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JAEA Reports

Annual report of Engineering Services Department on JFY2020

Engineering Services Department

JAEA-Review 2021-054, 85 Pages, 2022/01

JAEA-Review-2021-054.pdf:95.12MB

The Engineering Services Department is in charge of operation and maintenance of utility facilities (water distribution systems, electricity supply systems, steam generation systems and drain water systems etc.) in whole of the institute. And also is in charge of operation and maintenance of specific systems (power receiving and transforming facilities, an emergency electric power supply system, an air/liquid waste treatment system, a compressed air supply system) in nuclear reactor facilities, nuclear fuel treatment facilities and usual facilities or buildings. In addition, the department is in charge of maintenance of buildings, design and repair of electrical/mechanical equipments. This annual report describes summary of activities, operation and maintenance data and technical developments of the department carried out in JFY 2020. We hope that this report may help to future work.

JAEA Reports

Annual report of Engineering Services Department on JFY2019

Engineering Services Department

JAEA-Review 2021-011, 86 Pages, 2021/08

JAEA-Review-2021-011.pdf:5.35MB

The Engineering Services Department is in charge of operation and maintenance of utility facilities (water distribution systems, electricity supply systems, steam generation systems and drain water systems etc.) in whole of the institute. And also is in charge of operation and maintenance of specific systems (power receiving and transforming facilities, an emergency electric power supply system, an air/liquid waste treatment system, a compressed air supply system) in nuclear reactor facilities, nuclear fuel treatment facilities and usual facilities or buildings. In addition, the department is in charge of maintenance of buildings, design and repair of electrical/mechanical equipments. This annual report describes summary of activities, operation and maintenance data and technical developments of the department carried out in JFY 2019. We hope that this report may help to future work.

JAEA Reports

Annual report of Engineering Services Department on JFY2018

Engineering Services Department

JAEA-Review 2019-044, 96 Pages, 2020/03

JAEA-Review-2019-044.pdf:6.11MB

The Engineering Services Department is in charge of operation and maintenance of utility facilities (water distribution systems, electricity supply systems, steam generation systems and drain water systems etc.) in whole of the institute. And also is in charge of operation and maintenance of specific systems (power receiving and transforming facilities, an emergency electric power supply system, an air/liquid waste treatment system, a compressed air supply system) in nuclear reactor facilities, nuclear fuel treatment facilities and usual facilities or buildings. In addition, the department is in charge of maintenance of buildings, design and repair of electrical/mechanical equipments. This annual report describes summary of activities, operation and maintenance data and technical developments of the department carried out in JFY 2018. We hope that this report may help to future work.

JAEA Reports

Applicability of statistical geometry model to light water moderating systems

Mori, Takamasa; Kojima, Kensuke*; Suyama, Kenya

JAEA-Research 2018-010, 57 Pages, 2019/02

JAEA-Research-2018-010.pdf:6.25MB

In order to estimate applicability of the statistical geometry model (STGM) of MVP/GMVP, a parametric study in infinite geometry and criticality safety analyses for direct disposal of spent fuel in simple finite geometry have been carried out by using the MVP Monte Carlo code. It has been found that calculations with STGM for larger fuel spheres give larger thermal utilization factors and larger infinite multiplication factors compared with explicit random models in the range of fuel sphere packing fraction between 6.5 % and 63.3 %. Substantial differences are not observed between the results with two nearest neighbor distributions (NNDs); that given by the MCRDF code and the analytical expression based on a statistically uniform distribution. It is inferred that the overestimation by STGM is caused by the facts that STGM cannot take account of the surroundings of each neutron, whether a fuel sphere rich region or a water moderator rich one, because STGM always uses an NND averaged over such surroundings and that STGM, therefore, cannot take the effect of consecutive scatterings in the water moderator into account.

JAEA Reports

Water jet intrusion into hot melt concomitant with direct-contact boiling of water

Shibamoto, Yasuteru

JAERI-Research 2005-016, 127 Pages, 2005/08

JAERI-Research-2005-016.pdf:4.54MB

no abstracts in English

Journal Articles

Seasonal characteristics of chemical compositions of the atmospheric aerosols collected in urban seaside area at Tokaimura, eastern central Japan

Fu, F.; Watanabe, Kazuo; Yabuki, Sadayo*; Akagi, Tasuku*

Journal of Geophysical Research, 109(20), p.D20212_1 - D20212_9, 2004/10

Size-separated aerosol samples were collected at Tokaimura urban seaside area of Japan using an Andersen type sampler during July 2002 to July 2003. The size-separated aerosols were divided into water-soluble and insoluble fractions, and chemical compositions (Na$$^{+}$$, Cl$$^{-}$$, NH$$_{3}$$$$^{+}$$, NO$$_{3}$$$$^{-}$$, SO$$_{4}$$$$^{2-}$$, Al, Ca, Mg, Fe, Pb, Th and U) in both water-soluble and insoluble fractions were analyzed. Then, the seasonal variations and the size-distribution in mass concentration and chemical composition have been investigated in detail. Our results showed that the atmospheric aerosol in Tokaimura was obviously affected by dust storm in China, and that sea-salt particles were bigger than those in the Antarctic and were deficient in chlorine.

Journal Articles

Subchannel analysis of CHF experiments for tight-lattice core

Nakatsuka, Toru; Tamai, Hidesada; Kureta, Masatoshi; Okubo, Tsutomu; Akimoto, Hajime; Iwamura, Takamichi

Proceedings of International Conference on Global Environment and Advanced Nuclear Power Plants (GENES4/ANP 2003) (CD-ROM), 6 Pages, 2003/09

It is important to evaluate thermal margin of the tight lattice core in the Reduced-Moderation Water reactor (RMWR). In the present study, to assess the applicability of subchannel analysis for tight lattice cores, tight lattice CHF experiments were analyzed with COBRA-TF code. For the axial uniform heated rod bundle, the code gives good prediction of critical power for mass velocity of around 500kg/(m$$^{2}$$s), while the code underestimates it for lower mass velocity and overestimates for higher mass velocity. The predicted BT position was outer channels and differed from the measured position. For the axially double-humped heated bundle, the code gives good prediction for mass velocity of around 200kg/(m$$^{2}$$s), and overestimates for higher mass velocity. It turned out that the two-phase multiplier of friction loss have a large influences on the flow distribution among the subchannels. To improve the calculation accuracy, it is required to predict precisely the flow distribution including the prediction of pressure distribution in a tight lattice bundle.

Journal Articles

Convenient method of UV-absorbing organic materials in river waters by high-performance gel permeation chromatography

Nagao, Seiya; Matsunaga, Takeshi; Suzuki, Yasuhiro*; Hiraki, Keizo*

Chikyu Kagaku, 35(3), p.107 - 120, 2001/08

no abstracts in English

Journal Articles

Molecular size distribution of Np, Pu and Am in organic rich, saline groundwater

Nagao, Seiya; Tanaka, Tadao; Nakaguchi, Yuzuru*; Suzuki, Yasuhiro*; Muraoka, Susumu; Hiraki, Keizo*

Understanding and Maraging Organic Matter in Soils, Sediments and Waters, p.525 - 532, 2001/00

no abstracts in English

Journal Articles

Measurement of flux tilt and eigenvalue separation in axially decoupled core

Ando, Masaki; *; Nishina, Kojiro*; *

Journal of Nuclear Science and Technology, 34(5), p.445 - 453, 1997/05

 Times Cited Count:6 Percentile:49.28(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Measurements and analyses of the ratio of $$^{238}$$U captures to $$^{235}$$U fission in low-enriched UO$$_{2}$$ tight lattices

Nakajima, Ken; ; Yamamoto, Toshihiro; ; Suzaki, Takenori

Journal of Nuclear Science and Technology, 31(11), p.1160 - 1170, 1994/11

 Times Cited Count:7 Percentile:57.56(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Measurement of reaction rates in FCA XIV-cores simulating high conversion light water reactor

Obu, Makoto; ; Sakurai, Takeshi; Iijima, Susumu; *; Osugi, Toshitaka

JAERI-M 90-052, 52 Pages, 1990/03

JAERI-M-90-052.pdf:1.31MB

no abstracts in English

JAEA Reports

Tritium distribution ratios between the 30% tributyl phosphate(TBP)-normal dodecane(nDD) organic phase and uranyl nitrate-nitric acid aqueous phase

Fujine, Sachio; Uchiyama, Gunzo; Sugikawa, Susumu; Maeda, Mitsuru; Tsujino, Takeshi

JAERI-M 89-152, 14 Pages, 1989/10

JAERI-M-89-152.pdf:0.48MB

no abstracts in English

JAEA Reports

Journal Articles

Distribution coefficients used for a safety assessment for shallow land radioactive waste burial

;

Nihon Genshiryoku Gakkai-Shi, 28(4), p.344 - 351, 1986/00

 Times Cited Count:0 Percentile:0.02(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Hybrid-Log-Normal distribution and its applications

Kumazawa, Shigeru; *

Oyo Tokeigaku, 15(1), p.1 - 14, 1986/00

no abstracts in English

Journal Articles

Two-dimensional fall back flow and core cooling in the slab core test facility: SCTF

; ; ;

Proc.2nd Int.Topical Meeting on Nuclear Power Plant Thermal Hydraulics and Operations, p.2 - 129, 1986/00

no abstracts in English

18 (Records 1-18 displayed on this page)
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