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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

Development of Stress intensity factor coefficients database for a surface crack of an RPV considering the stress discontinuity between cladding and base metal

Onizawa, Kunio; Shibata, Katsuyuki*; Suzuki, Masahide

Proceedings of 2005 ASME/JSME Pressure Vessels and Piping Division Conference (PVP 2005), 12 Pages, 2005/07

Under a transient loading like pressurized thermal shock (PTS), the stress discontinuity near the interface between cladding and base metal of a reactor pressure vessel (RPV) is caused by the difference in their thermal expansion factors. So the stress intensity factor (SIF) of a surface crack which the deepest point exceeds the interface should be calculated by taking account of the stress discontinuity. Many SIF calculations are performed in Monte Carlo simulation of the probabilistic fracture mechanics (PFM) analysis. To avoid the time consuming process from the SIF calculation in the PFM analysis, the non-dimensional SIF coefficients corresponding to the stress distributions in the cladding and base metal were developed. The non-dimensional SIF coefficients database were obtained from 3D FEM analyses. The SIF value at the surface was determined by linear extrapolation of SIF value near the surface. Using the SIF coefficients database, the SIF values at both surface and deepest points of a surface crack can be evaluated precisely and in a reasonable time.

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.

JAEA Reports

Measurement of coolant flow in fuel elements at the JRR-4 silicide fuel core

Yamamoto, Kazuyoshi; Watanabe, Shukichi; Nagatomi, Hideki; Kaminaga, Masanori; Funayama, Yoshiro

JAERI-Tech 2002-034, 40 Pages, 2002/03

JAERI-Tech-2002-034.pdf:1.97MB

JRR-4, a swimming-pool type research reactor with a thermal power of 3.5MW, attained criticality in July 1998, after replacing its 90% enrichment fuel with a 20% enrichment fuel under the Reduced Enrichment Program. As a part of the program, safety analysis on thermo-hydraulics of the reactor core was conducted on cases including single channel blockage accident. With the conclusion that a certain margin on thermo-hydraulics was necessary, investigation and experiments were carried out with an aim to increase the core flow rate. To increase the core flow, it was carried out to reduce the bypass flow in the core and to increase the primary coolant flow rate from 7m$$^{3}$$/min to 8m$$^{3}$$/min. After flow measurements using a mock-up fuel element, flow velocity of the fuel channel was determined as 1.45m/s as opposed to the designed value of 1.44m/s, and the ratio of core flow to total flow was 0.88, exceeding the value 0.86 used for the safety analysis.This report describes the JRR-4 core flow increase plan as well as the results of the channel flow rate measurement

Journal Articles

Pressure dependence of supercritical carbon dioxide extraction equilibrium of palladium(II) with 2-Methyl-8-quinolinol

Ogiyanagi, Jin; Meguro, Yoshihiro; Yoshida, Zenko; Ohashi, Kozaburo*

Analytical Sciences (CD-ROM), 17(Suppl.), p.717 - 720, 2002/03

no abstracts in English

Journal Articles

Analytical study of volumetric scroll pump for liquid hydrogen circulating system

Kritmaitree, P.; Akiyama, Mitsunobu*; Hino, Ryutaro; Kaminaga, Masanori; Terada, Atsuhiko*

Journal of Nuclear Science and Technology, 39(1), p.101 - 107, 2002/01

 Times Cited Count:3 Percentile:74.77(Nuclear Science & Technology)

The paper presents analytical results of suction process of a volumetric scroll pump, which will be developed for circulating liquid hydrogen in a cold moderator system. The multi-block grid generation approch has been applied to generate a moving boundaries computational model. The finer mesh patterns have been generated in the near-wall regions. The analysis has been carried out under liquid hydrogen flow conditions. The analytical results show that at the end of suction process the relative pressures increase significantly in a pocket while decrease continuously in another pocket. This phenomenon might damage scroll pump components if the high-pressure side is too high and/or the low-pressure side is too low until the cavitations occur. Therefore, the pockect should open to the discharge chamber before it closes and separates from the suction chamber in order to prevent the cavitations and extremely high-pressure regions.

JAEA Reports

Design pressure differences and design velocities for core components of the JRR-3 silicide core

Kaminaga, Masanori; Murayama, Yoji; ;

JAERI-Tech 97-043, 63 Pages, 1997/09

JAERI-Tech-97-043.pdf:1.64MB

no abstracts in English

JAEA Reports

Core void fraction distribution under high-temperature high-pressure boil-off conditions; Experimental study with two-phase flow test facility(TPTF)

; Kumamaru, Hiroshige; Murata, Hideo; Anoda, Yoshinari; Kukita, Yutaka

JAERI-M 93-200, 56 Pages, 1993/10

JAERI-M-93-200.pdf:1.85MB

no abstracts in English

Journal Articles

Pressure effect on cation exchange distribution of some fission products on a strongly acidic cation exchanger of sulfonic acid type in nitric acid

Sato, Tadashi

Journal of Radioanalytical and Nuclear Chemistry, 152(1), p.219 - 225, 1991/00

 Times Cited Count:0 Percentile:100(Chemistry, Analytical)

no abstracts in English

Journal Articles

Distribution of $$gamma$$ and cosmic ray exposure rates in a 12-storied concrete building

Radiat.Prot.Dosim., 18(4), p.221 - 228, 1987/04

no abstracts in English

Journal Articles

Effect of magnetic field on the characteristics of hollow cathode ion source

; ; ; ; Ohara, Yoshihiro

Review of Scientific Instruments, 54(9), p.1104 - 1112, 1983/00

 Times Cited Count:13 Percentile:18.43(Instruments & Instrumentation)

no abstracts in English

Journal Articles

Hydrodynamic and hydraulic studies on void fractions in two-phase flow

; *

Journal of Nuclear Science and Technology, 15(12), p.886 - 898, 1978/00

 Times Cited Count:3

no abstracts in English

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