CSNI0024: SEMISCALE/S-PL-3E-LV, Scaled Reference 4-Loop PWR Experiment, Loss of Offsite Power Simulation

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CSNI0024 SEMISCALE/S-PL-3E-LV (Abstract last modified 22-MAY-1992)

SEMISCALE/S-PL-3E-LV, Scaled Reference 4-Loop PWR Experiment, Loss of Offsite Power Simulation

Abstract Table of Contents:

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

2. COMPUTER FOR WHICH PROGRAM IS DESIGNED AND OTHER MACHINE VERSION PACKAGES AVAILABLE -

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Explanation of the status codes.

Program-name Package-ID Status SEMISCALE/S-PL-3E-LV CSNI0024/01 Arrived

Machines used: Package-ID Orig.Computer Test Computer CSNI0024/01 Many Computers

3. DESCRIPTION OF TEST FACILITY - The Semiscale Mod-3B system is scaled to a reference four-loop PWR. The scaling criterion is a modified volume scaling based on the ratio of Semiscale power to the thermal power of the reference plant (Trojan). This scaling produces a scale factor of 1/1705.5. The system consists of a pressure vessel with an electrically-heated, 25-rod PWR core simulator and internals, an external pipe downcomer, and two primary coolant loops. Each loop has an active tube and shell steam generator. The intact loop is scaled to represent three of the four primary loops in a PWR, while the broken loop represents the fourth. Even though S-PL-3 does not incorporate a break, this loop is referred to as the "broken loop". In order to correctly scale the facility and preserve important phenomena, component elevations, dynamic pressure heads, and liquid distributions are maintained as close to the reference PWR values as possible.

4. DESCRIPTION OF TEST - The S-PL-3 experiment simulates a loss of offsite power with accompanying failure of the auxiliary feedwater and emergency AC power systems. When primary system pressure reached the safety-relief-valve setpoint, emergency power was assumed to be restored and recovery was initiated by latching open the power-operated relief valve (PORV) and initiating emergency core coolant (ECC) flow to begin the primary feed and bleed recovery.

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
CSNI0024/01: 22-MAY-1992 Arrived at NEADB

10. REFERENCES  -
- James R. Wolf, John E. Streit
  "The Semiscale Power Loss Experiment S-PL-3 with Primary Feed
  and Bleed Plant Recovery"
  EGG-M-07384
CSNI0024/01:
- Kenneth E. Sacket and L. Bruce Clegg:
  Experiment Data Report for Semiscale MOD-2B Power Loss Test Series
  (Tests S-PL-1, -2, and -3)   NUREG/CR-3419 and EGG-2269, August 1983
- 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)
- J.R. Wolf, J.E, Streit, J.C. Chapman:
  Analysis of the Semiscale MOD-2B Power Loss Experiment S-PL-3
  EGG-SEMI-6429 October 1983
- 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)

11. TEST DESIGNATION - S-PL-3E (Long Version)

12. PROGRAMMING LANGUAGE(S) USED -
CSNI0024/01:

15. ESTABLISHMENT -
Idaho National Engineering Laboratory
Idaho Falls, Idaho, U. S. A.

16. MATERIAL AVAILABLE -
CSNI0024/01:
               (TOTAL: 4,565,120)
Current                  122,880
Computed parameters       30,720
Force                     46,080
Flows                    371,840
Differential pressure    844,800
Pressure                 291,840
Power                    138,240
Rotational speed          30,720
Temperature            2,565,120
Voltage                  122,880

17. CATEGORIES -

- Y. Integral Experiments Data, Databases, Benchmarks

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