Integral Experiments Data, Databases, Benchmarks and Safety Joint Projects
CSNI0025 SEMISCALE/S-PL-3E-SV
last modified: 22-MAY-1992 | catalog | new | search |

CSNI0025 SEMISCALE/S-PL-3E-SV

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

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1. NAME OR DESIGNATION:  SEMISCALE/S-PL-3E(SV).
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2. COMPUTERS

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Program name Package id Status Status date
SEMISCALE/S-PL-3E-SV CSNI0025/01 Arrived 22-MAY-1992

Machines used:

Package ID Orig. computer Test computer
CSNI0025/01 Many Computers
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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.
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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.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM: EXPERIMENTAL LIMITATIONS OR SHORTCOMINGS
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6. PHENOMENA TESTED

Natural circulation in 1- and 2-phase flow; core thermohydraulics; 1- and 2-phase pump behaviour.
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7. UNUSUAL FEATURES: SPECIAL FEATURES OF EXPERIMENT
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8. RELATED OR AUXILIARY PROGRAMS: COUNTERPART EXPERIMENTS
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9. STATUS
Package ID Status date Status
CSNI0025/01 22-MAY-1992 Arrived at NEADB
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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
CSNI0025/01, included references:
- 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)
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11. TEST DESIGNATION:  S-PL-3E (Short Version)
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12. PROGRAMMING LANGUAGE(S) USED
No specified programming language
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15. ESTABLISHMENT

Idaho National Engineering Laboratory
Idaho Falls, Idaho, U. S. A.
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16. MATERIAL AVAILABLE
CSNI0025/01
CCVM data        mag tape                 (TOTAL:  4,454,400 bytes  CVMTP
CCVM data        mag tapeCurrent                     122,880        CVMTP
CCVM data        mag tapeComputed parameters          30,720        CVMTP
CCVM data        mag tapeForce                        46,080        CVMTP
CCVM data        mag tapeFlows                       261,120        CVMTP
CCVM data        mag tapeDifferential pressure       844,800        CVMTP
CCVM data        mag tapePressure                    291,840        CVMTP
CCVM data        mag tapePower                       138,240        CVMTP
CCVM data        mag tapeRotational speed             30,720        CVMTP
CCVM data        mag tapeTemperature               2,565,120        CVMTP
CCVM data        mag tapeVoltage                     122,880        CVMTP
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17. CATEGORIES
  • Y. Integral Experiments Data, Databases, Benchmarks

Keywords: data, loss-of-coolant accident, transients.