Annual report on the effluent control of low level liquid waste in Nuclear Fuel Cycle Engineering Laboratories FY2014

Watanabe, Hitoshi; Nakano, Masanao; Fujita, Hiroki; Kono, Takahiko; Inoue, Kazumi; Yoshii, Hideki*; Otani, Kazunori*; Hiyama, Yoshinori*; Kikuchi, Masaaki*; Sakauchi, Nobuyuki*; et al.

JAEA-Review 2015-030, 115 Pages, 2015/12

JAEA-Review-2015-030.pdf:25.28MB

Based on the regulations (the safety regulation of Tokai reprocessing plant, the safety regulation of nuclear fuel material usage facilities, the radiation safety rule, the regulation about prevention from radiation hazards due to radioisotopes, which are related with the nuclear regulatory acts, the local agreement concerning with safety and environment conservation around nuclear facilities, the water pollution control law, and bylaw of Ibaraki prefecture), the effluent control of liquid waste discharged from the Nuclear Fuel Cycle Engineering Laboratories of Japan Atomic Energy Agency has been performed. This report describes the effluent control results of the liquid waste in the fiscal year 2014. In this period, the concentrations and the quantities of the radioactivity in liquid waste discharged from the reprocessing plant, the plutonium fuel fabrication facilities, and the other nuclear fuel material usage facilities were much lower than the limits authorized by the above regulations.

An Investigation on debris bed self-leveling behavior with non-spherical particles

Cheng, S.; Tagami, Hirotaka; Yamano, Hidemasa; Suzuki, Toru; Tobita, Yoshiharu; Takeda, Shohei*; Nishi, Shimpei*; Nishikido, Tatsuya*; Zhang, B.*; Matsumoto, Tatsuya*; et al.

Journal of Nuclear Science and Technology, 51(9), p.1096 - 1106, 2014/09

AA2013-0303.pdf:1.68MB

https://doi.org/10.1080/00223131.2014.910478

Annual report on the effluent control of low level liquid waste in Nuclear Fuel Cycle Engineering Laboratories FY2012

Sumiya, Shuichi; Watanabe, Hitoshi; Miyagawa, Naoto; Nakano, Masanao; Fujita, Hiroki; Kono, Takahiko; Inoue, Kazumi; Yoshii, Hideki; Otani, Kazunori*; Hiyama, Yoshinori*; et al.

JAEA-Review 2013-041, 115 Pages, 2014/01

JAEA-Review-2013-041.pdf:19.01MB

Based on the regulations (the safety regulation of Tokai reprocessing plant, the safety regulation of nuclear fuel material usage facilities, the radiation safety rule, the regulation about prevention from radiation hazards due to radioisotopes, which are related with the nuclear regulatory acts, and the local agreement concerning with safety and environment conservation around nuclear facilities, the water pollution control law, and bylaw of Ibaraki prefecture), this report describes the effluent control results of liquid waste discharged from the JAEA's Nuclear Fuel Cycle Engineering Laboratories in the fiscal year 2012, from 1st April 2012 to 31st March 2013. In this period, the concentrations and the quantities of the radioactivity in liquid waste discharged from the reprocessing plant, the plutonium fuel fabrication facilities, and the other facilities were much lower than the authorized limits of the above regulations.

Issues to be verified by IFMIF prototype accelerator for engineering validation

Sugimoto, Masayoshi; Imai, Tsuyoshi; Okumura, Yoshikazu; Nakayama, Koichi*; Suzuki, Shohei*; Saigusa, Mikio*

Journal of Nuclear Materials, 307-311(Part2), p.1691 - 1695, 2002/12

https://doi.org/10.1016/S0022-3115(02)01023-1

International Fusion Materials Irradiation Facility (IFMIF) is an accelerator-based intense neutron source for fusion reactor materials development. Each one of the two accelerator modules needs to have a capability to provide the 40MeV/125mA deuteron beam continuously. Although the technology to produce the 7MeV/100mA proton beam is already verified using 350 MHz linac in the past, an engineering study using a prototype is necessary to verify the performance of IFMIF 175 MHz deuteron linac, and Engineering Validation Phase (EVP) is planned for this purpose. Some critical design parameters, like final and transition energies of linacs or RF source characteristics, are needed to be optimised for the prototype. As it is also important to verify the essential component technology, e.g. ion source, RFQ beam matching, rf system components, etc., the present status and expected results of such undergoing verification tests are described. An integrated concept of prototype accelerator is shown as a Japanese proposal for EVP to provide for the international discussion.

Design of high temperature irradiation materials inspection cells (spent fuel inspection cells) in the High Temperature engineering Test Reactor

Ino, Hiroichi*; Ueta, Shohei; Suzuki, Hiroshi; Tobita, Tsutomu*; Sawa, Kazuhiro

JAERI-Tech 2001-083, 46 Pages, 2002/01

JAERI-Tech-2001-083.pdf:6.31MB

no abstracts in English

An Investigation of fuel and fission product behavior in start-up test of HTTR, 1; Result up to 15MW operation

Sawa, Kazuhiro; Tobita, Tsutomu*; Ueta, Shohei; Suzuki, Shuichi*; Sumita, Junya; Sekita, Kenji; Aoki, Kazunori*; Ouchi, Hiroshi

JAERI-Research 2001-002, 33 Pages, 2001/02

JAERI-Research-2001-002.pdf:1.42MB

no abstracts in English

Study on characteristics of particle-bed self-leveling driven by gas injection

Nakamura, Yuya*; Gondai, Yoji*; Cheng, S.*; Takeda, Shohei*; Zhang, B.*; Matsumoto, Tatsuya*; Morita, Koji*; Yamano, Hidemasa; Tagami, Hirotaka; Suzuki, Toru; et al.

no journal, , 

In order to clarify the characteristics of debris bed behavior in the post accident heat removal phase in the core disruptive accidents of FBR, an experimental study to simulate the coolant boiling in debris bed by gas injection from the bottom of the bed and basic knowledge on the self-leveling characteristic for large vapor velocity was obtained.

Criticality control technique development for Fukushima Daiichi fuel debris, 55; Evaluation for the drying behavior of fuel debris covered with water glass based neutron absorber

Suzuki, Seiya; Arai, Yoichi; Okamura, Nobuo; Watanabe, Masayuki; Kawano, Shohei*; Kawarada, Yoshiyuki*

no journal, , 

The water glass type neutron absorber has been developed as a measure to precaution of re-criticality during fuel debris retrieval. Since the neutron absorber covers the surface of the fuel debris, the drying of the water content of the fuel debris was suggested to be hindered. The drying test using the mock test piece was carried out in order to evaluate the effect on the drying behavior when the surface of the fuel debris is covered with the neutron absorber. We investigate the drying characteristic curve of the mock test piece by thermogravimetric analysis, and report the evaluation of drying behavior.