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JAEA Reports

System management for aggregation of knowledge on marine geological survey in coastal areas

Takahashi, Tadao*; Sato, Toshinori; Masunaga, Kosuke

JAEA-Review 2017-030, 60 Pages, 2018/01

JAEA-Review-2017-030.pdf:4.32MB

The amount of the information such as the data, models and analysis results related to geological environment has been enormous. It is believed that an appropriate organization of the information is useful for conducting geological environment survey work at the candidate sites of geological disposal. The Survey on Geological Disposal Technology projects commissioned by METI that started in FY2015 handles various information such as the data, models, analysis results, etc. of geological environment. In this project, in preparation for collection and compilation of the information on geological environment in coastal areas, we have made clear the current status of the existing systems including databases. At the same time, we have created measures for centralized information management for the purpose of organizing a huge amount of information as well as sharing the information and information management systems among the related organizations.

Journal Articles

Proving test and analyze for critical power performance in the RMWR tight lattice rod bundles under transient condition

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

Proceedings of 2005 International Congress on Advances in Nuclear Power Plants (ICAPP '05) (CD-ROM), 10 Pages, 2005/05

A major concern in the design of RMWR is that sufficient cooling capability be provided to keep fuel cladding temperature below specified values, even for a postulated abnormal transient process. In this research, centered the postulated transient cases that may be possibly met in the RMWR running, transient BT tests are performed in 7-rod and 37-rod double-humped tight lattice bundles, under the RMWR nominal operating condition (P = 7.2 MPa, Tin =556 K) for mass velocity G = 300 - 800 kg / (m$$^{2}$$s). Experiments are analyzed with TRAC code, in which JAERI critical power correlation is implemented for BT judgment. The traditional quasi-steady-state prediction of BT in transient process is confirmed being applicable for the postulated nominal transients in the RMWR cores.

Journal Articles

Critical power correlation for tight-lattice rod bundles

Liu, W.; Kureta, Masatoshi; Onuki, Akira; Akimoto, Hajime

Journal of Nuclear Science and Technology, 42(1), p.40 - 49, 2005/01

 Times Cited Count:7 Percentile:44.9(Nuclear Science & Technology)

In this research, critical power correlation for tight-lattice rod bundles is newly proposed using 7-rod axially uniform-heated data, 7-rod and 37-rod axially double-humped-heated data at Japan Atomic Energy Research Institute (JAERI). For low mass velocity region ($$<$$ 300 kg/m$$^{2}$$s), the correlation is written in critical quality - annular flow length type. For high mass velocity region ($$>$$ 300 kg/m$$^{2}$$s), it is written in local critical heat flux - critical quality type. The standard deviation of ECPR (Experimental Critical Power Ratio) to the whole JAERI data (694 data points) is 6%. The correlation is verified by Bettis Atomic Power Laboratory data (177 points, standard deviation: 7.7%). The correlation is confirmed being able to give good prediction for the effects of mass velocity, inlet temperature, pressure and heated equivalent diameter on critical power. The applicable range of the correlation is: gap between rods from 1.0 to 2.29 mm, heated length from 1.26 to 1.8 m, mass velocity from 150 to 2000 kg/m$$^{2}$$s and pressure from 2 to 11 MPa.

Journal Articles

Critical power in 7-rod tight lattice bundle

Liu, W.; Kureta, Masatoshi; Akimoto, Hajime

JSME International Journal, Series B, 47(2), p.299 - 305, 2004/05

Experimental research on critical power in tight lattice bundle that simulates the Reduced-Moderation Water Reactor (RMWR) has been carried out in Japan Atomic Energy Research Institute (JAERI). The bundle consists one center rod and six peripheral rods. The 7 rods are arranged on a 14.3 mm equilateral triangular pitch. Each rod is 13 mm in outside diameter. An axial 12-step power distribution is employed to simulate the complicate heating condition in RMWR. Experiments are carried out under ${it G}$ = 100-1400 kg/m$$^{2}$$s, ${it P}$$$_{ex}$$ = 2-8.5 MPa. Effects of mass velocity, inlet temperature, pressure, radial peaking factor and axial peaking factor on critical power and critical quality are discussed. Compared with axial uniform heating condition, the axial non-uniform heating condition causes an obvious decrease in critical quality. Arai correlation, which is the only correlation that has been optimized for tight lattice condition, is verified with the present experimental data. The correlation is found to be able to give reasonable prediction only around RMWR nominal operating condition.

JAEA Reports

Results of intercomparison test of the critical current and ac loss measurement on superconducting strands for the ITER coil

*; Takahashi, Yoshikazu; Nishi, Masataka; Isono, Takaaki; Tsuji, Hiroshi

JAERI-Research 96-013, 14 Pages, 1996/03

JAERI-Research-96-013.pdf:0.79MB

no abstracts in English

Journal Articles

New RIKEN-RAL pulsed $$mu$$CF facility and X-ray studies on DT-$$mu$$CF

Nagamine, Kanetada*; *; Ishida, Katsuhiko*; *; *; *; *; *; *; Tanase, Masakazu; et al.

Hyperfine Interactions, 101-102(1-4), p.521 - 538, 1996/00

no abstracts in English

JAEA Reports

Core Hydrodynamic Tests and Determination of Core Flow of JRR-3 to Be Renewed ata 20MWt

Sudo, Yukio; ; *;

JAERI-M 84-119, 108 Pages, 1984/06

JAERI-M-84-119.pdf:2.16MB

no abstracts in English

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