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JAEA Reports

Development of the Unified Cross-section Set ADJ2017

Yokoyama, Kenji; Sugino, Kazuteru; Ishikawa, Makoto; Maruyama, Shuhei; Nagaya, Yasunobu; Numata, Kazuyuki*; Jin, Tomoyuki*

JAEA-Research 2018-011, 556 Pages, 2019/03

JAEA-Research-2018-011.pdf:19.53MB
JAEA-Research-2018-011-appendix1(DVD-ROM).zip:433.07MB
JAEA-Research-2018-011-appendix2(DVD-ROM).zip:580.12MB
JAEA-Research-2018-011-appendix3(DVD-ROM).zip:9.17MB

We have developed a new unified cross-section set ADJ2017, which is an improved version of the unified cross-section set ADJ2010 for fast reactors. The unified cross-section set is used for reflecting information of C/E values (analysis / experiment values) obtained by integral experiment analyses, which are stored in the standard database for FBR core design via the cross-section adjustment methodology, which integrates with the information such as uncertainty (covariance) of nuclear data, uncertainty of integral experiment / analysis, sensitivity of integral experiment with respect to nuclear data. The ADJ2017 is based on Japan's latest nuclear data library JENDL-4.0 as in the previous version of ADJ2010, and it incorporates more information on integral experimental data related to minor actinides (MAs) and degraded plutonium (Pu). In the deveropment of ADJ2010, a total of 643 integral experimental data were analyzed and evaluated, and 488 of integral experimental data were finally selected to be used for the cross-section adjustment. In contrast, we have evaluated a total of 719 anlysis results, and eventually adopted 620 integral experimental data to create ADJ2017. ADJ2017 shows almost the same performance as ADJ2010 for the main neutronic characteristics of conventional sodium-cooled MOX-fuel fast reactors. In addition, for the neutrnic characteristics related to MA and degraded Pu, ADJ2017 improves the C/E values of the integral experimental data, and reduces the uncertainty induced by the nuclear data. ADJ2017 is expected to be widely used in the analysis and design research of fast reactors. Moreover, it is expected that the integral experimental data used for ADJ2017 can be utilized as a standard database of FBR core core design.

Journal Articles

Development of a new modular switch using a next-generation semiconductor

Takayanagi, Tomohiro; Ueno, Tomoaki*; Horino, Koki*

Journal of Physics; Conference Series, 1067, p.082019_1 - 082019_6, 2018/10

Journal Articles

Beam extraction by the laser charge exchange method using the 3-MeV LINAC in J-PARC

Takei, Hayanori; Hirano, Koichiro; Tsutsumi, Kazuyoshi; Meigo, Shinichiro

Plasma and Fusion Research (Internet), 13(Sp.1), p.2406012_1 - 2406012_6, 2018/03

The Japan Proton Accelerator Research Complex (J-PARC) has a plan to build the Transmutation Physics Experimental Facility (TEF-P), in which a 400-MeV negative proton (H$$^{-}$$) beam will be delivered from the J-PARC linac. Since the TEF-P requires a stable proton beam with a power of less than 10 W, a stable and meticulous beam extraction method is required to extract a small amount of the proton beam from the high power beam using 250 kW. To fulfil this requirement, the Laser Charge Exchange (LCE) method has been developed. To demonstrate the charge exchange of the H$$^{-}$$, a preliminary LCE experiment was conducted using a linac with energy of 3 MeV in J-PARC. As a result of the experiment, a charge-exchanged H$$^{+}$$ beam with a power of about 8 W equivalent and an accuracy of about 2% was obtained under the J-PARC linac beam condition.

Journal Articles

Yb:YAG thin-disk chirped pulse amplification laser system for intense terahertz pulse generation

Ochi, Yoshihiro; Nagashima, Keisuke; Maruyama, Momoko; Tsubouchi, Masaaki; Yoshida, Fumiko; Kono, Nanase; Mori, Michiaki; Sugiyama, Akira

Optics Express (Internet), 23(11), p.15057 - 15064, 2015/06

 Times Cited Count:17 Percentile:16.9(Optics)

We have developed a 1 kHz repetition picosecond laser system dedicated for intense terahertz (THz) pulse generation. The system comprises a chirped pulse amplification laser equipped with a Yb:YAG thin-disk amplifier. At room temperature, the Yb:YAG thin-disk regenerative amplifier provides pulses having energy of over 10 mJ and spectral bandwidth of 1.2 nm. The pulse duration achieved after passage through a diffraction grating pair compressor was 1.3 ps. By employing this picosecond laser as a pump source, THz pulses having a peak frequency of 0.3 THz and 4 $$mu$$J of energy were generated by means of optical rectification in an Mg-doped LiNbO$$_{3}$$ crystal.

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

Study of light output and response function of liquid organic scintillator for high-energy neutron spectrometry

Satoh, Daiki; Sato, Tatsuhiko; Endo, Akira; Matsufuji, Naruhiro*; Sato, Shinji*; Takada, Masashi*; Ishibashi, Kenji*

Nuclear Science Symposium Conference Record, 2005 IEEE, Vol.3, p.1288 - 1290, 2005/10

The response functions of a BC501A liquid organic scintillator have been measured for incidence of various charged particles to investigate the relationship between the kinetic energy of the charged particles and the light output of BC501A. The experiment was performed at Heavy-Ion Medical Accelerator in Chiba (HIMAC) utilizing spallation reactions by heavy ion bombardment on a graphite target. Charged particles incidental on BC501A were identified with the two-dimensional scatter plot of the time-of-flight and the light output. The light output of the BC501A scintillator was deduced as a function of the kinetic energy of the charged particles, and was compared with the semi-empirical formula. While the experimental data showed a good agreement with the formula for proton and deuteron, the data gave slightly larger values compared with the systematic trend for alpha particle.

JAEA Reports

Design of micro-fission chambers for ITER low power operations

Nishitani, Takeo; Yamauchi, Michinori*; Izumi, Mikio*; Kusama, Yoshinori

JAERI-Tech 2005-047, 34 Pages, 2005/09

JAERI-Tech-2005-047.pdf:6.75MB

no abstracts in English

Journal Articles

Current status of thermal/hydraulic feasibility project for reduced-moderation water reactor, 1; Large-scale thermal/hydraulic test

Tamai, Hidesada; Onuki, Akira; Kureta, Masatoshi*; Liu, W.; Sato, Takashi; Akimoto, Hajime

Proceedings of 2005 International Congress on Advances in Nuclear Power Plants (ICAPP '05) (CD-ROM), 8 Pages, 2005/05

no abstracts in English

JAEA Reports

Study on the application of CANDLE burnup strategy to several nuclear reactors, JAERI's nuclear research promotion program, H13-002 (Contract research)

Sekimoto, Hiroshi*

JAERI-Tech 2005-008, 111 Pages, 2005/03

JAERI-Tech-2005-008.pdf:15.9MB

The CANDLE burnup strategy is a new reactor burnup concept, where the distributions of fuel nuclide densities, neutron flux, and power density move with the same constant speed from bottom to top (or from top to bottom) of the core and without any change in their shapes. Therefore, any burnup control mechanisms are not required, and reactor characteristics do not change along burnup. The reactor is simple and safe. When this burnup scheme is applied to some neutron rich fast reactors, either natural or depleted uranium can be utilized as fresh fuel after second core and the bunrup of discharged fuel is about 40%. It means that the nuclear energy can be utilized for many hundreds years without new mining, enrichment and reprocessing, and the amount of spent fuel can be reduced considerably. Compared to fast reactors, application of CANDLE burnup to prismatic fuel high-temperature gas cooled reactors is very easy. In this report, the applications of CANDLE burnup to both these types of reactors are studied.

Journal Articles

Stabilization of beam power for long pulse operation on JT-60U negative-ion based NBI system

Honda, Atsushi; Kawai, Mikito; Okano, Fuminori; Oshima, Katsumi*; Numazawa, Susumu*; Oga, Tokumichi; Ikeda, Yoshitaka

Heisei-16-Nendo Osaka Daigaku Sogo Gijutsu Kenkyukai Hokokushu (CD-ROM), 4 Pages, 2005/03

no abstracts in English

Journal Articles

Validation of simplified evaluation models for first peak power, energy, and total fissions of a criticality accident in a nuclear fuel processing facility by TRACY experiments

Nomura, Yasushi*; Okuno, Hiroshi; Miyoshi, Yoshinori

Nuclear Technology, 148(3), p.235 - 243, 2004/12

 Times Cited Count:3 Percentile:73.38(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Evaluation of scale effects in tight-lattice bundles using subchannel analysis

Tamai, Hidesada; Yoshida, Hiroyuki; Masuko, Kenji*; Akimoto, Hajime

Proceedings of 4th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS-4), p.230 - 236, 2004/12

no abstracts in English

Journal Articles

Feasible approach to the power reactor concept

Nishio, Satoshi

Purazuma, Kaku Yugo Gakkai-Shi, 80(11), p.944 - 948, 2004/11

Low aspect ratio tokamak power reactor with super-conducting toroidal field (TF) coils has been proposed. A center solenoid coil system and an inboard blanket were removed. The key point was how to find the engineering design solution of the TF coil system with the high field and high current density. The coil system with the center post radius of less than 1 m can generate the maximum field of $$sim$$ 20 T. This coil system causes a compact reactor concept, where the plasma major and minor radii of 3.5 m and 1.5 m, respectively and the fusion power of $$sim$$ 3 GW.

Journal Articles

Present status of 972MHz RF test-stand at JAERI

Hori, Toshihiko*; Chishiro, Etsuji; Yamazaki, Masayoshi*; Suzuki, Hiroyuki*; Hasegawa, Kazuo

Proceedings of 1st Annual Meeting of Particle Accelerator Society of Japan and 29th Linear Accelerator Meeting in Japan, p.212 - 214, 2004/08

no abstracts in English

Journal Articles

Stable operation study of 972MHz RF test stand at JAERI

Hori, Toshihiko*; Chishiro, Etsuji; Yamazaki, Masayoshi*; Suzuki, Hiroyuki*; Hasegawa, Kazuo

KEK Proceedings 2003-16 (CD-ROM), 4 Pages, 2004/02

no abstracts in English

JAEA Reports

Estimation of heat removal characteristics for air-cooler in HTTR

Tochio, Daisuke; Nakagawa, Shigeaki; Takada, Eiji*; Sakaba, Nariaki; Takamatsu, Kuniyoshi

JAERI-Tech 2003-097, 55 Pages, 2004/01

JAERI-Tech-2003-097.pdf:3.34MB

In high temperature engineering test reactor (HTTR) of 30 MW, the generated heat at reactor core is finally dissipated at the air-cooler (ACL) by way of the heat exchangers of the primary pressurized water cooler (PPWC) and the intermediate heat exchanger (IHX). Therefore, air temperature (secondary-side condition at ACL) is important factor for the heat removal capability of the reactor. Coping with the air temperature, stable reactor inlet temperature control is achieved by adjusting of ACL coolant temperature with coolant (pressurized water and air) flow rate. ACL heat removal characteristic was based on the previous operation data in rise-to-power test and in-service operation at HTTR. And evaluate heat removal capability at summertime air temperature as the most severe condition was estimated. As the result, it was confirmed that the rated power of 30 MW can be removed at the condition of summertime air-temperature.

Journal Articles

Power profile evaluation of the JCO precipitation vessel based on the record of the $$gamma$$-ray monitor

Tonoike, Kotaro; Nakamura, Takemi*; Yamane, Yuichi; Miyoshi, Yoshinori

Nuclear Technology, 143(3), p.364 - 372, 2003/09

 Times Cited Count:2 Percentile:79(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Critical power correlation for axially uniformly heated tight-lattice bundles

Kureta, Masatoshi; Akimoto, Hajime

Nuclear Technology, 143(1), p.89 - 100, 2003/07

 Times Cited Count:10 Percentile:39.04(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Critical power in axially uniformly-heated tight-lattice rod bundles

Kureta, Masatoshi; Akimoto, Hajime

Nippon Kikai Gakkai Rombunshu, B, 69(682), p.1469 - 1476, 2003/06

no abstracts in English

JAEA Reports

Operation, test, research and development of the High Temperature Engineering Test Reactor (HTTR) (FY1999-2001)

Department of HTTR Project

JAERI-Review 2003-013, 98 Pages, 2003/05

JAERI-Review-2003-013.pdf:4.98MB

The HTTR (High Temperature Engineering Test Reactor) with the thermal power of 30 MW and the reactor outlet coolant temperature of 850/950$$^{circ}$$C is the first high temperature gas-cooled reactor (HTGR) in Japan, which uses coated-particle fuel, graphite for core components, and helium gas for primary coolant. The HTTR, which locates at the south-west area of 5000 m$$^{2}$$ in the Oarai Research Establishment, had been constructed since 1991 before accomplishing the first criticality on November 10, 1998. Rise to power tests of the HTTR started in September, 1999 and the rated thermal power of 30 MW and the reactor outlet coolant temperature of 850$$^{circ}$$C was attained in December 2001. JAERI received the certificate of pre-operation test, that is, the commissioning license for the HTTR in March 2002. This report summarizes operation, tests, maintenance, radiation control, and construction of components and facilities for the HTTR as well as R&Ds on HTGRs from FY1999 to 2001.

267 (Records 1-20 displayed on this page)