Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Morita, Kenji; Morimoto, Makoto; Hisada, Masaki; Fukui, Yasutaka
JAEA-Technology 2015-038, 30 Pages, 2016/02
JAEA-Technology-2015-038.pdf:14.65MB
The Old Waste Treatment Facility for JOYO (Old JWTF) has been operated to treat radioactive liquid waste from the experimental fast reactor JOYO and post irradiation examination facilities. Operation of Old JWTF stopped in 1995, and dismantling & decontamination method has discussed. As a response to discussion results of remote and dismantling method in high dose environment on 2013, its concept examination was discussed on 2014. Results are follows. As a cutting tool for Old JWTF equipment, wire saw is selected from cutting ability (speed and thickness of objects). Discussed the component technology of wire saw remote operation system (handling, monitoring, collection method of secondary waste, else).
Morita, Kenji; Morimoto, Makoto; Hisada, Masaki; Fukui, Yasutaka
JAEA-Technology 2015-037, 28 Pages, 2016/01
JAEA-Technology-2015-037.pdf:8.44MB
Deuterium Critical Assembly (DCA) achieved first critically in 1969 and used for research and development program of Advanced Thermal Reactor. To achieved the aim of facility, DCA decommissioning work started in 2002. Decommissioning schedule consists of 4 stages. The third stage, which is the main work (To dismantle and remove reactor vessel and main equipment), was started in 2008 and will be finished at 2023. This report describes DCA decommissioning work and data (Ability of cutting tools and Man-hours) in 2013.
Hirokawa, Katsunori; Hisada, Masaki; Fukui, Yasutaka; Inoue, Setsunari
Dekomisshoningu Giho, (44), p.33 - 42, 2011/09
In Japan Atomic Energy Agency, facilities where the mission was finished and superannuation facilities are decommissioned systematically for rationalization and efficiency improvement of business. It is necessary to execute safe and economically by making good use of the technology according to the kind of facilities and the feature of the dismantlement object. In this report, it reports on the radiation measurement, decontamination and dismantling technology that develops in the Waste Treatment Technology Section O-ARAI Research and Development Center JAEA.
; Koyama, Shinichi;
JNC TN9430 2000-002, 58 Pages, 2000/06
JNC-TN9430-2000-002.pdf:4.99MB
Fabrication tests and irradiation examinations of americium added MOX fuel is planned as a part of JNC reseach project for advanced nuclear fuel recycle system. It is neccesary that evaluation of the influence of adding americium for performances of MOx fuel. Test MOX fuel (B8-HAM) containning about 1wt% americium that deriveds from decaying plutonium 241 were irradiated up to 26.2 GWd/t in the fast experimental reacter JOYO. Concentration profile of americium in the test fuels was measured by SXMA (shielded X-ray microprobe analyser) and the redistribution phenomena of americium was evaluated. As the results, at the center of the fuel colmn, it is revealed that americium concentration in the center area of pellet was increased to about 20% relative to the pellet average, and this increase rate is smaller than one of plutonium. And redistribution of americium was only obsevated clearly at the center of the fuel clomn, so that it is suggested that redistribution phenomena of americium depends on linear heat rate, like one of plutonium.
; ; ; ; Hirosawa, Takashi; ;
PNC TN9440 97-006, 335 Pages, 1997/06
A seminar of the Alpha-Gamma section (AGS) at O-arai Engineering Center of PNC was held from October 21, 1994 to March 19, 1997 per month. The contents of discussion of the seminar are as follows. (1)Status report of refurbishlnent of minor actinides (MA) fuel fabrication line and of a maintenance logbook of manipulators and up-to-date PIE examination reports of sold fission products at high burnup MOX fuels. (2)Investigation report of methods of melting temperature on irradiated MOX fuel, criteria of leakage rate for cells and glove boxes, measurement methods of high temperature and evaluation of radiation shielding of the Alpha-Gamma Facility. (3)Abridged translation of radiation damage, FP behavior in irradiated fuel, safety aspects of fuel behavior during faults and accidents and fuel modeling at high burnup. (4)Lecture of evaluation on measurement error. (5)Translation for "Statistical Analysis of Measurement Errors" by J.L.Jaech. This report is compiled the above proceedings of the seminar.
