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Motion-picture graphic display processor for ROSA-IV/LSTF experimental data

Technical Report:

Abstract

The ROSA-IV program is conducting integral experiments for investigation of thermal-hydraulic responses of a pressurized water reactor (PWR) during small-break loss-of-coolant accidents (SBLOCA) and operational transients using the Large Scale Test Facility (LSTF) which is a 1/48 volumetrical scaled, full-height, full-pressure simulator of a westinghouse-type 4-loop PWR. During a LOCA, the reactor coolant system, may become steam-water two-phase flow conditions with a predominant influence of gravity on the spatial distribution of reactor coolant. The LSTF experiments simulate such two-phase flow behavior and measure thermal-hydraulic responses by using more than 2300 transducers. A motion-picture graphic display processor has been developed to allow efficient interpretation of the measured data. The processor generates a color motion picture from both experimental and RELAP5-calculational results to be used for the presentation of the system transient responses. (author).
Authors:
Anoda, Yoshinari; [1]  Suzuki, Masayuki; Hiyama, Kazuo; Sasaki, Shigeru; Kawasaki, Kazuyo; Shimane, Yukio
  1. Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment
Publication Date:
Sep 01, 1991
Product Type:
Technical Report
Report Number:
JAERI-M-91-151
Reference Number:
SCA: 220900; 210200; 990200; PA: JPN-91:012171; SN: 92000659205
Resource Relation:
Other Information: PBD: Sep 1991
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; 99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE; PWR TYPE REACTORS; LOSS OF COOLANT; COMPUTER-GRAPHICS DEVICES; TRANSIENTS; TWO-PHASE FLOW; IMAGE PROCESSING; R CODES; MANUALS; THERMODYNAMICS; HYDRAULICS; COMPUTER PROGRAM DOCUMENTATION; 220900; 210200; 990200; REACTOR SAFETY; POWER REACTORS, NONBREEDING, LIGHT-WATER MODERATED, NONBOILING WATER COOLED; MATHEMATICS AND COMPUTERS
OSTI ID:
10117048
Research Organizations:
Japan Atomic Energy Research Inst., Tokyo (Japan)
Country of Origin:
Japan
Language:
Japanese
Other Identifying Numbers:
Other: ON: DE92768093; TRN: JP9112171
Availability:
OSTI; NTIS (US Sales Only); INIS
Submitting Site:
JPN
Size:
56 p.
Announcement Date:
Jun 30, 2005

Technical Report:

Citation Formats

Anoda, Yoshinari, Suzuki, Masayuki, Hiyama, Kazuo, Sasaki, Shigeru, Kawasaki, Kazuyo, and Shimane, Yukio. Motion-picture graphic display processor for ROSA-IV/LSTF experimental data. Japan: N. p., 1991. Web.
Anoda, Yoshinari, Suzuki, Masayuki, Hiyama, Kazuo, Sasaki, Shigeru, Kawasaki, Kazuyo, & Shimane, Yukio. Motion-picture graphic display processor for ROSA-IV/LSTF experimental data. Japan.
Anoda, Yoshinari, Suzuki, Masayuki, Hiyama, Kazuo, Sasaki, Shigeru, Kawasaki, Kazuyo, and Shimane, Yukio. 1991. "Motion-picture graphic display processor for ROSA-IV/LSTF experimental data." Japan.
@misc{etde_10117048,
title = {Motion-picture graphic display processor for ROSA-IV/LSTF experimental data}
author = {Anoda, Yoshinari, Suzuki, Masayuki, Hiyama, Kazuo, Sasaki, Shigeru, Kawasaki, Kazuyo, and Shimane, Yukio}
abstractNote = {The ROSA-IV program is conducting integral experiments for investigation of thermal-hydraulic responses of a pressurized water reactor (PWR) during small-break loss-of-coolant accidents (SBLOCA) and operational transients using the Large Scale Test Facility (LSTF) which is a 1/48 volumetrical scaled, full-height, full-pressure simulator of a westinghouse-type 4-loop PWR. During a LOCA, the reactor coolant system, may become steam-water two-phase flow conditions with a predominant influence of gravity on the spatial distribution of reactor coolant. The LSTF experiments simulate such two-phase flow behavior and measure thermal-hydraulic responses by using more than 2300 transducers. A motion-picture graphic display processor has been developed to allow efficient interpretation of the measured data. The processor generates a color motion picture from both experimental and RELAP5-calculational results to be used for the presentation of the system transient responses. (author).}
place = {Japan}
year = {1991}
month = {Sep}
}