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JAEA Reports

Data report of ROSA/LSTF experiment SB-SL-01; Main steam line break accident

Takeda, Takeshi

JAEA-Data/Code 2020-019, 58 Pages, 2021/01

JAEA-Data-Code-2020-019.pdf:3.85MB

An experiment denoted as SB-SL-01 was conducted on March 27, 1990 using the Large Scale Test Facility (LSTF) in the Rig of Safety Assessment-IV (ROSA-IV) Program. The ROSA/LSTF experiment SB-SL-01 simulated a main steam line break (MSLB) accident in a pressurized water reactor (PWR). The test assumptions were made such as auxiliary feedwater (AFW) injection into secondary-side of both steam generators (SGs) and coolant injection from high pressure injection (HPI) system of emergency core cooling system into cold legs in both loops. The MSLB led to a fast depressurization of broken SG, which caused a decrease in the broken SG secondary-side wide-range liquid level. The broken SG secondary-side wide-range liquid level recovered because of the AFW injection into the broken SG secondary-side. The primary pressure temporarily decreased a little just after the MSLB, and increased up to 16.1 MPa following the closure of the SG main steam isolation valves. Coolant was manually injected from the HPI system into cold legs in both loops a few minutes after the primary pressure reduced to below 10 MPa. The primary pressure raised due to the HPI coolant injection, but was kept at less than 16.2 MPa by fully opening a power-operated relief valve of pressurizer. The core was filled with subcooled liquid through the experiment. Thermal stratification was seen in intact loop cold leg during the HPI coolant injection owing to the flow stagnation. On the other hand, significant natural circulation prevailed in broken loop. When the continuous core cooling was ensured by the successive coolant injection from the HPI system, the experiment was terminated. The experimental data obtained would be useful to consider recovery actions and procedures in the multiple fault accident with the MSLB of PWR. This report summarizes the test procedures, conditions, and major observations in the ROSA/LSTF experiment SB-SL-01.

Journal Articles

Design and performance analysis of the ITER cryoplant and cryo-distribution subsystem

Guillemet, L.*; Jager, B.*; Haange, R.*; Hamada, Kazuya; Hara, Eiji*; Kalinin, G.*; Kato, Takashi; Millet, F.*; Shatil, N.*

Proceedings of 19th International Cryogenic Engineering Conference (ICEC-19), p.105 - 108, 2002/07

Japan Atomic Energy Research Institute has designed a ITER cryoplant and cryo-distribution in the international collaboration. The ITER cryoplant that will be the largest cryogenic system for the Fusion facility in the world, is designed to be stable in operation despite the pulsed nature of heat deposition in the magnet system. The refrigeration capacity of cryoplant is 48 kW at 4.5 K of refrigeration power and 0.16 kg/s of supercritical helium supply. In the cryoplant, a supercritical helium pump and a cold compressor is applied, based on the successful achievement of cryogenic system for the ITER central solenoid model coil.

JAEA Reports

ROSA/LSTF experiment report for RUN SB-CL-24; Repeated core heatup phenomena during 0.5% cold leg break

Suzuki, Mitsuhiro; Anoda, Yoshinari

JAERI-Tech 2000-016, p.173 - 0, 2000/03

JAERI-Tech-2000-016.pdf:7.25MB

no abstracts in English

JAEA Reports

Fabrication of sintered Li$$_{2}$$O thin wall tube specimens for irradiation in BEATRIX-II, phase 2

; Watanabe, H.

JAERI-M 91-082, 41 Pages, 1991/05

JAERI-M-91-082.pdf:3.42MB

no abstracts in English

JAEA Reports

Preparatio of uranium carbide pellets

; ; Abe, Jiro; ; ;

JAERI-M 7601, 36 Pages, 1978/03

JAERI-M-7601.pdf:1.95MB

no abstracts in English

JAEA Reports

An Experimental Study on Performance of Upper Head Injection System by the ROSA-II

*; *; *; *; *; *

JAERI-M 6707, 169 Pages, 1976/09

JAERI-M-6707.pdf:4.2MB

no abstracts in English

Journal Articles

Production of airtight and inner-pressure-resistine aluminium capsules cold-welded for reactor irradiation

; ; Masaki, N.;

Nihon Genshiryoku Gakkai-Shi, 16(5), p.276 - 281, 1974/05

no abstracts in English

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