CSNI0077 SEMISCALE/TEST1011. (Abstract last modified 10-JAN-1975)
1.
NAME OR DESIGNATION - SEMISCALE/TEST1011. 2.
COMPUTER FOR WHICH PROGRAM IS DESIGNED AND OTHER MACHINE VERSION PACKAGES AVAILABLE -
To request or retrieve programs click on the one of the active versions below.
A password and special authorization is required. Explanation of the status codes.
Machines used:
Package-ID Orig.Computer Test Computer
CSNI0077/01 Many Computers
3.
DESCRIPTION OF TEST FACILITY - The system consisted of a pressure vessel with simulated reactor internals, an intact loop with a steam generator, pump, and pressurizer, a blowdown loop with rupture assemblies, a simulated steam generator, and a simulated pump and a pressure suppression system with a suppression tank and header. The semiscale apparatus was designed to simulate a 100% double-ended offset shear of the cold leg of a pressurized water reactor to investigate the system response to a Loss of Coolant Accident (LOCA). The break areas in Test lOll were reduced by 20% so that the system behavior would be significantly different from the previous semiscale tests. 4.
DESCRIPTION OF TEST - 6.
PHENOMENA TESTED - Simulation of a Loss of Coolant Accident (LOCA) by the Semiscale Test Facility starting from isothermal conditions of the primary coolant loop. 9.
STATUS 10.
REFERENCES - 11.
TEST DESIGNATION - 1011. 12.
PROGRAMMING LANGUAGE -CSNI0077/01: 15.
ESTABLISHMENT - 16.
MATERIAL AVAILABLE -CSNI0077/01: 17.
CATEGORIES - Keywords: DATA, ISOTHERMAL, LOSS-OF-COOLANT ACCIDENT, PRIMARY COOLANT LOOP
Program-name Package-ID Status
SEMISCALE/TEST1011 CSNI0077/01 Report
Facility:
- 1 1/2 Loop Semiscale System consisted of a pressure vessel with internals, including 9 electrically heated fuel rod simulators;
- 1 intact loop with steam generator, simulated pump and bypass line
- 1 broken loop simulator
- emergency core cooling injection system
Scaling Information:
- volume to break area equal to volume to break area of a large PWR
- other parameters not scaled, facility should only yield data for comparison to analyses
Parameters offered for Comparison:
- 2 pressures ( upper plenum and upstream break nozzle) ; containment pressure
- 4 differential pressures (hot leg-cold leg, across pump, pressure vessel containment)
- 6 local fluid densities
- 7 flow rates and including break flow
- liquid level
- time to start high pressure injection system (HPIS) and low pressure injection system (LPIS)
CSNI0077/01: 10-JAN-1975 Report Only
CSNI0077/01:
- D.J. Barnum:
Comparative Analyses of Standard Problems - Standard Problem 2
Semiscale Test 1011 (Interim report I-296-75-1 1975)
- G.G. Loomis:
Summary Report Semiscale Mod-2A Heat Loss Characterization Test Series
EGG-SEMI-5448 (May 1981)
- E.M. Feldman and D.J. Olson:
Semiscale Mod-1 Program and System Description for the Blowdown
Heat Transfer Tests (ANCR-1230, August 1975)
- R.T. French:
An Evaluation of Piping Heat Transfer Piping Flow Regimes,
and Steam Generator Heat Transfer for the Semiscale Mod-1
Isothermal Tests (ANCR-1229, August 1975)
- M.T. Leonard:
RELAP5 Standard Model Description for the Semiscale Mod-2A System
EGG-SEMI-5692 (December 1981)
- D.W. Golden:
Steady State Control Model for the Standard RELAP5 Semiscale
Mod-2A System Model
RE-A-82-023 (April 1982)
- G.G. Loomis:
Summary of the Semiscale Program (1965-1986)
NUREG/CR-4945 - EGG-2509 (July 1987)
- John S. Martinelli:
"Semiscale Loss-of-Power Test Results"
11th Water Reactor Safety Research Information Meeting,
October 24-28, 1983
ECC-M-22283 Preprint
- L.J. Ball et al.:
Semiscale Program Description (TREE-NUREG-1210, May 1987)
Aerojet Nuclear Company
Idaho National Engineering Laboratory
Idaho Falls, Idaho 83401
U.S.A.
Interim report I-296-75-1
- Y. Integral Experiments Data, Databases, Benchmarks
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