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Journal Articles

Failure experiments on pipes with local wall thinning subjected to multi-axial loads

Li, Y.; Hasegawa, Kunio; Miura, Naoki*; Hoshino, Katsuaki*

Journal of Pressure Vessel Technology, 139(2), p.021203_1 - 021203_7, 2017/04

 Times Cited Count:0 Percentile:0.00(Engineering, Mechanical)

In order to investigate the failure behavior of the pipes with local wall thinning subjected to multi-axial loads including the torsion, failure experiments were performed on 20 mm diameter carbon steel pipes with a local wall thinning. Based on the experimental results, the failure estimation method is investigated.

Journal Articles

Experimental study on failure estimation method for circumferentially cracked pipes subjected to multi-axial loads

Li, Y.; Hasegawa, Kunio; Miura, Naoki*; Hoshino, Katsuaki*

Journal of Pressure Vessel Technology, 139(1), p.011204_1 - 011204_10, 2017/02

 Times Cited Count:3 Percentile:16.80(Engineering, Mechanical)

To investigate the failure behavior of cracked pipes subjected to multi-axial loads including the torsion moment, failure experiments were performed on 20 mm diameter stainless steel pipes with a circumferential surface crack or a through-wall crack under combined axial force, bending and torsion moments. Based on the experimental results, the failure estimation methods were investigated.

Journal Articles

Experimental study on failure estimation method for circumferentially cracked pipes subjected to multi-axial loads

Li, Y.; Hasegawa, Kunio; Miura, Naoki*; Hoshino, Katsuaki*

Proceedings of 2015 ASME Pressure Vessels and Piping Conference (PVP 2015) (Internet), 10 Pages, 2015/07

The failure estimation method in ASME Code Section XI accounts for the bending moment and axial force due to pressure into account. The torsion moment is not considered. Recently, analytical investigations have been carried out by several authors on the limit load of cracked pipes considering multi-axial loads including torsion and two failure estimation methods for multi-axial loads including torsion moment with different ranges of values have been proposed. In this study, to investigate the failure behavior of cracked pipes subjected to multi-axial loads including the torsion moment and to provide experimental support for the failure estimation methods, failure experiments were performed on 20 mm diameter pipes with a circumferential surface crack or a through-wall crack under combined axial force and bending and torsion moments. Based on the experimental results, the proposed failure estimation methods were confirmed to be applicable to cracked pipes subjected to multi-axial loads.

Journal Articles

Failure experiments on pipes with local wall thinning subjected to multi-axial loads

Li, Y.; Hasegawa, Kunio; Miura, Naoki*; Hoshino, Katsuaki*

Proceedings of 2015 ASME Pressure Vessels and Piping Conference (PVP 2015) (Internet), 8 Pages, 2015/07

Piping lines in nuclear power plants may experience multi-axial loads including tensile force, bending and torsion moments during operation. There is a lack of guidance for failure evaluation under the multi-axial loads including torsion moment. ASME B&PV Code Section XI Working Group is currently developing fully plastic failure evaluation procedures for pressurized piping items containing local wall thinning subjected to multi-axial loads. A failure estimation method for locally wall thinned pipes subjected to multi-axial loads including torsion moment has been proposed through numerical analyses. In this study, in order to investigate the failure behavior of the pipes with local wall thinning subjected to multi-axial loads including the torsion, failure experiments were performed on 20 mm diameter carbon steel pipes with a local wall thinning. Based on the experimental results, the proposed failure estimation method is confirmed to be applicable to pipes with local wall thinning.

JAEA Reports

Experimental Fast Reactor JOYO MK-III Functional Test; Secondary Cooling System Main Pumps Test

Terakado, Tsuguo; Morimoto, Makoto; Izawa, Osamu; Ishida, Koichi; Hoshino, Katsuaki; Suzuki, Shinya; Ito, Hideaki; Aoki, Hiroshi; Odo, Toshihiro

JNC TN9430 2004-003, 87 Pages, 2004/03

JNC-TN9430-2004-003.pdf:2.86MB

This paper describes the results of Secondary Cooling System main pumps test ,which were done as a part of JOYO MK-3 function test. The function tests were cexcuted to get the operating characteristics of secondary cooling system, after the Intermediate Heat Exchangers, Dump Heat Exchangers, secondary main pump motors, pump speed control board and rheostat were replaced in the MK-3 conversion. These tests are composed of six items. These tests purpose are confirmed in the function of the Main pumps, sodium purification system and argon cover gas pressure control system in Secondary Cooling System. (1) SKS-205-1: flow control test, (2) SKS-205-2: flow coast down characteristics test, (3) SKS-205-3: running operation test, (4) SKS-205-4: pump vibration measurement test, (5) SKS-212: secondary sodium purification system electromagnetic-pump flow control test, (6) SKS-213: argon cover gas pressure in secondary cooling system pressure control test function tests are satisfied the design criteria. We have confirmed the system performance of the main pump, secondary sodium purification system and argon cover gas pressure control system in the Secondary Cooling System after the MK-3 conversion.

JAEA Reports

Development of the Automatic Control Rod Operation System for JOYO; Appreciation of apply to MK-III reactor operation

Terakado, Tsuguo; Hoshino, Katsuaki; Suzuki, Shinya; Ito, Hideaki; Aoki, Hiroshi; Odo, Toshihiro

JNC TN9410 2004-008, 55 Pages, 2004/03

JNC-TN9410-2004-008.pdf:1.82MB

The automatic control rod operation system was developed to control the JOYO reactor power automatically in all operation modes(critical approach, cooling system heat up, power ascent and power descent), development began in 1989. Prior to applying, we are examined possibility of apply to the automatic control rod operation guide system which developed in MK-2 operation to get the control rod operation guide data in MK-3 performance tests. The main results are as follows: (1).Critical approach mode in control rod operation guide function will be need tuning of fuzzy algorisms structure for changed MK-3 reactor critical point. (2).Cooling system heet up mode, power ascent mode and power descent mode will be supply to good guidance at MK-3 reactor operation. Because, power change rate and cooling system heet up rate same MK-2 reactor operation. (3).Plant operation guide function will be need change, based on MK-3 reactor operation manual. (4).The automatic control rod operation guide system will be need renewal for system maintainability.

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