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JAEA Reports

Improvement of the RuO$$_{4}$$ vapor-liquid transfer model in the chemical behavior analysis code SCHERN for accident of evaporation to dryness by boiling of reprocessed high level liquid waste

Yoshida, Kazuo; Hiyama, Mina*; Tamaki, Hitoshi

JAEA-Research 2025-011, 25 Pages, 2025/11

JAEA-Research-2025-011.pdf:2.15MB

An accident of evaporation to dryness by boiling of high-level radioactive liquid waste (HLLW) is postulated as one of the severe accidents caused by the loss of cooling function at a fuel reprocessing plant. In this case, volatile radioactive materials, such as ruthenium (RuO$$_{4}$$) are released from the tanks with water and nitric-acid mixed vapor into the atmosphere. Accurate quantitative estimation of released Ru is one of the important issues for risk assessment of those facilities. RuO$$_{4}$$ is expected to be absorbed chemically into water dissolving nitrous acid (HNO$$_{2}$$). This behavior has been experimentally confirmed and plays an important role in the migration of Ru in the facility. A new model has been proposed as a chemical and physical absorption model based on the experimental results of the migration of RuO$$_{4}$$ into nitric acid-water mixtures. In this study, to improve the analytical performance of SCHERN, these new analytical models have been incorporated and attempted to analyze the behavior of RuO$$_{4}$$ in each phase. As a result, it has been observed a tendency that HNO$$_{2}$$ in the liquid phase increases rapidly during the late boiling phase, when RuO$$_{4}$$ release increases rapidly, and confirmed that this HNO$$_{2}$$ concentration change significantly affects the subsequent migration behavior of RuO$$_{4}$$. These results indicate that it is essential to improve the analytical accuracy of the chemical behavior of HNO$$_{2}$$ in each phase.

Journal Articles

Effect of nitrous ion on oxidation of oxidizing-metallic ion in nitric acid solution

Irisawa, Eriko; Seki, Masaharu*; Ueno, Fumiyoshi; Kato, Chiaki; Motooka, Takafumi; Abe, Hitoshi

Proceedings of 21st International Conference & Exhibition; Nuclear Fuel Cycle for a Low-Carbon Future (GLOBAL 2015) (USB Flash Drive), p.1108 - 1112, 2015/09

Journal Articles

Study on electrolytic reduction of pertechnetate in nitric acid solution for electrolytic extraction of rare metals for future reprocessing

Asakura, Toshihide; Kim, S.-Y.; Morita, Yasuji; Ozawa, Masaki*

Journal of Nuclear and Radiochemical Sciences, 6(3), p.267 - 269, 2005/12

An electrolytic extraction (EE) method, i.e. electro-reductive deposition, of Tc from nitric acid aqueous solution was studied for future reprocessing. After 30 min of constant potential electrolysis by carbon electrode at -0.3 V vs. SSE (Standard Silver Electrode), Tc concentration in 3 M nitric acid decreased to 93 % of the initial value, which corresponds to 7 % of deposition. With co-existence of Pd, the value reached to 15 % of deposition equivalent by electrolysis at $$pm$$0.0 V vs. SSE for 60 min. An acceleration effect of Pd on Tc deposition (promoter effect) was suggested. The concentration, however, increased to the initial value after further electrolysis and competing re-dissolution of deposited Tc was also suggested. In cyclic voltammetry measurements, it was found that the deposit from Tc-Pd-Ru-Rh solution dissolved easier than that from Pd-Ru-Rh did. In electrolyzed Tc solution, an absorption peak at 482 nm was found. It can be attributed to the complex with nitrite anion, and the complex formation is proposed as one possible mechanism of Tc re-dissolution.

JAEA Reports

Development of simulation code for MOX dissolution using silver-mediated electrochemical method (Contract research)

Kida, Takashi; Umeda, Miki; Sugikawa, Susumu

JAERI-Data/Code 2003-001, 29 Pages, 2003/03

JAERI-Data-Code-2003-001.pdf:6.34MB

MOX dissolution using silver-mediated electrochemical method will be employed for the preparation of plutonium nitrate solution in the criticality safety experiments in NUCEF. A simulation code for the MOX dissolution has been developed for the operating support. In this report an outline of the simulation code is proposed and a comparison with the experimental data and a parameter study on the MOX dissolution rate are described.The principle of this code is based on Zundelevich's model for PuO$$_{2}$$ dissolution using Ag$$^{2+}$$. The influence of nitrous acid on the material balance of Ag$$^{2+}$$ and the surface area of MOX powder on the basis of particle size distribution are taken into consideration in this model. A comparison with experimental data was carried out to confirm a validity of this model. It was confirmed that the behavior of MOX dissolution could adequately be simulated using the appropriate MOX dissolution rate constant. The parameters affecting the dissolution rate were studied, it was found that MOX particle size was major governing factor on the dissolution rate.

Journal Articles

Development of a new neptunium separation process by using photochemical reduction in nuclear fuel reprocessing

Uchiyama, Gunzo; Kihara, Takehiro; Hotoku, Shinobu; Fujine, Sachio; Maeda, Mitsuru

Radiochimica Acta, 81(1), p.29 - 32, 1998/00

no abstracts in English

Journal Articles

Distribution of nitrous acid between tri-n-butyl phosphate/n-dodecane and nitric acid

Uchiyama, Gunzo; Hotoku, Shinobu; Fujine, Sachio

Solvent Extr. Ion Exch., 16(5), p.1177 - 1190, 1998/00

 Times Cited Count:9 Percentile:47.62

no abstracts in English

JAEA Reports

Distribution equilibrium of nitrous acid in reprocessing solution

Hotoku, Shinobu; Kihara, Takehiro; Uchiyama, Gunzo; Fujine, Sachio; Maeda, Mitsuru

JAERI-M 93-095, 19 Pages, 1993/03

JAERI-M-93-095.pdf:0.66MB

no abstracts in English

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