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JAEA Reports

Conceptual design of multipurpose compact research reactor; Annual report FY2011

Watahiki, Shunsuke; Hanakawa, Hiroki; Imaizumi, Tomomi; Nagata, Hiroshi; Ide, Hiroshi; Komukai, Bunsaku; Kimura, Nobuaki; Miyauchi, Masaru; Ito, Masayasu; Nishikata, Kaori; et al.

JAEA-Technology 2013-021, 43 Pages, 2013/07

JAEA-Technology-2013-021.pdf:5.12MB

The number of research reactors in the world is decreasing because of their aging. On the other hand, the necessity of research reactor, which is used for human resources development, progress of the science and technology, industrial use and safety research is increasing for the countries which are planning to introduce the nuclear power plants. From above background, the Neutron Irradiation and Testing Reactor Center began to discuss a basic concept of Multipurpose Compact Research Reactor (MCRR) for education and training, etc., on 2010 to 2012. This activity is also expected to contribute to design tool improvement and human resource development in the center. In 2011, design study of reactor core, irradiation facilities with high versatility and practicality, and hot laboratory equipment for the production of Mo-99 was carried out. As the result of design study of reactor core, subcriticality and operation time of the reactor in consideration of an irradiation capsule, and about the transient response of the reactor to the reactivity disturbance during automatic control operation, it was possible to do automatic operation of MCRR, was confirmed. As the result of design study of irradiation facilities, it was confirmed that the implementation of an efficient mass production radioisotope Mo-99 can be expected. As the result of design study with hot laboratory facilities, Mo-99 production, RI export devised considered cell and facilities for exporting the specimens quickly was designed.

JAEA Reports

Investigation on shortening fabrication process of instrumented irradiation capsule of JMTR

Nagata, Hiroshi; Inoue, Shuichi; Yamaura, Takayuki; Tsuchiya, Kunihiko; Nagao, Yoshiharu

JAEA-Technology 2013-008, 30 Pages, 2013/06

JAEA-Technology-2013-008.pdf:2.24MB

Refurbishment of JMTR was completed in FY2010. For damage caused by the 2011 off the Pacific coast of Tohoku Earthquake, the repair of facilities was completed in October 2012. Currently, the JMTR is in preparation for restart. Irradiation tests for LWRs safety research, science and technologies, etc. are expected after the JMTR restart. On the other hand, aiming at the attractive irradiation testing reactor, the usability improvement has been discussed. As a part of the usability improvement, shortening of turnaround time was discussed focusing on the fabrication process of irradiation capsules, where the fabrication process was analyzed and reviewed by referring a trial fabrication of the mockup capsule. As a result, it was found that the turnaround time can be shortened 2 months from fabrication period of 6 months with communize of irradiation capsule parts, application of ready-made instrumentation including the sheath heater, reconsideration of inspection process, etc.

Journal Articles

Status of irradiation capsule design

Nagata, Hiroshi; Yamaura, Takayuki; Nagao, Yoshiharu

UTNL-R-0483, p.10_3_1 - 10_3_9, 2013/03

no abstracts in English

JAEA Reports

Conceptual design of multipurpose compact research reactor; Annual report FY2010 (Joint research)

Imaizumi, Tomomi; Miyauchi, Masaru; Ito, Masayasu; Watahiki, Shunsuke; Nagata, Hiroshi; Hanakawa, Hiroki; Naka, Michihiro; Kawamata, Kazuo; Yamaura, Takayuki; Ide, Hiroshi; et al.

JAEA-Technology 2011-031, 123 Pages, 2012/01

JAEA-Technology-2011-031.pdf:16.08MB

The number of research reactors in the world is decreasing because of their aging. However, the planning to introduce the nuclear power plants is increasing in Asian countries. In these Asian countries, the key issue is the human resource development for operation and management of nuclear power plants after constructed them, and also the necessity of research reactor, which is used for lifetime extension of LWRs, progress of the science and technology, expansion of industry use, human resources training and so on, is increasing. From above backgrounds, the Neutron Irradiation and Testing Reactor Center began to discuss basic concept of a multipurpose low-power research reactor for education and training, etc. This design study is expected to contribute not only to design tool improvement and human resources development in the Neutron Irradiation and Testing Reactor Center but also to maintain and upgrade the technology on research reactors in nuclear power-related companies. This report treats the activities of the working group from July 2010 to June 2011 on the multipurpose low-power research reactor in the Neutron Irradiation and Testing Reactor Center and nuclear power-related companies.

JAEA Reports

Design of fuel transient test facility system

Hosokawa, Jinsaku; Iimura, Koichi; Ogawa, Mitsuhiro; Tomita, Kenji; Yamaura, Takayuki

JAEA-Technology 2010-018, 269 Pages, 2010/08

JAEA-Technology-2010-018.pdf:5.75MB

At Oarai Research and Development Center, Japan Atomic Energy Agency (JAEA) advances the plan of refurbishing Japan Materials Testing Reactor (JMTR) to start the operation in fiscal 2011. Fuel Transient Test Facility is scheduled to be set up as neutron irradiation test equipment of the light-water reactor fuel that uses JMTR after it operates again. The abnormal transition examination device is the irradiation facilities where the output sudden rise examination that makes the light-water reactor fuel an irradiation sample is done to use it to develop the safety evaluation technology and the damage influence evaluation technology of the light-water reactor fuel that reaches high burn-up. In this report, as for the system design, it is a summary to JMTR among detailed designs of the abnormal transition examination device of the installation schedule.

JAEA Reports

Development of mechanical seal structure for reuse of re-instrumentation device used in fuel irradiation test

Inoue, Shuichi; Yamaura, Takayuki; Saito, Takashi; Ishikawa, Kazuyoshi; Kikuchi, Taiji; Sozawa, Shizuo; Tsuchiya, Kunihiko

JAEA-Technology 2009-076, 33 Pages, 2010/03

JAEA-Technology-2009-076.pdf:18.29MB

In Japan Material Testing Reactor (JMTR), a lot of experiments of fuel irradiation with the power ramping tests have been performed by using the shroud irradiation facility and the Boiling Water Capsule (BOCA). The fuel samples used in these tests were welded to re-instrumentation devices such as thermocouples and FP gas pressures. In this development, the mechanical connection method as "mechanical seal structure", that enables the re-use of re-instrumentation devices, was adopted in order to improve the utilization efficiency of the device. The test samples with mechanical seal structure were fabricated and the confirmatory tests such as He leakage test, thermal cycle test, autoclave test, etc. were carried out. The test samples with the mechanical seal structure showed an excellent result in various confirmatory tests, and the prospect are bright for the re-use of re-instrumentation devices with the mechanical seal structure.

Journal Articles

Development of mechanical seal for re-capsule

Inoue, Shuichi; Yamaura, Takayuki; Saito, Takashi; Kanno, Masaru

UTNL-R-0475, p.2_4_1 - 2_4_10, 2010/03

no abstracts in English

JAEA Reports

Thermal-hydraulic tests with out-of-pile test facility simulating natural convection capsule

Inaba, Yoshitomo; Sakamoto, Taichi; Yamaura, Takayuki

JAEA-Technology 2009-080, 22 Pages, 2010/02

JAEA-Technology-2009-080.pdf:7.06MB

The power transient tests for the fuels of light water reactors are to be carried out in the Japan Materials Testing Reactor (JMTR) using capsule-type test facilities, and the integrity of the fuels is to be investigated by the tests. Prior to the irradiation tests of the fuels, the out-of-pile test facility, which had an electric heater pin instead of a test fuel pin, was designed and fabricated to simulate the capsules used in the power transient tests. Using this facility, necessary tests for the planning of the test methods were carried out. In the present report, the outline of the out-of-pile test facility, the test plan and the tests simulating natural convection capsule were described. As a result of the tests, it was found that the power of the heater pin with a diameter of 9.5 mm can achieve to 600 W/cm without transition from nucleate boiling to film boiling under BWR and PWR coolant pressure conditions.

JAEA Reports

Seismic analysis for shroud facility in-pile tube and saturated temperature capsules

Iimura, Koichi; Yamaura, Takayuki; Ogawa, Mitsuhiro

JAEA-Technology 2009-033, 45 Pages, 2009/07

JAEA-Technology-2009-033.pdf:5.01MB

At Oarai Research and development center, Japan Atomic Energy Agency (JAEA), the plan of repairing and refurbishing Japan Materials Testing Reactor (JMTR) has progressed in order to restart JMTR operation in the fiscal 2011. By using Oarari Shroud Facility and fuel irradiation facility with the He-3 gas control system for power lamping test using boiling water capsules. By using saturated temperature capsules and the water environment control system, the material irradiation tests under the water chemistry condition of LWL will be carried out to clarify the mechanism of IASCC. The detailed design for renewal or remodeling was carried out based on the new design condition in order to be correspondent to the irradiation test plan after restart JMTR operation. Stress calculation and evaluation were carried out by fem piping analysis code SAP and structure analysis code ABAQUS. It was proven by the analysis that these facilities maintain the structural integrity under earthquake condition.

JAEA Reports

Numerical analysis on thermal-hydraulic behavior in natural convection capsules

Inaba, Yoshitomo; Ogawa, Mitsuhiro; Yamaura, Takayuki; Tobita, Masahiro

JAEA-Technology 2009-032, 51 Pages, 2009/07

JAEA-Technology-2009-032.pdf:8.74MB

The fuel transient tests for light water reactors are to be carried out in the Japan Materials Testing Reactor (JMTR), and the capsule-type test facilities (fuel transient test capsules) are to be used in the tests. In order to investigate the thermal-hydraulic behavior in the capsules, the multi-dimensional two-fluid model code ACE-3D is used. At first, the functions of ACE-3D were expanded for the pre-process and the post-process. Then, the BWR power calibration test capsule, which had been tested in JMTR, was modeled, and the BWR power calibration tests were simulated numerically for the verification of ACE-3D. The numerical results agreed well with the test data. As a result, it was found that ACE-3D is applicable to the numerical simulation of the fuel transient tests. In addition, the fuel transient tests with a natural convection capsule were simulated numerically with ACE-3D, and the thermal-hydraulic behavior in the capsule was investigated.

JAEA Reports

The Present situation and future utilization of testing reactors in the world

Ito, Haruhiko; Ide, Hiroshi; Yamaura, Takayuki; Tsuji, Tomoyuki

JAERI-Review 2004-001, 39 Pages, 2004/02

JAERI-Review-2004-001.pdf:2.02MB

no abstracts in English

Journal Articles

Effect of neutron irradiation on electromotive force of oxygen sensor using zirconia solid electrolyte

Hiura, Nobuo*; Yamaura, Takayuki; Motohashi, Yoshinobu*; Kobiyama, Mamoru*

Nihon Genshiryoku Gakkai Wabun Rombunshi, 1(2), p.202 - 208, 2002/06

The purpose of this study is to develop oxygen sensor which can measure the oxygen potential of the fuel in a nuclear reactor. The oxygen sensor with CaO stabilized zirconia solid electrolyte has been specially designed in order to prolong its life time. Electromotive force (EMF) of solid galvanic cell Ni/NiO|ZrO$$_{2}$$-CaO|Fe/FeO was measured in both the out-pile tests and the in-situ tests using Japan Material Testing Reactor (JMTR), and the characteristics of EMF was discussed. In the out-pile test, it was found that the EMF was almost equal to the theoretical values at temperatures ranging from 700 to 1,000$$^{circ}C$$, and the life span of the sensor was very long up to 980h at 800$$^{circ}C$$. In the in-situ test, it was found that the EMF showed almost the reliable values up to 300 h (neutron fluence (E $$>$$ 1 MeV) 1.5$$times$$10$$^{23}$$ m$$^{-2}$$), at temperatures from 700 to 900$$^{circ}C$$. The imprecision of the EMF was found to be within 6% of the theoretical values up to 1,650 h irradiation time (neutron fluence (E $$>$$ 1 MeV) 8.0$$times$$10$$^{23}$$ m$$^{-2}$$) at 800$$^{circ}C$$. The oxygen sensors were found to be applicable for the oxygen potential measurement of the fuels in a reactor.

Journal Articles

Overview of recent development on irradiation technique for the JMTR

Komori, Yoshihiro; Matsui, Yoshinori; Itabashi, Yukio; Yamaura, Takayuki; Nagao, Yoshiharu

KAERI/GP-195/2002, p.59 - 69, 2002/00

JAERI has been developing irradiation technique and facilities for irradiation tests in the JMTR to improve irradiation capability keeping up with progress of nuclear fuels and materials research. This paper summarizes recent development on irradiation technique for the JMTR. Design study and installation of the IASCC (Irradiation Assisted Stress Corrosion Cracking) irradiation test facility was main and the most urgent task of the field in the last five years since two large projects for IASCC were planned in Japan to start irradiation tests in 2002. Almost four years were devoted to preliminary design study, detail design and installation of the facility, then IASCC irradiation test started in March, 2002. Instrumentation technique and capsules development for other research purposes also have been steadily progressing during the term, and new type of off-line temperature monitor, dual re-instrumentation device and the uniform irradiation capsule became available for the irradiation tests.

JAEA Reports

Development of welding technique by remote control at the JMTR hot laboratory

Shimizu, Michio; Iwamatsu, Shigemi; Takada, Fumiki; Sozawa, Shizuo; Kawamata, Kazuo; Oshima, Kunio; Tsuchiya, Kunihiko; Yamaura, Takayuki; Matsui, Yoshinori; Iwai, Takashi; et al.

JAERI-Tech 2000-029, p.48 - 0, 2000/03

JAERI-Tech-2000-029.pdf:9.26MB

no abstracts in English

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:50.34(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

Oral presentation

Advanced irradiation technology for LWR fuel and material; Development of mechanical seal structure for BOCA

Inoue, Shuichi; Yamaura, Takayuki; Ishikawa, Kazuyoshi; Saito, Takashi; Tsuchiya, Kunihiko

no journal, , 

no abstracts in English

Oral presentation

Refurbishment and restart of JMTR, 7; Technology development for attractive irradiation tests, 1; Mechanical seal for reutilization of instruments

Inoue, Shuichi; Yamaura, Takayuki; Ishikawa, Kazuyoshi; Saito, Takashi; Sozawa, Shizuo; Tsuchiya, Kunihiko

no journal, , 

no abstracts in English

Oral presentation

Refurbishment and restart of JMTR, 4; Plan of new irradiation test facility, 1; Fuel transient test facility system

Nagata, Hiroshi; Yamaura, Takayuki; Hosokawa, Jinsaku; Matsui, Yoshinori; Kanno, Masaru

no journal, , 

no abstracts in English

31 (Records 1-20 displayed on this page)