducing agents has several advantages, such as a significant pH increase, possibility of separation of radioisotopes which can be utilized in other technologies, reduction of volatility of radioisotopes and fixation of certain mono- and divalent radioisotopes with zeolite. In the present work some aspects of denitration of simulated radioactive liquid wastes at laboratory level were investigated. Denitration of HNO3 with formic acid was investigated for different [HCOOH]/[HNO3] ratios. The changes in the induction time, pH increase and volume reduction were determined. It was shown that by the denitration of simulated radioactive liquid waste high pH values could be achieved which in real systems would create more possibilities in radioactive waste management. Analysis of solid phases formed after the oxidation of excess HCOOH with H2O2 showed the presence of amorphous fraction as well as goethite and hematite phases, which could remove different radioactive cations from the liquid phase. The immobilization of simulated solid radioactive waste with borosilicate glass matrix was also shown.

AB - Radioactive liquid wastes containing large amounts of nitric acid (approx. 4–7 M) generated in the nuclear fuel cycle are very undesirable by-products. Denitration of highly acidic radioactive liquid wastes with organic reducing agents has several advantages, such as a significant pH increase, possibility of separation of radioisotopes which can be utilized in other technologies, reduction of volatility of radioisotopes and fixation of certain mono- and divalent radioisotopes with zeolite. In the present work some aspects of denitration of simulated radioactive liquid wastes at laboratory level were investigated. Denitration of HNO3 with formic acid was investigated for different [HCOOH]/[HNO3] ratios. The changes in the induction time, pH increase and volume reduction were determined. It was shown that by the denitration of simulated radioactive liquid waste high pH values could be achieved which in real systems would create more possibilities in radioactive waste management. Analysis of solid phases formed after the oxidation of excess HCOOH with H2O2 showed the presence of amorphous fraction as well as goethite and hematite phases, which could remove different radioactive cations from the liquid phase. The immobilization of simulated solid radioactive waste with borosilicate glass matrix was also shown.

KW - Borosilicate glass

KW - Denitration

KW - Formic acid

KW - Radioactive liquid waste

UR - http://www.scopus.com/inward/record.url?scp=85074029215&partnerID=8YFLogxK

UR - http://www.scopus.com/inward/citedby.url?scp=85074029215&partnerID=8YFLogxK

U2 - 10.1007/s10967-019-06736-x

DO - 10.1007/s10967-019-06736-x

M3 - Article

AN - SCOPUS:85074029215

JO - Journal of Radioanalytical and Nuclear Chemistry

JF - Journal of Radioanalytical and Nuclear Chemistry

SN - 0022-4081

ER -