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Task Force on Writing Textbook of Nuclear Fuel Materials
JAEA-Review 2020-007, 165 Pages, 2020/07
JAEA-Review-2020-007.pdf:6.63MB
The present textbook was written by Task Force on Writing Textbook of Nuclear Fuel Materials at the Nuclear Science Research Institute in order to improve technological abilities of engineers and researchers who handle nuclear fuel materials. The taskforce consists of young and middle class engineers each having certification for chief engineer of nuclear fuel. The present textbook mainly deals with uranium and plutonium, and shows their nuclear properties, physical and chemical properties, and radiation effects on materials and human body. It also presents basic matters for safety handling of nuclear fuel materials, such as handling of nuclear fuel materials with hood and glovebox, important points in storage and transportation of nuclear fuel materials, radioactive waste management, radiation safety management, and emergency management. Furthermore, incident cases at domestic and foreign nuclear fuel materials facilities are compiled to learn from the past.
Marufuji, Takato; Sato, Takumi; Ito, Hideaki; Suzuki, Hisashi; Fujishima, Tadatsune; Nakano, Tomoyuki
JAEA-Technology 2019-006, 22 Pages, 2019/05
JAEA-Technology-2019-006.pdf:2.84MB
Radioactive contamination incident occurred at Plutonium Fuel Research Facility (PFRF) in Oarai Research and Development Institute, Japan Atomic Energy Agency on June 6, 2017. During inspection work of storage container containing nuclear fuel materials, the PVC bag packaging in the storage container ruptured when a worker opened the lid in the hood, and a part of contents was spattered over the room. The cause of the increase of internal pressure of the storage container was gas generation by alpha radiolysis of the epoxy resin mixed with nuclear fuel materials. Opening inspection of about 70 similar containers stored in PFRF has been planned to confirm the condition of the contents and to stabilize the stored materials containing organic compounds. For safe and reliable open inspection of the storage containers with high internal pressure in the glove box, it is necessary to develop a pressure-resistant chamber in which the storage containers are opened and the contents are inspected under gastight condition. This report summarizes the concerns and countermeasures of the chamber design and the design results of the chamber.
Sakaba, Nariaki; Furusawa, Takayuki; Kawamoto, Taiki; Ishii, Yoshiki; Ota, Yukimaru
Nuclear Engineering and Design, 233(1-3), p.147 - 154, 2004/10
Times Cited Count：10 Percentile：55.72(Nuclear Science & Technology)The HTTR mainly consists of the core components, reactor pressure vessel, cooling systems, instrumentation and control systems, and containment structures. The design of remaining utility systems is described in this paper. They are: auxiliary helium systems which include the helium purification system, the helium sampling system, and the helium storage and supply system; fuel handling and storage system. The helium purification systems are installed in the primary and secondary helium cooling systems in order to reduce the quantity of chemical impurities. The helium sampling systems monitor the concentration of impurities. The helium storage and supply systems keep the steady pressure of the helium system during the normal operation. The fuel handling and storage system is utilised to handle the new and spent fuels safely and reliably.
Tachimori, Shoichi
JAERI-Research 2001-048, 23 Pages, 2001/10
JAERI-Research-2001-048.pdf:1.88MB
A new chemical process, ARTIST process, is proposed for the treatment of spent nuclear fuel. The main concept of the ARTIST process is to recover and stock all actinides (Ans) in two groups, uranium (U) and a mixture of transuranics (TRU), to preserve their resource value and to dispose solely fission products (FPs). The process composed of two main steps, an U exclusive isolation and a total recovery of TRU; which copes with the nuclear non-proliferation measures, and additionally Pu separation process and soft N-donor process if requested, and optionally processes for separation of long-lived FPs. These An products: U-product and TRU-product, are to be solidified by calcination and allowed to the interim stockpile for future utilization. These separations are achieved by use of amidic extractants in accord with the CHON principle. The technical feasibility of the ARTIST process was explained by the performance of both the branched-alkyl monoamides the diglycolic amide (TODGA) in thorough extraction of all TRU by tridentate fashon.
Sawa, Kazuhiro; Fujikawa, Seigo; Yoshimuta, Shigeharu*; Kato, Shigeru*
JAERI-Research 2001-034, 20 Pages, 2001/05
JAERI-Research-2001-034.pdf:1.68MB
no abstracts in English
Kurosawa, Masayoshi; Naito, Yoshitaka; Suyama, Kenya; *; Suzuki, Katsuo*; *
Nihon Genshiryoku Gakkai-Shi, 40(6), p.486 - 494, 1998/00
Times Cited Count：0 Percentile：0.01(Nuclear Science & Technology)no abstracts in English
Okuno, Hiroshi; *
Criticality Safety Challenges in the Next Decade, 0, p.150 - 155, 1997/00
no abstracts in English
Nishimura, Mitsuhiro
Genshiryoku Kogyo, 38(4), p.29 - 31, 1992/04
no abstracts in English
Shirai, Eiji; ; Kodaira, Tsuneo; Sato, Hiroshi
Proc. of the 3rd Int. Conf. on Nuclear Fuel Reprocessing and Waste Management: RECOD91,Vol. l, p.367 - 370, 1991/00
no abstracts in English
Kawasaki, Satoru; Nakamura, Jinichi
IAEA-SR-171, 27 Pages, 1990/00
no abstracts in English
*;
JAERI-M 85-137, 24 Pages, 1985/09
no abstracts in English
; *;
JAERI-M 85-002, 62 Pages, 1985/02
no abstracts in English
Ishii, Junichi; Izawa, Kazuhiko; Okubo, Takuya; Ogawa, Kazuhiko
no journal, ,
For compliance with the new regulatory requirements in Japan, the Static Critical Experiment Facility (STACY) has been remodeling the existing fuel storages. In the remodeling, the existing fuel storage spaces, to which shape and dimension management are applied, are designed to add a neutron absorber for the critical control, taking into account the case of shape and dimension collapse. In order to confirm the validity of the criticality safety design, subcritical calculations were performed. In the calculations, the Japanese Evaluated Nuclear Data Library, JENDL-3.2, was used to cross reference the data. The neutron multiplication factor was calculated using a continuous-energy Monte Carlo code, MVP, and PIJ code in the SRAC code system. It has been confirmed from the results that all fuel storages comply with the safety criteria required to ensure subcriticality.
