CSNI0023: SEMISCALE/S-IB-3, Semiscale MOD-2A, 21.7% Communication Cold Leg Break LOCA Experiment

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CSNI0023 SEMISCALE/S-IB-3. (Abstract last modified 22-MAY-1992)

SEMISCALE/S-IB-3, Semiscale MOD-2A, 21.7% Communication Cold Leg Break LOCA Experiment

Abstract Table of Contents:

OPERATING SYSTEM

OTHER RESTRICTIONS

1. NAME OR DESIGNATION - SEMISCALE/S-IB-3.

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-IB-3 CSNI0023/01 Arrived

Machines used: Package-ID Orig.Computer Test Computer CSNI0023/01 Many Computers

3. DESCRIPTION OF TEST FACILITY - The Semiscale Mod-2A system used for this test was designed as a smallscale model of the primary system of four loop PWR nuclear generating plant. consists of a pressure v internals, including a 25-rod core with electrically powered rods and an external downcomer assembly; an intact loop with pressurizer, steam generator, pump, and rupture disc assembly. It is scaled to simulate the three intact loops in a PWR. The broken loop simulates the single loop in which a break is postulated to occur in a PWR. The system also has emergency core cooling for the intact loop from high- and low-pressure injection pumps, a coolant injection accumulator for the intact loop, and a pressure suppression system with steam supply and pressure suppression tank. Twenty-three rods of the 25-rod core were powered equally with a power density of 26.51 kW/m. The total core power for Test S-IB-3 was 1.45 MW.

4. DESCRIPTION OF TEST - This test was a 21.7%, communicative, cold leg break loss-of-coolant experiment with ECC injection. The test was intended to provide reference data for comparison of Semiscale test results to result from LOBI test B-R1M. The test was also intended to provide reference data for evaluation and assessment of reactor safety code capabilities to predict integral blowdown, refill/reflood experiments for intermediate break sizes, and particularly for providing data to extend the code into the reflood regime. Particular emphasis was placed on providing extensive core fluid and heater rod measurements to facilitate this development.

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 - LOBI test B-R1M.

9. STATUS
CSNI0023/01: 22-MAY-1992 Arrived at NEADB

10. REFERENCES  -
CSNI0023/01:
- 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)
- T.J. Boucher and M.T. Leonard:
  "Quick Look Report for Semiscale Intermediate Break Test S-IB-3"
  EGG-SEMI-6013, August 1982
- K.E. Sackett and L/B/ Clegg:
  "Experiment Data Report for Semiscale MOD-2A Intermediate Break Test Series
(Test S-IB-3)"   NUREG/CR-2738 and EGG-2198, June 1982
- T.J. Boucher:
  "Experiment Operating Specification for Semiscale MOD-2A Experiment S-IB-3"
  EGG-SEMI-5787, February 1982

11. TEST DESIGNATION - S-IB-3

12. PROGRAMMING LANGUAGE(S) USED -
CSNI0023/01:

15. ESTABLISHMENT -
      T.J. Boucher, M.T. Leonard
      Idaho National Engineering Laboratory
      Idaho Falls, Idaho, U.S.A.

16. MATERIAL AVAILABLE -
CSNI0023/01:
Directory          TOTAL: 5,025,120
Current                      45,120
Computed parameters         553,440
Density                     486,080
Force                       180,480
Flows                       240,640
Differential pressure       812,160
Pressure                    315,680
Power                        60,320
Rotational speed             30,080
Temperature               2,256,000
Voltage                      45,120
Valve position               45,600

17. CATEGORIES -

- Y. Integral Experiments Data, Databases, Benchmarks

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

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