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Magome, Hirokatsu; Iimura, Koichi; Matsui, Yoshinori
JAEA-Testing 2020-008, 52 Pages, 2021/02
JAEA-Testing-2020-008.pdf:5.46MB
As to the removal of the hydraulic rabbit No.1 irradiation facility related to the decommissioning of JMTR, points to be noted for considering a removal plan and maintenance methods after the removal were studied based on the past experiences of removing the hydraulic rabbit No.2 irradiation facility. As results, it became clear that it was necessary to (1) add a shutoff valve and a closing flange to piping for preventing cooling water leakage, (2) prepare a drawing jig for inner tube, and (3) shorten the remaining piping to withstand earthquakes. In addition, regarding the management of equipment to be maintained after removal, the necessary management items for the removal methods of the three patterns of ground equipments were listed.
Magome, Hirokatsu; Iimura, Koichi; Matsui, Yoshinori
JAEA-Technology 2020-022, 32 Pages, 2021/02
JAEA-Technology-2020-022.pdf:4.04MB
Among the canal underwater equipment of HR-1, seismic evaluations of the canal side wall parts and the canal bottom surface parts were carried out for the insertion device, take-out device and decay tank. As a result, it was confirmed that the equipments have sufficient seismic resistances because the maximum stress of the canal side wall joint, the bolt portion of the canal bottom joint, and the fillet weld are within the allowable stress.
Kobayashi, Yasuhiko; Funayama, Tomoo; Wada, Seiichi; Sakashita, Tetsuya
Uchu Seibutsu Kagaku, 18(3), p.186 - 187, 2004/11
no abstracts in English
Sugimoto, Masayoshi; Imai, Tsuyoshi; Okumura, Yoshikazu; Nakayama, Koichi*; Suzuki, Shohei*; Saigusa, Mikio*
Journal of Nuclear Materials, 307-311(Part2), p.1691 - 1695, 2002/12
Times Cited Count：2 Percentile：17.03(Materials Science, Multidisciplinary)International Fusion Materials Irradiation Facility (IFMIF) is an accelerator-based intense neutron source for fusion reactor materials development. Each one of the two accelerator modules needs to have a capability to provide the 40MeV/125mA deuteron beam continuously. Although the technology to produce the 7MeV/100mA proton beam is already verified using 350 MHz linac in the past, an engineering study using a prototype is necessary to verify the performance of IFMIF 175 MHz deuteron linac, and Engineering Validation Phase (EVP) is planned for this purpose. Some critical design parameters, like final and transition energies of linacs or RF source characteristics, are needed to be optimised for the prototype. As it is also important to verify the essential component technology, e.g. ion source, RFQ beam matching, rf system components, etc., the present status and expected results of such undergoing verification tests are described. An integrated concept of prototype accelerator is shown as a Japanese proposal for EVP to provide for the international discussion.
Ito, Hitoshi
Shokuhin Kigai Biseibutsu Handobukku, p.307 - 315, 1998/09
no abstracts in English
Soroi, Masatoshi; Miyakawa, Shunichi
PNC TN9410 98-050, 57 Pages, 1998/05
This report describes the present situation and problems with the development of the flow control irradiation facility (FLORA). The purpose of FLORA is to run the cladding breach (RTCB) irradiation test under loss of flow conditions in the experimental fast reactor "JOYO". FLORA is a facility like FPTF (Fuel Performance Test Facility) plus BFTF (Breached Fuel Test Facility) in EBR-II, USA. The technical feature of FLORA is its annular linear induction pump (A-LIP), which was developed in response to a need identified through the experiences in the mechanical flow control of FPTF. We have already designed the basic system facility of FLORA for the JOYO MK-II core. However, to put FLORA to practical use in the future, we have to confirm the stability of the JOYO MK-III core condition, solve problems and improve the design. The main results and problems of the development of FLORA are as follows; (1)The results of the development: (a)The neutron detector in FLORA can detect the delayed neutron which is emitted from failed fuel. (b)Out-of-pile A-LIP tests in sodium conditions has been completed. (The length of the tested A-LIP is half the actual size.) Out-of-pile test results showed that the A-LIP achieved a 300
/min flow rate and 265kPa pressure in 550
C sodium. This pump performance satisfied the FLORA requirements. (c)By controlling the sodium flow rate from 40 to 100% using the A-LIP, we can control the fuel cladding temperature satisfactorily. (2)The problems: (a)In the development of the process detector, it is necessary to miniaturize the neutron detector and test the effect of neutron irradiation and high temperatures on the permanent magnet in the flow meter. (b)The problem which is left about A-LIP is its influence on neutron irradiation. For this purpose, we have to irradiate a small size A-LIP and test its characteristics and electric isolation. (c)To get more accurate results concerning the efficiency of the A-LIP, we have to ...
Bottcher, J. T.
PNC TN9440 97-011, 215 Pages, 1997/06
J.H.Bottcher started his intemational Fellow position at PNC on March 25, 1996.During his 15 months in PNC he worked in the Irradiation Section of the Experimental Reactor Division. There he worked on conceptual design reviews and related the US irradiations methodology to the members. His work extended to other Divisions at OEC and Tokai Works, mainly related to fuel development and irradiation performance. In these efforts he published two papers, wrote a desip review document, and presented six lectures on irradiated fuels and materials. In addition he participated in coordinating a new four year PNC/DOE collaborative program on irradiated steels characterization.
ray sourcesHihakai Kensa, 46(11), P. 783, 1997/00
no abstracts in English
Iimura, Katsumichi; ; ; Abe, Shinichi; Takahashi, Kiyoshi; ; Iwai, Takashi
Dekomisshoningu Giho, (10), p.42 - 48, 1994/06
no abstracts in English
Kobayashi, Katsumi*; Usami, Noriko*; Yokoya, Akinari
Journal of Radiation Research, 34(1), 110 Pages, 1993/03
no abstracts in English
Arigane, Kenji; *; ; Seguchi, Tadao; Takahashi, Hidetake
Proc. of 4th Asian Symp. on Research Reactors, 10 Pages, 1993/00
no abstracts in English
Kasai, Noboru; Seguchi, Tadao
JAERI-M 92-011, 35 Pages, 1992/03
no abstracts in English
*; Hojo, Kiichi; Furuno, Shigemi; ; *
Shinku, 35(4), p.431 - 437, 1992/00
no abstracts in English
Kasai, Noboru; Nishii, Masanobu; Seguchi, Tadao
JAERI-M 91-064, 35 Pages, 1991/04
no abstracts in English
