CSNI0026 SEMISCALE/S-UT-1. (Abstract last modified 22-MAY-1992)
1.
NAME OR DESIGNATION - SEMISCALE/S-UT-1. 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
CSNI0026/01 Many Computers
3.
DESCRIPTION OF TEST FACILITY - The Semiscale Mod-2A system for this test consists of a pressure vessel with simulated reactor internals, including a 256-rod core with electrically powered rods and an external downcomer assembly; an intact loop with pressurizer, steam generator, and pump; and a broken loop with a steam generator, pump, and rupture assembly. The system also has emergency core coolant (ECC) from high- and low-pressure injection pumps for each loop; a coolant injection accumulator for the intact loop and a pressure suppression system with header, suppression tank, and steam supply system. 4.
DESCRIPTION OF TEST - This test simulates a loss-of-coolant accident resulting from a 10% communicative break in the cold leg of a pressurized water reactor. The break size for this test was 0.228 sq.cm. which is volumetrically scaled to represent a 10% pipe break in a PWR. The Mod-2A system was configured to simulate a PWR with the capability to inject emergency core coolant (ECC) into the vessel upper head. However, for this test, no upper head ECC injection was used. The intact loop accumulator pressure was set at 2.76 MPa as is specified for upper head injection (UHI) plants. 5.
EXPERIMENTAL LIMITATIONS OR SHORTCOMINGS - 6.
PHENOMENA TESTED - Natural circulation in 1- and 2-phase flow; core thermohydraulics; 1- and 2-phase pump behaviour. 7.
SPECIAL FEATURES OF EXPERIMENT - 8.
COUNTERPART EXPERIMENTS - 9.
STATUS 10.
REFERENCES - 11.
TEST DESIGNATION - S-UT-1 12.
PROGRAMMING LANGUAGE(S) USED - 15.
ESTABLISHMENT - 16.
MATERIAL AVAILABLE - 17.
CATEGORIES - Keywords: DATA, LOSS-OF-COOLANT ACCIDENT, TRANSIENTS
Program-name Package-ID Status
SEMISCALE/S-UT-1 CSNI0026/01 Arrived
CSNI0026/01: 22-MAY-1992 Arrived at NEADB
- Kenneth E. Sackett, L. Bruce Clegg
"Experiment Data Report for Semiscale MOD-2A Small Break Test Series (Tests S-UT-1 and S-UT-2)"
NUREG/CR-2176 and EGG-2108, July 1981
CSNI0026/01:
- 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)
- J.E. Blakeley, R.G. Hanson, D.J. Shimeck:
"Quick Look Report for Semiscale Mod-2A Test S-UT-1"
EGG-SEMI-5331, January 1981
- M.T. Leonard:
"Posttest RELAP5 Simulation of the Semiscale S-UT Series Experiments"
EGG-SEMI-5622, October 1981
CSNI0026/01:
Idaho National Engineering Laboratory
Idaho Falls, Idaho, U.S.A.
CSNI0026/01:
(TOTAL: 4,264,000 bytes)
Current 45,120
Computed parameters 285,760
Density 334,080
Force 152,000
Flows 273,600
Differential pressure 887,360
Pressure 225,600
Power 60,160
Rotational speed 30,080
Temperature 1,910,080
Voltage 60,160
- Y. Integral Experiments Data, Databases, Benchmarks
Home - About Us - Work Areas - Data Bank - Publications - Press Room - List of acronyms - Search