Development of a proton accelerator for OIST BNCT

Kondo, Yasuhiro; Hasegawa, Kazuo; Higashi, Yasuo*; Kumada, Hiroaki*; Kurokawa, Shinichi*; Matsumoto, Hiroshi*; Naito, Fujio*; Yoshioka, Masakazu*

Proceedings of 12th Annual Meeting of Particle Accelerator Society of Japan (Internet), p.948 - 950, 2015/09

An accelerator based boron neutron capture therapy (BNCT) facility is being planned at Okinawa institute of science and technology (OIST). The proton accelerator consists of a radio frequency quadrupole (RFQ) linac and a drift tube linac (DTL). The reqired beam power is 60 kW. The present beam energy and current are 10 MeV and 30 mA, respectively. The pulse length is 3.3 ms and the repetition rate is 60 Hz, therefore, the duty factor is 20%. In this paper, present designof this compact, midium current, high duty proton linac is presented.

Vane machining by the ball-end-mill for the new RFQ in the J-PARC linac

Morishita, Takatoshi; Kondo, Yasuhiro; Hasegawa, Kazuo; Kawamata, Hiroshi*; Naito, Fujio*; Yoshioka, Masakazu*; Matsumoto, Hiroshi*; Hori, Yoichiro*; Saito, Yoshio*; Baba, Hiroshi*

Proceedings of 25th International Linear Accelerator Conference (LINAC 2010) (CD-ROM), p.518 - 520, 2010/09

http://accelconf.web.cern.ch/AccelConf/LINAC2010/papers/tup049.pdf

The fabrication of a new RFQ has been started in the J-PARC linac. The RFQ cavity is divided by three unit tanks in the longitudinal direction. The unit tank consists of two major vanes and two minor vanes, those will be brazed together. To reduce the costs and periods to develop the special formed bite for the modulation machining, a numerical controlled machining using a conventional ball-end-mill was adopted for the vane modulation cutting instead of the wheel shape cutter. The dimension accuracy was confirmed by cutting test pieces. Moreover, the obtained surface seems smooth enough for the operation. Results of the ball-end-mill machining for the vanes are described.

Fabrication of the new RFQ for the J-PARC linac

Morishita, Takatoshi; Kondo, Yasuhiro; Hasegawa, Kazuo; Naito, Fujio*; Yoshioka, Masakazu*; Matsumoto, Hiroshi*; Hori, Yoichiro*; Kawamata, Hiroshi*; Saito, Yoshio*; Baba, Hiroshi*

Proceedings of 1st International Particle Accelerator Conference (IPAC '10) (Internet), p.783 - 785, 2010/05

http://accelconf.web.cern.ch/AccelConf/IPAC10/papers/mopd044.pdf

The J-PARC RFQ (length 3.1 m, 4-vane type, 324 MHz) accelerates a negative hydrogen beam from 0.05 MeV to 3 MeV toward the following DTL. The stability of the operating RFQ decreased for a few months at the end of 2008, then, we started a preparation of a new RFQ as a backup machine in the case of RFQ problem. The beam dynamics design of the new RFQ is the same as the current cavity for a quick resumption of operation, however, the engineering and RF designs are changed to improve stability. The processes of the vane machining and the surface treatments have been carefully considered to reduce the discharge problem. The vacuum brazing technique has been chosen for vane jointing. The design of the new RFQ and the fabrication progress is descried in this proceeding.

Status of the J-PARC RFQ

Hasegawa, Kazuo; Morishita, Takatoshi; Kondo, Yasuhiro; Oguri, Hidetomo; Kobayashi, Tetsuya; Naito, Fujio*; Yoshioka, Masakazu*; Matsumoto, Hiroshi*; Kawamata, Hiroshi*; Hori, Yoichiro*; et al.

Proceedings of 6th Annual Meeting of Particle Accelerator Society of Japan (CD-ROM), p.693 - 695, 2010/03

http://www.pasj.jp/web_publish/pasj6/papers/tpopa03.pdf

The J-PARC RFQ (length 3.1m, 4-vane type, 324 MHz) accelerates a beam from the ion source to the DTL. The beam test of the linac was started in November 2006 and 181 MeV beam was successfully accelerated in January 2007. Since then, the linac has been delivered beams for commissioning of the linac itself, downstream accelerators and facilities. Trip rates of the RFQ, however, suddenly increased in Autumn 2008, and we are suffering from this issue for user run operation. We tried to recover by tender conditioning, modification of RF control, improvement of vacuum and so on. We manage to have beam operation. In this report, we describe the status of the RFQ.

None

Ouchi, Jin; Nogami, Yoshitaka; Tobita, Noriyuki;

JNC TN8420 99-002, 52 Pages, 1999/01

JNC-TN8420-99-002.pdf:4.87MB

None

Test results of Run, 5 in steam generator safety test facility (SWAT-3); Report No.10, Large leak sodium-water reaction test

Hiroi, Hiroshi*; *; *; *; *; *

PNC TN941 79-04, 274 Pages, 1979/10

PNC-TN941-79-04.pdf:8.87MB

Large leak sodium-water reaction tests have been carried out using SWAT-3 facility in PNC O-arai Engineering Center to obtain the data on the safe design of the prototype, LMFBR Monju is steam generator against large leak accident. This report gives the results of SWAT-3 run-5 test. The heat transfer tube bundle of the evaporator used in run-5 test was designed and fabricated by MITSUBISHI HEAVY INDUSTRIES, LTD. The water injection rate into the evaporator was 15 kg/sec, which corresponds to test scale of 5 tubes failure in actural size system according to iso-velocity modeling. Measurements were made of pressure, strain, temperature, sodium level, void, thrust load, acceleration, displacement, flow rate, and so on. Initial spike pressure was 24.6 kg/cm a nearest to injection point, and the maximun quasi-steady pressure in evaporator was 7.6 kg/cma. The rupture disc of evaporator was bursted at 0.23 sec after water injected, and the pressure relief system was well functioned. No secondary tube failure was observed.

Test results of Run-6 in steam generator safety test facility(SWAT-3); Report No.11; Large leak sodium-water reaction test

*; *; Hiroi, Hiroshi*; *; *; *

PNC TN941 78-154, 210 Pages, 1978/10

PNC-TN941-78-154.pdf:7.19MB

Large Leak sodium-water reaction tests have been carried out using SWAT-3 facility in PNC O-arai Engineering Center to obtain the data on the safe design of the prototype LMFBR Monju's steam generator against large leak accident. This report describes the resulting data of Run-6 test. The heat transfer tube bundle of the evaporator used was fabricated by HITACHI/BABCOCK HITACHI. The water injection rate into the evaporator was 9.4 kg/sec, which corresponds to test scale of 5.7 tubes failure in actual size system according to iso-velocity modeling. Pressure, strain, temperature, sodium level, void, thrust load, acceleration, displacement, flow rate, etc were measured during water injection test. Initial spike pressure was 12 kg/cma nearest to injection point, and the maximun quasi-steady pressure in evaporator was 5.1 kg/cma. The rupture disc of evaporator was bursted at 0.58 sec after water injected, and the pressure relief system was well functioned. No secondary tube failure was observed.

Progress report for large leak sodium-water reaction study No.1; Large leak sodium-water reaction test report (No.7)

*; *; *; *; *; *; *

PNC TN941 78-32, 84 Pages, 1978/01

PNC-TN941-78-32.pdf:2.35MB

The study to establish the safe design of LMFBR MONJU's steam generator system against the large leak sodium-water reaction is conducing by Power Reactor & Nuclear Fuel Development Corporation. This report includes seven topics which have been presented to the meetings of Atomic Energy Society of Japan, etc. during 1977. Summaries of these topics are as follow; (1)A computer program SWAC-11 was developed to predict the water leak rate from the ruptured heat transfer tube in the steam generator. The basic equations used and method of numerical calculation were explained. The sensitivity survey calculations for various parameters used in the code and the demonstration calculation of the case of MONJU's evaporator were reported. (2)A computer program SWAC-13 was developed to ptedict the pressure and flow behavior in the secondary cooling system, i.e. the quasistatic pressure build up, sodium/hydrogen gas flow in the SG vessels and secondary sodium circuit, and flow characteristics of pressure relief line and the hydrogen gas reliese into the atmosphere. The modeling, basic equations and the method of numerical calculation of the program were reported, and the applicability to SWAT-3 tests was demonstrated. (3)The reaction vessel drain line of SWAT-3 facility was chocked with sodium-water reaction products after water injection test Run-3. In order to understand the cause of chocking, the investigations of the reaction product and temperature distributions in the drain line, and the chemical analysis and the freezing temperature measurement of the reaction products were performed. Those results were summarized quantitatively in this chapter. (4)In order to make clear the flow characteristic of the pressure relief line, we tried to rearrange the data of two test runs of SWAT-1 rig which were obtained by the various kind of the sensors attached on the relief line. It became clear from those investigations that the sodium/hydrogen-gas two phase flow in the ...

Construction of a BNCT facility using an 8MeV high power proton linac in Ibaraki

Kobayashi, Hitoshi*; Kurihara, Toshikazu*; Matsumoto, Hiroshi*; Yoshioka, Masakazu*; Matsumoto, Noriyuki*; Kumada, Hiroaki*; Matsumura, Akira*; Sakurai, Hideyuki*; Hiraga, Fujio*; Kiyanagi, Yoshiaki*; et al.

no journal, , 

no abstracts in English