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JAEA Reports

Investigation of JNC,s competitive position reprocessing plant design of light water reactor fuels and MOX fuel fabrication plant design in world markets

*; Yumoto, Ryozo; *; *; *

JNC TJ9440 99-019, 106 Pages, 1999/03

Problems were picked up by investigating how to strengthen JNC's competitive position of the fuel cycle technologies (reprocessing and MOX fabrication) in world markets. Market needs in mainly Asian countries were also investigated about plutonium utilization in light water reactors (LWRs). Legal regulations were surveyed on import, export and transport of nuclear fuels. Foreign enterprises involved in fuel reprocessing and MOX fabrication businesses were surveyed on their activities and company histories. Fundamental conditions required to a company which is going to commence and run a fuel reprocessing and MOX fuel fabrication were discussed. Technical problems were picked up concerning strengthening JNC's competitive position of reprocessing technologies by making an image of 400tons / year model plant. Cost reduction and improvement of safety are two basic indexes for pick up technical problems other indexes are simplification of process, cutting down of radioactive waste generation and so on. Accumulated amount and generation rate of spent fuels discharged from LWRs in some Asian countries were analyzed from the date of electric power consumption and share of nuclear power plant generation. Latent reprocessing demand which is caused by the pressure of big accumulations of spent fuel storage were also estimated. Then timing of commencing fuel reprocessing and MOX fuel utilizing were forecasted for Korea, Taiwan and China based on the above results.

JAEA Reports

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.

Journal Articles

Experience on Pu-U mixed oxide fuel development in Japan

Uematsu, Kunihiko; Honda, Yutaka*; Yumoto, Ryozo

Nihon Genshiryoku Gakkai-Shi, 24(6), p.420 - 428, 1982/06

https://doi.org/10.3327/jaesj.24.420

Times Cited Count：0 Percentile：0.02(Nuclear Science & Technology)

JAEA Reports

Critical Experiment for Power Flattening in Plutonium Fuel Lattice, 1; Measurement of Power Distribution

Murakami, Kiyonobu; ; ; Ono, Akio*; ; *; *; *

JAERI-M 9876, 83 Pages, 1982/01

JAERI-M-9876.pdf:3.09MB

no abstracts in English

JAEA Reports

None

*; Kawata, Tomio*; Yumoto, Ryozo; *; *; *

PNC TN243 81-02, 15 Pages, 1981/10

PNC-TN243-81-02.pdf:0.36MB

no abstracts in English

JAEA Reports

None

Yumoto, Ryozo; *; *;

PNC TN841 81-34, 189 Pages, 1981/03

PNC-TN841-81-34.pdf:3.93MB

no abstracts in English

JAEA Reports

None

Yumoto, Ryozo; Kaya, Akira; *; Yokozawa, Naoki; *; *

PNC TN841 81-24, 217 Pages, 1981/03

PNC-TN841-81-24.pdf:22.1MB

no abstracts in English

JAEA Reports

None

Yumoto, Ryozo; *; *

PNC TN841 81-15, 222 Pages, 1981/03

PNC-TN841-81-15.pdf:27.95MB

no abstracts in English

JAEA Reports

None

Yumoto, Ryozo; *; Sasajima, Hideyoshi*

PNC TN841 79-40, 100 Pages, 1979/07

PNC-TN841-79-40.pdf:5.26MB

no abstracts in English

JAEA Reports

None

Koizumi, Masumichi; Honda, Yutaka*; Yumoto, Ryozo; *; *; *; Hirasawa, Masayoshi; Yagi, Takao

PNC TN841 79-38, 250 Pages, 1979/06

PNC-TN841-79-38.pdf:16.67MB

no abstracts in English

JAEA Reports

None

Yumoto, Ryozo; *; Hirasawa, Masayoshi; *

PNC TN841 78-59, 363 Pages, 1978/11

PNC-TN841-78-59.pdf:7.62MB

no abstracts in English

JAEA Reports

PURSE:A Plutonium Radiation Source Code

Yumoto, Ryozo; Sasajima, Hideyoshi*; Fukuda, Shoji*

PNC TN852 78-13, 53 Pages, 1978/10

PNC-TN852-78-13.pdf:1.66MB

PURSE has been developed to calculate alpha, beta, ray and neutron intensity from fresh plutonium mixed-oxide fuels which contain daughter nuclides of plutonium and uranium. PURSE also has an ability to calculate ray spectrum from mixed-oxide fuels. Four main decay chains of uranium, actinium, thorium and neptunium are considered. In addition, decay chains of transplutonium elements and some kinds of Fission Product elements which will be slightly remained in plutonium after reprocessing are also considered. Number of curies and emission energy of alpha, beta and ray from nuclides in these decay chains are calculated as a function of time. The number of energy groups of ray can be taken up to 18, the total and average energy of each groups can be calculated, and the ray spectrum is plotted by the use of a plotter. As for neutron generation, spontaneus fission and (, n) reaction with oxygen are considered. PURSE is written in FORTRAN IV for the CDC 6600 and a running time is about one minute. A plotter is the CalComp 915-1136.