Refine your search:     
Report No.
 - 
Search Results: Records 1-20 displayed on this page of 28

Presentation/Publication Type

Initialising ...

Refine

Journal/Book Title

Initialising ...

Meeting title

Initialising ...

First Author

Initialising ...

Keyword

Initialising ...

Language

Initialising ...

Publication Year

Initialising ...

Held year of conference

Initialising ...

Save select records

Journal Articles

Investigation for tiny metal contamination of water cooling system in J-PARC Linac

Suganuma, Kazuaki; Hiroki, Fumio; Ito, Takashi; Yamazaki, Yoshio

Proceedings of 16th Annual Meeting of Particle Accelerator Society of Japan (Internet), p.846 - 848, 2019/07

In the past, water flow decreased at water cooling system in J-PARC Linac. Contamination get mixed in cooling water. The problem was resolved by changing the system of the circulation pumps and reducing the tiny metal in water cooling system. However, suppression of occurring tiny metal is unresolved. The tiny metal is the unique problem of accelerator. It is caused by heavy using oxygen free copper and phosphorus deoxidized copper. The two copper is used for the part of accelerator and purified water. The object of the report is investigation of tiny metal contamination of water cooling system in J-PARC Linac.

Journal Articles

Vibration analysis of water cooling towers' defective fan bearing units at J-PARC RCS

Fujirai, Kosuke; Suganuma, Kazuaki; Yamazaki, Yoshio

Proceedings of 14th Annual Meeting of Particle Accelerator Society of Japan (Internet), p.874 - 876, 2017/12

The J-PARC (Japan Proton Accelerator Research Complex) 3-GeV RCS (Rapid Cycling Synchrotron) has many devices such as Radio-Frequency components, electromagnets and power supplies. These devices use 17MW of electricity during operation, most of which is consumed as thermal energy. Therefore, cooling water equipment is indispensable for the operation of the accelerator and its stability affects the operation rate of the accelerator. Due to resent operation experience, the bearing unit of the cooling tower fan, which is also an important part of the cooling water equipment, broke down. This accident leads to the suspension of the J-PARC operation. In order to investigate the cause of the failure, we tried to measure vibration for the defective bearing and the bearing unit were cut and observed damaged surface. As a result of the vibration measurement, it was found that vibration frequency depends on the presence or absence of scratches on the bearing. We found surface of the outer ring had scratches called flaking.

JAEA Reports

Simulation tests for thermal characteristics of JCO precipitation vessel using a mock-up device

Watanabe, Shoichi; Miyoshi, Yoshinori; Yamane, Yuichi

JAERI-Tech 2002-043, 93 Pages, 2002/03

JAERI-Tech-2002-043.pdf:6.74MB

no abstracts in English

JAEA Reports

Estimation of thermochemical behavior of spallation products in mercury target

Kobayashi, Kaoru*; Kaminaga, Masanori; Haga, Katsuhiro; Kinoshita, Hidetaka; Aso, Tomokazu; Teshigawara, Makoto; Hino, Ryutaro

JAERI-Tech 2002-005, 118 Pages, 2002/02

JAERI-Tech-2002-005.pdf:9.71MB

In order to examine the radiation safety of a spallation mercury target system, it is necessary to clarify the chemical forms of spallation products generated by spallation reaction with proton beam. As for the chemical forms of spallation products in mercury that involves large amounts of spallation products, these forms were estimated by using the binary phase diagrams and the thermochemical equilibrium calculation based on the amounts of spallation product. Calculation results showed that the mercury would dissolve Al, As, B, Be, Bi, C, Co, Cr, Fe, Ga, Ge, Ir, Mo, Nb, Os, Re, Ru, Sb, Si, Ta, Tc, V and W in the element state, and Ag, Au, Ba, Br, Ca, Cd, Ce, Cl, Cs, Cu, Dy, Er, Eu, F, Gd, Hf, Ho, I, In, K, La, Li, Lu, Mg, Mn, Na, Nd, Ni, O, Pb, Pd, Pr, Pt, Rb, Rh, S, Sc, Se, Sm, Sn, Sr, Tb, Te, Ti, Tl, Tm, Y, Yb, Zn and Zr in the form of inorganic mercury compounds.

JAEA Reports

The 3rd technological meeting of Tokai reprocessing plant

Maki, Akira; ; Taguchi, Katsuya; ; Shimizu, Ryo; Shoji, Kenji;

JNC-TN8410 2001-012, 185 Pages, 2001/04

JNC-TN8410-2001-012.pdf:9.61MB

"The third technological meeting of Tokai Reprocessing plant (TRP)" was held in JNFL Rokkasyo site on March 14$$^{th}$$, 2001. The technical meetings have been held in the past two times. The first one was about the present status and future plan of the TRP and second one was about safety evaluation work on the TRP. At this time, the meeting focussed on the corrosion experrience, in-service inspection technology and future maintenance plan. The report contains the proceedings, transparancies and questionnaires of the meeting are contained.

Journal Articles

Two-phase flow behavior with boiling caused by ingress of water into vacuum vessels of fusion reactors

Takase, Kazuyuki; Ose, Yasuo*; Akimoto, Hajime

Dai-37-Kai Nippon Dennetsu Simpojiumu Koen Rombunshu, p.703 - 704, 2000/05

no abstracts in English

JAEA Reports

Development of whole core thermal-hydraulic analysis program ACT (III); Coupling core module with primary heat transport system module

; Ohshima, Hiroyuki

JNC-TN9400 98-004, 34 Pages, 1998/10

JNC-TN9400-98-004.pdf:1.44MB

A whole core thermal hydraulic analysis program ACT is being developed for the purpose of evaluating detailed in-core thermal hydraulic phenomena of fast reactors including inter-wrapper flow under various reactor operation conditions. In this work, the core module as a main part of the ACT developed last year, which simulates thermal-hydraulics in the subassemblies and the inter-subassembly gaps, was coupled with an one dimensional plant system thermal-hydraulic analysis code LEDHER to simulate transients in the primary heat transport system and to give appropriate boundary conditions to the core model. The effective algorithm to couple these two calculation modules was developed, which required minimum modification of them. In order to couple these two calculation modules on the computing system, parallel computing technique using PVM(Parallel Virtual Machine) programming environment was applied. The code system was applied to analyze an out-of-pile sodium experiment simulating core with 7 subassemblies under transient condition for code verification. It was confirmed that analytical results show a similar tendency of experimental results.

JAEA Reports

Study on thermal-hydraulics during a PWR reflood phase

Iguchi, Tadashi

JAERI-Research 98-054, 216 Pages, 1998/10

JAERI-Research-98-054.pdf:7.94MB

no abstracts in English

JAEA Reports

Design and first integral test of MUSE facility in ALPHA program

H.Park*; ; Maruyama, Yu; Moriyama, Kiyofumi; Kudo, Tamotsu; Y.Yang.*; Sugimoto, Jun

JAERI-Tech 98-007, 62 Pages, 1998/03

JAERI-Tech-98-007.pdf:2.44MB

no abstracts in English

Journal Articles

Measurement method of $$^{35}$$S concentration in primary cooling water by LSC

Sato, Koichi;

Hoken Butsuri, 31(2), p.230 - 233, 1996/00

no abstracts in English

Journal Articles

Ceramic breeding blanket development for experimental fusion reactor in JAERI

Kurasawa, Toshimasa; Takatsu, Hideyuki; Sato, Satoshi; Mori, Seiji*; Hashimoto, T.*; Nakahira, Masataka; Furuya, Kazuyuki; Tsunematsu, Toshihide; Seki, Masahiro; Kawamura, Hiroshi; et al.

Fusion Engineering and Design, 27, p.449 - 456, 1995/00

 Times Cited Count:7 Percentile:38.98(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Study of air vent design for inverted U-tube type heat exchanger

Takada, Shoji; Shibata, Mitsuhiko; ; Fujisaki, Katsuo; Ota, Yukimaru; ;

JAERI-M 94-013, 89 Pages, 1994/02

JAERI-M-94-013.pdf:2.77MB

no abstracts in English

JAEA Reports

Study on improvement of constitutive equations and numerical methods for three-fluid model

*; *; Kataoka, Isao*; Mishima, Kaichiro*; *; Abe, Yutaka*

PNC-TJ9565 93-001, 265 Pages, 1993/04

PNC-TJ9565-93-001.pdf:6.09MB

The purpose of the present study is to improve a numerical method for multiphase flows based on the three-fluid model. Conducted were (1) improvement of a numcrical scheme, (2)examination on the validity of governing equations, (3)survey and verification of available constitutive equations, (4)development of theoretical constitutive equations and (5) numerical analyses of experimental database on steam-water and air-water annular-mist flows. As a result, the following conclusions were obtained: (a)multi-fluid modelling for all flow regimes were completed, (b)numerical stability of the three-fluid model was clarified, (c)stability-enhanced solution method was developed, (d)a physically-rational and well-posed multi-fluid model was proposed for dispersed flows, (e)systematic survey and evaluation of available constitutive equations for entrainment was conducted and summarized, (f)a theoretical method for the evaluation of film thickness and interfacial shear stress was presented, and(g)it was confirmed that FIDAS-1DS can accurately predict critical heat fluxes under atmospheric pressure, and that it can give qualitatively good predictions conserning film thickness, droplet flow rate and so forth of the air-water annular-mist flow.

JAEA Reports

Test apparatus for ITER blanket cooling water distributor design

Yoshida, Hiroshi; Enoeda, Mikio; Hirata, Shingo*; Ito, H.*

JAERI-M 92-070, 45 Pages, 1992/05

JAERI-M-92-070.pdf:1.34MB

no abstracts in English

Journal Articles

JMTR modification to ensure reactor safety concerning with core conversion to low enriched uranium fuel

Sato, Takeshi; ; Nagaoka, Yoshiharu; ; Saito, Junichi; Ishitsuka, Etsuo; Ando, Hiroei; Saito, Minoru;

UTNL-R-0274, p.1-1 - 1-11, 1992/00

no abstracts in English

JAEA Reports

JAEA Reports

Journal Articles

An application of flow injection analysis to water quality monitoring system

; ;

Boshoku Gijutsu, 36(4), p.234 - 238, 1987/04

no abstracts in English

Journal Articles

The fracture toughness measured on sensitized 304 stainless steel in simulated reactor water

; *; Nakajima, Hajime; Kondo, Tatsuo

Nucl.Eng.Des., 93, p.95 - 106, 1986/00

 Times Cited Count:6 Percentile:39.73(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Reduction of delayed gamma ray backgrounds for a pulsed neutron source

Nuclear Instruments and Methods in Physics Research A, 253, p.43 - 46, 1986/00

 Times Cited Count:0 Percentile:100

no abstracts in English

28 (Records 1-20 displayed on this page)