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Journal Articles

Development of radiation detectors for in-pile measurement

Takeuchi, Tomoaki; Otsuka, Noriaki; Shibata, Hiroshi; Nagata, Hiroshi; Endo, Yasuichi; Matsui, Yoshinori; Tsuchiya, Kunihiko

KAERI/GP-418/2015, p.110 - 112, 2015/00

$$gamma$$ irradiation experiments with a $$^{60}$$Co source were carried out for developing Self-Powered Gamma Detectors (SPGDs) with lead (Pb) emitter and Self-Powered Neutron Detectors (SPNDs) with Pt-40%Rh emitter prior to in-core irradiation experiments. The results showed the output currents of the SPGDs were proportional to the $$gamma$$ dose rate in the range from about 200-6000 Gy/h with about 10% accuracy. In the case of SPNDs, the output currents flowed in inverse direction and were an order of magnitude lower compared with that of the SPGDs. These different behaviors of the output currents are considered to be caused by the difference in the emitter sizes and the current component originated at the MI cables.

Journal Articles

Development of the irradiation facility for simulating condition of light-water reactor

Kitagishi, Shigeru; Endo, Yasuichi; Okada, Yuji; Hanawa, Hiroshi; Matsui, Yoshinori

UTNL-R-0486, p.7_1 - 7_10, 2014/03

no abstracts in English

Journal Articles

Neutron irradiation tests for beryllium material selection of neutron reflector in JMTR

Tsuchiya, Kunihiko; Ito, Masayasu; Kitagishi, Shigeru; Endo, Yasuichi; Saito, Takashi; Hanawa, Yoshio; Dorn, C. K.*

JAEA-Conf 2012-002, p.111 - 114, 2012/12

no abstracts in English

Journal Articles

Performance evaluation of friction welded joint of zircaloy-2 to type 316L stainless steel

Kitagishi, Shigeru; Saito, Takashi; Kikuchi, Taiji; Endo, Yasuichi; Tsuchiya, Kunihiko

Nippon Kikai Gakkai Rombunshu, A, 78(788), p.564 - 570, 2012/04

The development of the friction welded joint between Zircaloy-2 (Zry-2) and Type 316L stainless steel (SUS316L) has been carried out for the fabrication of fuel irradiation capsules in Japan Materials Testing Reactor (JMTR). The welding condition was determined from the fabrication test results of total loss and tensile strength. The joint interface was characterized by metallographic observation, elemental analysis and micro-hardness test. It was found that heat-affected zones at the joint interface were different between the center and outside positions. The tensile strength of the joint was equal to that of base Zry-2 metals at 300$$^{circ}$$C. And, the joint performance was good from the results of helium leak test and hydraulic pressure burst test. From the results of these tests, it was obvious that the Zry-2/SUS316L friction welded joints were promised to use for the structural material of irradiation capsules for fuel irradiation tests.

JAEA Reports

Fabrication study of new irradiation facility for $$^{99}$$Mo production in JMTR

Takita, Kenji; Iimura, Koichi; Tomita, Kenji; Endo, Yasuichi; Kanno, Masaru

JAEA-Technology 2012-006, 41 Pages, 2012/03

JAEA-Technology-2012-006.pdf:6.8MB

At JAEA Oarai Research and Developnment Establishment (JAEA Oarai), JAEA Oarai was proceeding a plan to repair JMTR, which is to re-operate in fiscal 2012. Additionally, as an effective utilizati of JMTR, JAEA Oarai is planning to manufacture $$^{99}$$Mo, which is a parent nuclide of $$^{99}$$Tc. $$^{99m}$$Tc is most commonly used as a radiopharmaceution in the field of nuclear medicine. Currently $$^{99}$$Mo supply is dependent only on foreign imports, so JAEA is aiming for working on partially manufacturing $$^{99}$$Mo domestically with industrial circles in Japan. In this article, this report described the choice and fabric of irradiathion facility named Hydraulic Rabbit Facility for manufacturing $$^{99}$$Mo, the technical study of fabrication technique.

Journal Articles

Status of the design and investigation for hydraulic rabbit irradiation facility

Takita, Kenji; Iimura, Koichi; Tomita, Kenji; Endo, Yasuichi; Kanno, Masaru

UTNL-R-0480, p.7_4_1 - 7_4_6, 2012/03

no abstracts in English

JAEA Reports

Review on technical evaluation of aging of JMTR reactor facility

Ide, Hiroshi; Tobita, Kenji; Endo, Yasuichi; Hori, Naohiko

JAEA-Review 2010-043, 80 Pages, 2010/10

JAEA-Review-2010-043.pdf:34.97MB

"Regulations Concerning the Installment, Operation, etc. of Research Reactors" was revised in February 2004. Based on the regulations, the reactor owner must perform the technical evaluation on aging if reactor operation is over 30 years. Moreover, based on the evaluation, the reactor owner must make the 10 years maintenance program concerning the action to maintain the reactor facility. Result of the technical evaluation on aging and the maintenance plan of JMTR reactor facility were reported to the MEXT in March 2005. In response to the report, the advisor meeting was held by the MEXT to evaluate the result of technical evaluation on aging and the maintenance plan. Corresponding to the meeting, we reviewed the technical evaluation result on aging and the maintenance program of JMTR reactor facility. This report summarized the review on the technical evaluation of aging of JMTR reactor facility and so on corresponding to the advisor meeting.

Journal Articles

Development of oxygen sensors using zirconia solid electrolyte for fuel rods

*; Endo, Yasuichi; Yamaura, Takayuki; Matsui, Yoshinori; Niimi, Motoji; Hoshiya, Taiji; Kobiyama, M.*; Motohashi, Yoshinobu*

JAERI-Conf 99-006, p.343 - 348, 1999/08

no abstracts in English

Journal Articles

Electrical properties of neutron-irradiated oxygen potential sensors using stabilized zirconia solid electrolyte

*; Endo, Yasuichi; Yamaura, Takayuki; Hoshiya, Taiji; Niimi, Motoji; Saito, Junichi; ; Ooka, Norikazu; Kobiyama, M.*

Journal of Nuclear Materials, 258-263, p.2041 - 2045, 1998/00

 Times Cited Count:6 Percentile:49.15(Materials Science, Multidisciplinary)

no abstracts in English

JAEA Reports

Neutron irradiation characteristic tests of oxygen sensors using zirconia solid electrolyte

*; Endo, Yasuichi; Yamaura, Takayuki; Niimi, Motoji; Hoshiya, Taiji; Saito, Junichi; ; Ooka, Norikazu; *

JAERI-Research 97-028, 46 Pages, 1997/03

JAERI-Research-97-028.pdf:2.49MB

no abstracts in English

JAEA Reports

Fission gas release during power change; Re-irradiation test of LWR fuel rod at JMTR

Nakamura, Jinichi; Endo, Yasuichi; ; ; Furuta, Teruo

JAERI-Research 95-083, 38 Pages, 1995/11

JAERI-Research-95-083.pdf:1.42MB

no abstracts in English

JAEA Reports

Development of thermocouple re-instrumentation technique for irradiated fuel rod; Techniques for making center hole into UO$$_{2}$$ pellets and thermocouple re-instrumentation to fuel rod

; Saito, Junichi; ; Endo, Yasuichi; ; Nakagawa, Tetsuya; ; Kawamata, Kazuo; ; Kawamura, Hiroshi; et al.

JAERI-Tech 95-037, 87 Pages, 1995/07

JAERI-Tech-95-037.pdf:5.14MB

no abstracts in English

JAEA Reports

Plate-out distribution of iodine in a high temperature gas cooling in-pile loop facility

Matsumoto, Mikio; Endo, Yasuichi; ; Itabashi, Yukio; ; Yokouchi, Iichiro; Ando, Hiroei

JAERI-M 92-212, 62 Pages, 1993/01

JAERI-M-92-212.pdf:2.09MB

no abstracts in English

JAEA Reports

Evaluation of lift-off fraction in accident condition of HTGR

Sawa, Kazuhiro; ; *; Endo, Yasuichi; Shiozawa, Shusaku;

JAERI-M 91-207, 34 Pages, 1991/12

JAERI-M-91-207.pdf:0.93MB

no abstracts in English

JAEA Reports

Design procedure of capsule with multistage heater control, named MUSTAC

; Endo, Yasuichi; Hoshiya, Taiji; Niimi, Motoji;

JAERI-M 90-214, 57 Pages, 1990/11

JAERI-M-90-214.pdf:1.59MB

no abstracts in English

Journal Articles

Improvement in the temperature control method for irradiation capsules in the JMTR

; Endo, Yasuichi; ;

UTNL-R-0247, 6 Pages, 1990/00

no abstracts in English

Oral presentation

Development of improved type rabbit in JMTR

Kitagishi, Shigeru; Endo, Yasuichi; Matsui, Yoshinori

no journal, , 

no abstracts in English

Oral presentation

Establishment of irradiation facility for LWR water environment simulation tests

Kitagishi, Shigeru; Endo, Yasuichi; Okada, Yuji; Hanawa, Hiroshi; Matsui, Yoshinori; Tsuchiya, Kunihiko; Yamaura, Takayuki

no journal, , 

no abstracts in English

Oral presentation

Development of irradiation testing facility capable of simulating BWR / PWR reactor condition

Otsuka, Noriaki; Endo, Yasuichi; Tobita, Masahiro*; Matsui, Yoshinori; Yamaura, Takayuki

no journal, , 

no abstracts in English

19 (Records 1-19 displayed on this page)
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