Investigation of pyrometallurgical partitioning and extracting technology of irradiated fuel

Yumoto, Ryozo*; Yokochi, Yoji*; Koizumi, Masumichi*; Seki, Sadao*

PNC TJ9409 96-002, 93 Pages, 1996/03

PNC-TJ9409-96-002.pdf:2.64MB

The state of development of pyrometallurgical partitioning and extracting technology of irradiated fuel is investigated. Also in case of perfoming the test at O-arai engineering center, the contents of the test, equipments, structure and arragement of cells that equipments are installed, are studied. The purpose of the test is to confirm the realization of the process and behavior of FP and TRU elements, and off-gass that cannot be made dear by cold test. In this study it is assumed that 100g monju fuel (94,000MWd/t B.U, cooled for 550 days) per batch is treated. Four processes are picked up except for pin sectioning and powdering, as important subjects. They are as follows. (1)reduction of oxide fuel (2)electrorefining (3)cathode processing (4)extraction of TRU elements. And the outline of the test, blocked flow chart and the outline of equipment are clarified. And the outline of chart is drawn. Moreover, the specification of analitical equipments which are necessary to analyze the product is shown. From spent chloride, TRU and a part of FP elements are extracted and they are recycled for electrorefining and so on. The salt-waste including residual FP elements is kept in a receptacle after being absorbed into Zeorite and soldified. As the disposition of these tests, modified test cell in the existing FMF, modified concrete cell in AGF, new cell at B2F in the existing FMF and new cell at second auxiliary room in FMF extension are studied. As result of considering the disposition for equipment, the difficulty of reconstucting new cell including of equipments, method of mentenance, and equipments of ventilazion (Ar circumstance) including of management of off gas, and the plan of disposition, it is concluded that constructing iron cell into the second auxiliary room of FMF extension is best, because it is easy to construct safely, and the occurance of radioactive waste and the influence to other tests is little, and it is possible to examine more efficiently.

None

Koizumi, Masumichi

Nihon Genshiryoku Gakkai-Shi Semmon Iinkai Hokoku, 33(11), 87 Pages, 1991/11

None

Study of new type fuels for FBR

*; *; Koizumi, Masumichi

PNC TN9410 89-037, 32 Pages, 1989/03

PNC-TN9410-89-037.pdf:0.74MB

New type fuels (metal, nitride and carbide) are expected to be superior to MOX fuel in future. Here, informations about the new fuels are investigated and evaluated for comparing with these of MOX (Mix Oxide) fuel. It is believed that this evaluation can contribute to the decision of policy how they are chosen. In Japan and Europe, the MOX fuel has been developed as the main FBE fuel. However, the research and development of MC (Mix Carbide) and MN (Mix Nitride) fuel in Europe, which includes the manufacturing process, properties of physical-chemistry, and irradiation behavior, has been continued on a labo-scale since before. In France, U.K., Switzerland, and West Germany, they have a plan of development which puts stress on MN fuel more than MC fuel. In the united States, DOE had developed MOX fuel as the favorite like Japan, but they decided to advance the development of Metal fuel and small-sized reactor in 1985. If they can't have anticipated results, it is thought to secure the option of being able to access to data of MOX fueled large scale FBR in Japan.

None

Koizumi, Masumichi; *; Kaneko, Hiromitsu; Kishimoto, Yoichiro; Kanamori, Masashi; Ojima, Hisao; ; *

PNC TN842 83-05, 49 Pages, 1983/10

PNC-TN842-83-05.pdf:1.72MB

None

Development of a Process for Co-Conversion of Pu-U Nitrate Mixed Solutions to Mixed Oxide Powder Using Microwave Heating Method

*; Naruki, Kaoru*; Koizumi, Masumichi*; ; Oshima, Hirofumi; *

Journal of Nuclear Science and Technology, 20(7), p.529 - 536, 1983/00

https://doi.org/10.1080/18811248.1983.9733431

Certificate and Records of HALDEN IFA-529 Test Fuel Rods in PNC Irradiation Program

Kashima, Sadamitsu; *; *; Koizumi, Masumichi; Tateishi, Yoshinori*; Honda, Yutaka*

PNC TN841 80-21, 51 Pages, 1980/03

PNC-TN841-80-21.pdf:1.56MB

The Halden IFA-529 irradiation test is planned to examine the fuel dehavior of BWR Type fuel under reactor operation. Twelve fuel rods for this irradiation testwere fabricated in Research & Development Section of Plutonium Fuel Div. in PNC. These fuel rods have instrumentations for the measurement of fuel column elongation, claddingelongation, plenum pressure and fuel center temperature. The fuel pellets were made from type of raw materials. One was obtained by precipitation-calcination prosess, and another was direct denitration process. The fuel composition is 8.3% PuO2-U02(natural), and the pellet nominal dimension is 10.56mm dia. and 10mm height.

Fabrication tests of low density nuclear fuel pellets

Honda, Yutaka*; Kashima, Sadamitsu; ; Koizumi, Masumichi*

American Ceramic Society Bulletin, 60(12), p.1296 - 1299, 1980/00

Effect of Temperature and Deformation Rate on Fracture Strength of Sintered Uranium Dioxide

Tachibana, Toshimichi; Furuya, Hirotaka*; Koizumi, Masumichi*

Journal of Nuclear Science and Technology, 16(4), p.266 - 277, 1979/00

https://doi.org/10.1080/18811248.1979.9730900

None

Koizumi, Masumichi; Kashima, Sadamitsu; *; *; *; *; *; *

PNC TN841 78-16, 44 Pages, 1978/02

PNC-TN841-78-16.pdf:2.75MB

no abstracts in English

None

Koizumi, Masumichi; Honda, Yutaka*; Yamaguchi, Toshihiro; *; Kaneko, Hiromitsu

PNC TN841 77-62, 26 Pages, 1977/11

PNC-TN841-77-62.pdf:1.81MB

no abstracts in English