CSNI0019 LOFT/L9-3.

1. NAME OR DESIGNATION:  LOFT/L9-3.

3. DESCRIPTION OF TEST FACILITY

The LOFT Integral Test Facility is a scale model of a LPWR.  The intent of the facility is to model the nuclear, thermal-hydraulic phenomena which would take place in a LPWR during a LOCA.  The general philosophy in scaling coolant volumes and flow areas in LOFT was to use the ratio of the LOFT core [50 MW(t)] to a typical LPWR core [3000 MW(t)].  For some components, this factor is not applied; however, it is used as extensively as practical.  In general, components used in LOFT are similar in design to those of a LPWR.  Because of scaling and component design, the LOFT LOCA is expected to closely model a LPWR LOCA.

4. DESCRIPTION OF TEST

This was the third of the NRC L9 series of experiments on Anticipated Transients with Multiple Failures. Loss-of-feedwater effects were studied. The experiment was conducted on 7 April 1982.

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

6. PHENOMENA TESTED

Phase separation; ECC bypass and penetration; core heat transfer; quench front propagation.

7. SPECIAL FEATURES OF EXPERIMENT:  Only integral research facility with a nuclear core.

8. RELATED OR AUXILIARY PROGRAMS: COUNTERPART EXPERIMENTS

- P.D. Bayless and J.M. Divine
Experiment Data Report for LOFT Anticipated Transient
Without Scram Experiment L9-3
NUREG/CR-2717 - EGG-2195 (May 1982)
- Charles L. Nalezny:
Summary of Nuclear Regulatory Commission's
LOFT Program Experiments
NUREG/CR-3214 - EGG-2248 (July 1983)
- Charles L. Nalezny:
Summary of Nuclear Regulatory Commission's
LOFT Program Research Findings
NUREG/CR-3005 - EGG-2231 (April 1985)
- D.L. Reeder:
LOFT System and Test Description
NUREG/CR-0247 (TREE-1208) July 1978.
- J. Fell and S.M. Modro:
An Account of the OECD LOFT Project
OECD LOFT-T-3907 May 1990.
- Technical Considerations for LOFT Consortium Test Plan,
Prepared for discussion by LOFT Consortium Working Group Meeting
Munich, Germany, July 15-16, 1982 (SEN/LOFT(82)6)

11. TEST DESIGNATION:  L9-3

15. ESTABLISHMENT

        Idaho National Engineering Laboratory
        EG&G Idaho
        Idaho Falls, Idaho 83415.
        U.S.A.

CCVM data        mag tapeDirectory     TOTAL: 71,111,680            CVMTP
CCVM data        mag tapeCurrent                 361,280            CVMTP
CCVM data        mag tapeControl valve           542,080            CVMTP
CCVM data        mag tapeComputed parameters   4,125,680            CVMTP
CCVM data        mag tapeDensity                 181,440            CVMTP
CCVM data        mag tapeFlow velocity         2,253,680            CVMTP
CCVM data        mag tapeFrequency               361,280            CVMTP
CCVM data        mag tapeMass flow             1,807,680            CVMTP
CCVM data        mag tapeLevels                1,083,840            CVMTP
CCVM data        mag tapeMomentum flux           191,120            CVMTP
CCVM data        mag tapeNeutron detector        542,240            CVMTP
CCVM data        mag tapeDifferential pressure 2,899,840            CVMTP
CCVM data        mag tapePressure              4,021,360            CVMTP
CCVM data        mag tapeNIS-power range         723,040            CVMTP
CCVM data        mag tapeRod position          1,445,120            CVMTP
CCVM data        mag tapeRotational speed        361,600            CVMTP
CCVM data        mag tapeTemperature          50,210,400            CVMTP