CSNI0021: LOFT/L3-, Loss of Fluid Test, 7th NRC L3 Small Break LOCA Experiment

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CSNI0021 LOFT/L3-7. (Abstract last modified 25-MAY-1992)

LOFT/L3-, Loss of Fluid Test, 7th NRC L3 Small Break LOCA Experiment

Abstract Table of Contents:

OPERATING SYSTEM

OTHER RESTRICTIONS

1. NAME OR DESIGNATION - LOFT/L3-7.

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 LOFT/L3-7 CSNI0021/01 Arrived

Machines used: Package-ID Orig.Computer Test Computer CSNI0021/01 Many Computers

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 seventh in the NRC L3 Series of small-break LOCA experiments. A 2.5-cm (10-in.) cold-leg noncommunicative-break LOCA was simulated. The experiment was conducted on 20 June 1980.

5. 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. COUNTERPART EXPERIMENTS -

9. STATUS
CSNI0021/01: 25-MAY-1992 Arrived at NEADB

10. REFERENCES -
CSNI0021/01:
- D.L. Gillas and J.M. Carpenter:
Experiment Data Report for LOFT Nuclear Small Break
Experiment L3-7
NUREG/CR-1570 - EGG-2049 (August 1980)
- 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 - L3-7

12. PROGRAMMING LANGUAGE(S) USED -
CSNI0021/01:

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

16. MATERIAL AVAILABLE -
CSNI0021/01:
Directory        TOTAL: 106,521,600
Control valve             2,856,800
Computed parameters      19,819,600
Density                  12,444,000
Flow velocity             2,857,120
Mass flow               11,427,200        C
Levels                    8,570,400
Momentum flux             5,713,600
Neutron detector          5,713,600
Differential pressure    22,847,040
Power                     4,285,200
Rotational speed          9,987,040
Directory        TOTAL: 107,142,000
Temperature part 1      107,142,000
Directory        TOTAL: 115,704,640
Temperature part 2       75,709,440
ressure                  39,995,200

17. CATEGORIES -

- Y. Integral Experiments Data, Databases, Benchmarks

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

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