CSNI0027: SEMISCALE/S-06-3(LV), Thermal and Hydraulic Phenomena with LOCA in U-Tube PWR

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CSNI0027 SEMISCALE/S-06-3(LV) (Abstract last modified 22-MAY-1992)

SEMISCALE/S-06-3(LV), Thermal and Hydraulic Phenomena with LOCA in U-Tube PWR

Abstract Table of Contents:

OPERATING SYSTEM

OTHER RESTRICTIONS

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

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.

Program-name Package-ID Status SEMISCALE/S-06-3(LV) CSNI0027/01 Arrived

Machines used: Package-ID Orig.Computer Test Computer CSNI0027/01 Many Computers

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. EXPERIMENTAL LIMITATIONS OR SHORTCOMINGS -

6. PHENOMENA TESTED - Natural circulation in 1- and 2-phase flow; core hermohydraulics; 1- and 2-phase pump behaviour.

7. SPECIAL FEATURES OF EXPERIMENT -

8. COUNTERPART EXPERIMENTS - LOFT Test Series 6.

9. STATUS
CSNI0027/01: 22-MAY-1992 Arrived at NEADB

10. REFERENCES  -
CSNI0027/01:
- 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)
- 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(Long Version)

12. PROGRAMMING LANGUAGE(S) USED -
CSNI0027/01:

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

16. MATERIAL AVAILABLE -
CSNI0027/01:
              (TOTAL:   5,133,600 bytes)
Current                    29,760
Control valve              14,880
Computed parameters     1,740,960
Density                   342,240
Flows                     372,000
Differential pressure     595,200
Pressure                  223,200
Power                      29,760
Rotational speed           14,880
Temperature             1,755,840
Voltage                    14,880

17. CATEGORIES -

- Y. Integral Experiments Data, Databases, Benchmarks

Keywords: DATA, LOSS-OF-COOLANT ACCIDENT, TRANSIENTS

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