CSNI0028 SEMISCALE/S-06-3(SV)

1. NAME OR DESIGNATION:  SEMISCALE/S-06-3(SV).

3. DESCRIPTION OF TEST FACILITY

The Semiscale Mod-1 system used for this test consisted of a pressure vessel with internals, including a 40-rod core with 36 electrically heated rods; an intact loop with steam generator, pump, and pressurizer; a broken loop with simulated steam generator, simulated pump, simulated reflood bypass lines, LOFT counterpart nozzles, and two rupture assemblies; a coolant injection accumulator for the intact loop; high and low pressure suppression tank, header, and heated steam supply system.

4. DESCRIPTION OF TEST

Test S-06-2 was conducted to investigate the thermal and hydraulic phenomena accompanying a hypothesized loss-of- coolant accident in a pressurized water reactor (PWR) system. Initial conditions were 15513 kPa and 563K to investigate the response of the Semiscale Mod-1 system to a depressurization and reflood transient following a simulated double-ended offset shear of the broken loop cold leg piping. During the test, cooling water was injected into the cold leg of the intact loop to simulate emergency core coolant injection in a PWR. The heater rods in the electrically heated core were operated at an axial peak power density which was 50% of the maximum peak power density (52.5 kW/m).

5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM: EXPERIMENTAL LIMITATIONS OR SHORTCOMINGS

6. PHENOMENA TESTED

Natural circulation in 1- and 2-phase flow; core thermohydraulics; 1- and 2-phase pump behaviour.

7. UNUSUAL FEATURES: SPECIAL FEATURES OF EXPERIMENT

8. RELATED OR AUXILIARY PROGRAMS: COUNTERPART EXPERIMENTS

- 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)
- Morris L. Patton, Jr., Brent L. Collins, Kenneth E. Sackett:
  "Experiment Data Report for Semiscale Mod-1 Test S-06-2
   (LOFT Counterpart Test)", TREE-NUREG-1122 (August 1977)
- Robert L. Gillins, Kenneth E. Sackett, Cheryl E. Coppin
  "Experiment Data Report for Semiscale Mod-1 Test S-06-4
   (LOFT Counterpart Test)", TREE-NUREG-1124 (December 1977)

11. TEST DESIGNATION:  S-06-3(Short Version)

15. ESTABLISHMENT

U.S. Nuclear Regulatory Commission
and
Department of Energy
Idaho Operations Office

CCVM data        mag tape              (TOTAL:  5,133,600 bytes)    CVMTP
CCVM data        mag tapeCurrent                   29,760           CVMTP
CCVM data        mag tapeControl valve             14,880           CVMTP
CCVM data        mag tapeComputed parameters    1,740,960           CVMTP
CCVM data        mag tapeDensity                  342,240           CVMTP
CCVM data        mag tapeFlows                    372,000           CVMTP
CCVM data        mag tapeDifferential pressure    595,200           CVMTP
CCVM data        mag tapePressure                 223,200           CVMTP
CCVM data        mag tapePower                     29,760           CVMTP
CCVM data        mag tapeRotational speed          14,880           CVMTP
CCVM data        mag tapeTemperature            1,755,840           CVMTP
CCVM data        mag tapeVoltage                   14,880           CVMTP