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JAEA Reports

Data report of ROSA/LSTF experiment SB-HL-12; 1% Hot leg break LOCA with SG depressurization and gas inflow

Takeda, Takeshi

JAEA-Data/Code 2015-022, 58 Pages, 2016/01

JAEA-Data-Code-2015-022.pdf:3.31MB

The SB-HL-12 test simulated PWR 1% hot leg SBLOCA under assumptions of total failure of HPI system and non-condensable gas (nitrogen gas) inflow. SG depressurization by fully opening relief valves in both SGs as AM action was initiated immediately after maximum fuel rod surface temperature reached 600 K. After AM action due to first core uncovery by core boil-off, the primary pressure decreased, causing core mixture level swell. The fuel rod surface temperature then increased up to 635 K. Second core uncovery by core boil-off took place before LSC induced by steam condensation on ACC coolant injected into cold legs. The core liquid level recovered rapidly after LSC. The fuel rod surface temperature then increased up to 696 K. The pressure difference became larger between the primary and SG secondary sides after nitrogen gas inflow. Third core uncovery by core boil-off occurred during reflux condensation. The maximum fuel rod surface temperature exceeded 908 K.

JAEA Reports

Data report of ROSA/LSTF experiment SB-CL-32; 1% cold leg break LOCA with SG depressurization and no gas inflow

Takeda, Takeshi

JAEA-Data/Code 2014-021, 59 Pages, 2014/11

JAEA-Data-Code-2014-021.pdf:5.16MB

Experiment SB-CL-32 was conducted on May 28, 1996 using the LSTF. The experiment SB-CL-32 simulated 1% cold leg small-break LOCA in PWR under assumptions of total failure of HPI system and no inflow of non-condensable gas from ACC tanks. Secondary-side depressurization of both SGs as AM action to achieve the depressurization rate of 200 K/h in the primary system was initiated 10 min after break. Core uncovery started with liquid level drop in crossover leg downflow-side. The core liquid level recovered rapidly after first LSC. The surface temperature of simulated fuel rod then increased up to 669 K. Core uncovery took place before second LSC induced by steam condensation on ACC coolant. The core liquid level recovered rapidly after second LSC. The maximum fuel rod surface temperature was 772 K. The continuous core cooling was confirmed because of coolant injection by LPI system. This report summarizes the test procedures, conditions and major observation.

Journal Articles

Response analysis of radioactive gas monitors for short duration inflow of radioactive gas

Oishi, Tetsuya; Yoshida, Makoto

Journal of Nuclear Science and Technology, 38(12), p.1115 - 1119, 2001/12

no abstracts in English

Journal Articles

Low electric field (0.08V m$$^{-1}$$) plasma-current start-up in JT-60U

Yoshino, Ryuji; Seki, Masami

Plasma Physics and Controlled Fusion, 39(1), p.205 - 222, 1997/01

 Times Cited Count:30 Percentile:29.18(Physics, Fluids & Plasmas)

no abstracts in English

Journal Articles

Experimental and analytical results for cooling performance of HTTR core bottom structure using HENDEL-T$$_{2}$$

Ioka, Ikuo; Inagaki, Yoshiyuki; Suzuki, Kunihiro; Kunitomi, Kazuhiko;

Nippon Genshiryoku Gakkai-Shi, 37(3), p.217 - 227, 1995/00

 Times Cited Count:1 Percentile:81.68(Nuclear Science & Technology)

no abstracts in English

Journal Articles

PWR thermal-hydraulic phenomena following loss of residual heat removal(RHR) during mid-loop operation

Nakamura, Hideo; Kukita, Yutaka

Int. Conf. on New Trends in Nulear System Thermohydraulics,Vol. 1, 0, p.77 - 86, 1994/00

no abstracts in English

Journal Articles

Loss of Residual Heat Removal(RHR) event during PWR mid-loop operation; ROSA-IV/LSTF experiment without opening on primary loop pressure boundary

Nakamura, Hideo; Katayama, Jiro; Kukita, Yutaka

Power Plant Transients,1992; FED-Vol. 140, p.9 - 16, 1993/00

no abstracts in English

Journal Articles

RELAP5 code analysis of a ROSA-IV/LSTF experiment simulating a loss of residual heat removal event during PWR mid-loop operation

Nakamura, Hideo; Katayama, Jiro; Kukita, Yutaka

Proc. of the 5th Int. Topical Meeting on Reactor Thermal Hydraulics: NURETH-5,Vol. 5, p.1333 - 1340, 1992/00

no abstracts in English

Journal Articles

Loss of residual heat removal during PWR mid-loop operation; ROSA-IV/LSTF experiment and analysis

Nakamura, Hideo; *; Anoda, Yoshinari; Kukita, Yutaka

1st JSME/ASME Joint Int. Conf. on Nuclear Engineering,Vol. 2, p.209 - 214, 1991/00

no abstracts in English

Journal Articles

Loss of residual heat removal(RHR) during PWR MID-loop operation; Experiments in ROSA-IV/LSTF

Nakamura, Hideo; Anoda, Yoshinari; Kukita, Yutaka

Proc. of the Int. Topical Meeting on Safety of Thermal Reactors, p.497 - 503, 1991/00

no abstracts in English

Journal Articles

Construction of in-core structure test section in HENDEL, (II); Testing devices and their performance test

; ; ; ; ; ; *;

Nippon Genshiryoku Gakkai-Shi, 30(5), p.427 - 433, 1988/05

 Times Cited Count:1 Percentile:79.81(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Development of on emergency-use stack gas monitor

;

Nippon Genshiryoku Gakkai-Shi, 29(7), p.656 - 663, 1987/07

 Times Cited Count:0 Percentile:100(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Sudies on thermal and hydraulic performance of fuel stack of VHTR, Part III; Experimental and analytical results of HENDEL multi-channel test rig with 12 independently heated fuel rods

; ; ; ; ;

Nippon Genshiryoku Gakkai-Shi, 29(2), p.133 - 140, 1987/02

 Times Cited Count:1 Percentile:80.11(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

VHTR Fuel Irradiation Tests by the In-pile Gas Loop,OGL-1 at JMTR

; ; ; ;

JAERI-M 86-068, 17 Pages, 1986/04

JAERI-M-86-068.pdf:0.8MB

no abstracts in English

Journal Articles

Experimental results of the fuel stack test section(Ti), 2nd report; Test resultsof a multi-channel test rig with uniform heating of 12 fuel pins

; ; ; ; ;

Nippon Genshiryoku Gakkai-Shi, 28(6), p.527 - 533, 1986/00

 Times Cited Count:2 Percentile:66.98(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Thermal diffusivity of internal insulation layer of HENDEL hot gas duct

; ; ; ; ; Sanokawa, Konomo

JAERI-M 85-056, 18 Pages, 1985/05

JAERI-M-85-056.pdf:0.43MB

no abstracts in English

JAEA Reports

Test Results of the Hot Gas Ducts of HENDEL

; ; *; ; ; ; Sanokawa, Konomo

JAERI-M 85-008, 20 Pages, 1985/02

JAERI-M-85-008.pdf:0.54MB

no abstracts in English

JAEA Reports

Biennial report of the Department of High Temperature Engineering; April 1,1982-March 31,1984

Sanokawa, Konomo; ; ; ;

JAERI-M 84-190, 177 Pages, 1984/10

JAERI-M-84-190.pdf:4.92MB

no abstracts in English

JAEA Reports

Present Status on Helium Technology of HTGR

;

JAERI-M 84-083, 44 Pages, 1984/05

JAERI-M-84-083.pdf:1.07MB

no abstracts in English

JAEA Reports

Irradiation Test of The 1st and 2nd OGL-1 Fuel Assemblies

Ikawa, Katsuichi; ; ; ; ; Minato, Kazuo; Iwamoto, K.; ; ;

JAERI-M 83-012, 251 Pages, 1983/03

JAERI-M-83-012.pdf:17.56MB

no abstracts in English

33 (Records 1-20 displayed on this page)