The Effect of the pressure broadening for isotopic analysis using diode laser

Kuwahara, Akira; Aiba, Yasuaki*; Matsui, Makoto*; Nankawa, Takuya

no journal, , 

no abstracts in English

Development of corrosion detection technology on drum inner surface by SH wave

Nakanishi, Yoshiki

no journal, , 

no abstracts in English

Research and development on dismantling technologies for gloveboxes; Examination of separation and transfer technologies for a glovebox

Yoshida, Masato

no journal, , 

no abstracts in English

Development of an ultra compact device using liquid electrode plasma for radioactive element analysis

Do, V. K.; Yamamoto, Masahiko; Taguchi, Shigeo; Kuno, Takehiko; Surugaya, Naoki; Takamura, Yuzuru*

no journal, , 

Commercial ICP AES is often applied for analysis of radioactive nuclides present in the waste stream. However, the instrument is bulky with auxiliary equipment. Consequently, it is difficult to maintain or replace those instruments in a shielded cell or a glove box. A novel liquid electrode plasma (LEP) would be a suitable option instead of ICP. LEP is compact to be easily installed, maintained and operated in a shielded cell or a glove box because the method does not require plasma gas, a nebulizer or large power supply. LEP allows only L-level waste emission due to the use of microchannel. In the study, we utilized LEP as an excitation source for analysis of radioactive nuclides. The newly installed instrument was characterized by determining cesium and strontium in a highly active waste simulated sample. The obtained result is promising for further application of LEP in the field of radiochemical analysis.

Development of realized random model for coated fuel particle of prismatic HTGR

Ho, H. Q.; Honda, Yuki; Goto, Minoru; Takada, Shoji; Ishitsuka, Etsuo

no journal, , 

Investigation to enhance performance of HTGR fuel

Mizuta, Naoki; Ueta, Shohei; Aihara, Jun; Shibata, Taiju

no journal, , 

JAEA has performed the research and development of the high-packing fraction fuel compact to prolong an operation cycles of HTGR. In this study, the fuel compacts were fabricated with CFP packing fraction targeted at 33 percent to confirm the feasibility of fabrication technology of the high-packing fraction fuel compact. SiC layer defective fraction, compressive strength and internal CFP distribution of the compact were evaluated. As a result, the fuel compacts showed as same level of SiC layer defective fraction as that of HTTR first loading fuel, and larger compressive strength than the HTTR fuel criteria. Uniformity of internal CFP distribution of the fuel compact was confirmed by ceramography. By the above results, the feasibility of fabrication technology for the high-packing fraction fuel compact was confirmed.

Seawater corrosion behavior evaluation of BWR core material

Shizukawa, Yuta; Sekio, Yoshihiro; Yamagata, Ichiro; Akasaka, Naoaki; Maeda, Koji

no journal, , 

The upper plug of a fuel rod used for the spent fuel pool (SFP) of Unit 4 in Fukushima Daiichi Nuclear Plant (1F) consists of Zircaloy-2 bolt and SUS304L nut, and it forms the screw-gap structure. Therefore, when seawater left in this gap structure by a seawater injection after an accident, crevice corrosion might occur. It may have an influence on the integrity of a fuel assembly stored in common pool. In this study, the systematic determining the repassivation potential for crevice corrosion of SUS304L and Zircaloy-2 samples. From the result, SUS304L/SUS304L clearance specimen indicates the tendency of corrosion to progress at 50C, Chloride ion concentration 10 ppm. SUS304L/SUS304L clearance specimen and SUS304L/Zircaloy-2 clearance specimen show the tendency not to corrode at 80C, Chloride ion concentration 10 ppm.

Development of a method to treat the radioactive liquid waste containing chloride ions generated by Pyroprocessing

Tada, Kohei; Kitawaki, Shinichi; Watanabe, So; Hinai, Hiroshi; Shibata, Atsuhiro; Nomura, Kazunori

no journal, , 

no abstracts in English

Research on the radionuclide concentrations in flatfish

Matsubara, Natsumi; Nagaoka, Mika; Fujita, Hiroki; Nakano, Masanao

no journal, , 

no abstracts in English

Interrelationship between thermal and electrical conductivity of (Dy,Zr)N solid solution simulating nitride fuel for MA transmutation

Takaki, Seiya; Takano, Masahide

no journal, , 

Nitride fuel with ZrN matrix have been studied for transmutation of minor actinide (MA). These are supposed to be designed as ZrN solid solution or TiN compounds with MA nitride from 20 mol% to 40 mol%. From the above, composition and temperature dependence of thermal conductivity for safety evaluation of the fuel have been studied with a little of MA. In future, it is important to understand the heat conduction mechanism in detail when evaluating irradiation effect on thermal conductivity. In the present study, we are aimed to clarify composition and temperature dependence of thermal conductivity of DyZrN solid solution as surrogate nitride fuel with MA in order to understand the dependence of the MA nitride fuel physically.

Remote radiation imaging system using a multicopter UAV

Sato, Yuki; Ozawa, Shingo*; Terasaka, Yuta; Kaburagi, Masaaki; Miyamura, Hiroko; Tanifuji, Yuta; Kawabata, Kuniaki; Izumi, Ryo*; Suzuki, Toshikazu*; Torii, Tatsuo

no journal, , 

no abstracts in English