Consideration on stress corrosion cracking evaluation of zirconium for Fuel Reprocessing Facilities

Hashikura, Yasuaki*; Ishijima, Yasuhiro; Nakahara, Masaumi; Sano, Yuichi; Ueno, Fumiyoshi; Abe, Hitoshi

Hozengaku, 19(3), p.95 - 102, 2020/10

A plutonium concentrator was selected, and constant load tensile tests with controlled applied potentials and electrochemical tests were conducted in nitric acid and sodium nitrate solutions. From the results, a map which shows the effect of nitric acid concentration to crack initiation potential was drawn. And, it was pointed out that not only the nitric acid but also the nitrate ion coordinated to the nitrate must be considered in evaluating the possibility of stress corrosion cracking.

Electrochemical properties of zirconium in highly concentrated plutonium nitrate solution

Nakahara, Masaumi; Sano, Yuichi; Abe, Hitoshi

Progress in Nuclear Science and Technology (Internet), 5, p.52 - 55, 2018/11

https://doi.org/10.15669/pnst.5.52

For evaluating the secular change of Pu evaporator made of Zr in the commercialized nuclear fuel reprocessing plant, electrochemical experiments were carried out with Pu nitrate solutions. The open circuit potentials of Zr increased with increasing Pu, HNO concentrations and temperature. However, these experimental results imply that Zr has high corrosion resistance in Pu nitrate solutions.

Actinides recovery from irradiated fuel for SmART cycle

Sano, Yuichi; Watanabe, So; Nakahara, Masaumi; Aihara, Haruka; Takeuchi, Masayuki

Proceedings of International Nuclear Fuel Cycle Conference (GLOBAL 2017) (USB Flash Drive), 4 Pages, 2017/09

JAEA has been promoting MA recycle project using a FR fuel cycle named as SmART cycle concept. The SmART cycle contains the recovery of all actinides, in which total amount of MA is estimated to around 1-2g, at CPF from the FR Joyo spent fuel, the fabrication of MA bearing MOX fuel pellets and pins at AGF with recovered actinides, and the irradiation test of the fabricated fuels at the Joyo. In this paper, recent activities on actinides recovery in CPF, which will make a significant contribution to the SmART cycle, were summarized.

SPECT imaging of mice with Tc-radiopharmaceuticals obtained from Mo produced by Mo(n,2n)Mo and fission of U

Hashimoto, Kazuyuki; Nagai, Yasuki; Kawabata, Masako; Sato, Nozomi*; Hatsukawa, Yuichi; Saeki, Hideya; Motoishi, Shoji*; Ota, Masayuki; Konno, Chikara; Ochiai, Kentaro; et al.

Journal of the Physical Society of Japan, 84(4), p.043202_1 - 043202_4, 2015/04

https://doi.org/10.7566/JPSJ.84.043202

Tolerance of anhydrobiotic eggs of the tardigrade to extreme environments

Horikawa, Daiki*; Yamaguchi, Ayami*; Sakashita, Tetsuya; Tanaka, Daisuke*; Hamada, Nobuyuki*; Yukuhiro, Fumiko*; Kuwahara, Hirokazu*; Kunieda, Takekazu*; Watanabe, Masahiko*; Nakahara, Yuichi*; et al.

Astrobiology, 12(4), p.283 - 289, 2012/04

https://doi.org/10.1089/ast.2011.0669

We examined the hatchability of hydrated and anhydrobiotic eggs of the tardigrade to hatch after ionizing irradiation (helium ions), extremely low and high temperatures, and high vacuum. Anhydrobiotic eggs (50% lethal dose; 1690 Gy) were substantially more radioresistant than hydrated ones (50% lethal dose; 509 Gy). Anhydrobiotic eggs also have a broader temperature resistance compared with hydrated ones. Over 70% of the anhydrobiotic eggs treated at high and low temperatures, but all of the hydrated eggs failed to hatch. After exposure to high vacuum conditions, the hatchability of the anhydrobiotic eggs was comparable to that of untreated control eggs.

Nuclear-charge polarization at scission in proton-induced fission of U

Nishinaka, Ichiro; Tanikawa, Masashi*; Nagame, Yuichiro; Nakahara, Hiromichi*

European Physical Journal A, 47(1), p.1 - 8, 2011/01

https://doi.org/10.1140/epja/i2011-11001-0

The most probable charges of secondary fragments in the 11.5 MeV proton-induced fission of U were determined from the mass yields measured by the double time-of-flight method and the fractional cumulative and independent yields measured radiochemically and reported in literature. The nuclear-charge polarization of primary fragments at scission was obtained by correcting the secondary fragment mass for neutron evaporation. The results show that the nuclear-charge polarization is determined by the minimum potential energy of nuclei at scission and that it is nearly independent not only of mass and excitation energy but also of the neutron-to-proton ratio of the fissioning nucleus.

Uranium, plutonium and neptunium co-recovery with high nitric acid concentration in extraction section by simplified solvent extraction process

Nakahara, Masaumi; Sano, Yuichi

Radiochimica Acta, 97(12), p.727 - 731, 2009/12

https://doi.org/10.1524/ract.2009.1671

The behavior of Np in a simplified solvent extraction process for U, Pu, and Np co-recovery was investigated. Two approaches flow sheets, high HNO concentration of feed solution and high HNO concentration of scrubbing solution, was examined with dissolver solution of an irradiated fast reactor core fuel. It is more effective for the Np recovery under the condition of the feed solution with a high HNO concentration because the inextractable Np(V) is effectively oxidized to extractable Np(VI) in the feed solution and there is less effect of HNO at the extraction section.

U, Pu and Np co-recovery in simplified solvent extraction process; Extraction behavior of Np using high HNO concentration at extraction section

Nakahara, Masaumi; Sano, Yuichi; Koizumi, Tsutomu

JAEA-Research 2008-078, 24 Pages, 2008/10

JAEA-Research-2008-078.pdf:0.98MB

Concerning the advanced aqueous reprocessing system, we have been investigating a simplified solvent extraction process using TBP as an extractant for U, Pu and Np co-recovery. The experiment was conducted with low HNO concentration in the feed solution and high HNO concentration in the scrubbing solution, which was expected to bring a high HNO concentration into the extraction section and the efficient Np oxidation and extraction in this section. This experiment had been conducted with the dissolver solution of "JOYO" Mk-I and Mk-II irradiated MOX fuel. The Pu valence was adjusted to Pu(IV) by bubbling NOx gas into the feed solution. It was attempted to oxidize Np(V) to Np(VI) in the extraction section by adjusting HNO concentration of the feed and scrubbing solutions to 3.9M and 10M, respectively. After operation, the Np leakage to the raffinate could be kept under 6.3%. The decontamination factor of total- was 5.110 in this experiment.

Dissolution of powdered spent fuel and U crystallization from actual dissolver solution for "NEXT" process development

Nomura, Kazunori; Hinai, Hiroshi; Nakahara, Masaumi; Kaji, Naoya; Kamiya, Masayoshi; Oyama, Koichi; Sano, Yuichi; Washiya, Tadahiro; Komaki, Jun

Proceedings of 3rd International ATALANTE Conference (ATALANTE 2008) (CD-ROM), 5 Pages, 2008/05

Fluoride complexation of element 104, rutherfordium (Rf), investigated by cation-exchange chromatography

Ishii, Yasuo; Toyoshima, Atsushi; Tsukada, Kazuaki; Asai, Masato; Tome, Hayato; Nishinaka, Ichiro; Nagame, Yuichiro; Miyashita, Sunao*; Mori, Tomotaka*; Suganuma, Hideo*; et al.

Chemistry Letters, 37(3), p.288 - 289, 2008/03

https://doi.org/10.1246/cl.2008.288

We have investigated cation-exchange behavior of Rf together with the lighter homologues of the group-4 elements Zr and Hf, and the tetravalent pseudo-homologue Th, in HF/HNO solution using Automated Ion exchange separation apparatus coupled with the Detection system for Alpha spectroscopy (AIDA). The values of Zr, Hf, Th and Rf in HF/0.1 M HNO were decreased with increasing the concentration of the fluoride ion [F], indicating the formation of the fluoride complexes. The sequence of the fluoride complexation strength is Zr Hf Rf Th.