Development of advanced neutron radiography for inspection on irradiated fuels and materials; Feasibility study of neutron radiography in terms of PIE execution

Yasuda, Ryo; Nishi, Masahiro; Nakata, Masahito; Matsubayashi, Masahito

JAERI-Tech 2000-030, p.20 - 0, 2000/03

JAERI-Tech-2000-030.pdf:2.2MB

no abstracts in English

Outlines of VEGA experimental program on radionuclides release from irradiated fuel

Hidaka, Akihide; Nakamura, Takehiko; Kudo, Tamotsu

Genshiryoku eye, 46(3), p.79 - 83, 2000/03

http://ci.nii.ac.jp/naid/40005192047

no abstracts in English

Post irradiation examination data of high burnup PWR fuel rod; Rod No.:B15 (assembly No.:NO1G13)

*; Ishijima, Kiyomi; Yamahara, Takeshi

JAERI-Data/Code 98-002, 24 Pages, 1998/02

JAERI-Data-Code-98-002.pdf:1.02MB

no abstracts in English

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.

Behavior of stainless steel cladding fuel under a fast power transient condition; NSRR SC-1 test results

Katanishi, Shoji; Ishijima, Kiyomi; ; Kikuchi, Teruo;

JAERI-Research 94-039, 54 Pages, 1994/11

JAERI-Research-94-039.pdf:5.2MB

no abstracts in English

Determination of Pu Accumulated in Irradiated Fuels by Non-Destructive Isotopic Correlation Technique

; ; Matsuura, Shojiro

JAERI-M 8599, 13 Pages, 1979/11

JAERI-M-8599.pdf:0.55MB

no abstracts in English

Adsorption behavior of nuclear rare metals on hybrid microcapsules in spent fuel solution

Onishi, Takashi; Koyama, Shinichi; Mimura, Hitoshi*

no journal, , 

no abstracts in English