last modified: 20-SEP-1989 | catalog | categories | new | search |

CSNI0002 LOFT/LP-LB-1.

LOFT/LP-LB-1, Loss of Fluid Test, Large-Break LOCA Experiment

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1. NAME OR DESIGNATION:  LOFT/LP-LB-1.
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2. COMPUTERS
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Program name Package id Status Status date
LOFT/LP-LB-1 CSNI0002/01 Arrived 20-SEP-1989

Machines used:

Package ID Orig. computer Test computer
CSNI0002/01 Many Computers
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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 LOCE is expected to closely model a LPWR LOCA.
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4. DESCRIPTION OF TEST

Experiment LP-LB-1 was conducted on 3 February 1984 in the Loss-of-Fluid Test (LOFT) facility at the Idaho National Engineering Laboratory under the auspices of the Organization for Economic Cooperation and Development.  The primary objectives of Experiment LP-LB-1 were to determine system transient characteristics and to assess code predictive capabilities for design basis large-break loss-of-coolant accidents in pressurized water reactors (PWRs).  This experiment simulated a double-ended offset shear of one inlet pipe in a four-loop PWR and was initiated from conditions representative of licensing limits in a PWR.  Other boundary conditions for the simulation were loss of offsite power, rapid primary coolant pump coastdown, and United Kingdom minimum safeguard emergency core coolant injection rates.  The nuclear fuel rods were not pressurized.  The transient was initiated by opening the quick-opening blowdown valves in the broken loop hot and cold legs.
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5. EXPERIMENTAL LIMITATIONS OR SHORTCOMINGS

Short core and steam generator, excessive core bypass, other scaling compromises, and lack of adequate measurements in certain areas.
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6. PHENOMENA TESTED

Phase separation, core heat transfer, ECC bypass and penetration, and quench front propagation.
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7. SPECIAL FEATURES OF EXPERIMENT:  Only integral research facility with a nuclear core.
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8. COUNTERPART EXPERIMENTS:  Semiscale
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9. STATUS
Package ID Status date Status
CSNI0002/01 20-SEP-1989 Arrived at NEADB
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10. REFERENCES
CSNI0002/01, included references:
- OECD LOFT Experiment LP-LB-1 Data Results
- James P. Adams and Jonathan C. Birchley:
Quick-Look Report on OECD LOFT Experiment LP-LB-1
OECD LOFT-T-3504 (February 1984)
- 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.
- The OECD/LOFT Project, Achievements and Significant Results
Proceedings of an Open Forum, 9-11 May 1990, Madrid, Spain
printed in 1991
- 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)
- S.M. Modro, S.N. Aksan, V.T. Berta and A.B. Wahba
Review of LOFT Large Break Experiments
Topical Report OECD LOFT-T-3900 (August 1988)
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11. TEST DESIGNATION:  LP-LB-1
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12. PROGRAMMING LANGUAGE(S) USED
No specified programming language
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15. NAME AND ESTABLISHMENT OF AUTHORS

ESTABLISHMENT
        Idaho National Engineering Laboratory
        EG&G Idaho
        Idaho Falls, Idaho 83415
        UNITED STATES
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16. MATERIAL AVAILABLE
CSNI0002/01
CCVM data        mag tapeDirectory     (Total all files: 89.1 MB)   CVMTP
CCVM data        mag tapeControl valves                   4.9 MB    CVMTP
CCVM data        mag tapeComputed parameters              5.5 MB    CVMTP
CCVM data        mag tapeDensities                        2.2 MB    CVMTP
CCVM data        mag tapeFlows                            4.8 MB    CVMTP
CCVM data        mag tapeFrequency (pump)                 0.5 MB    CVMTP
CCVM data        mag tapeLevels                           2.0 MB    CVMTP
CCVM data        mag tapeMomentum flux                    3.8 MB    CVMTP
CCVM data        mag tapeNeutron detector                 0.7 MB    CVMTP
CCVM data        mag tapeDifferential pressure            5.2 MB    CVMTP
CCVM data        mag tapePressures                        7.2 MB    CVMTP
CCVM data        mag tapePower                            0.1 MB    CVMTP
CCVM data        mag tapeNIS power range                  0.1 MB    CVMTP
CCVM data        mag tapeROD position                     0.9 MB    CVMTP
CCVM data        mag tapeRotational speed                 0.5 MB    CVMTP
CCVM data        mag tapeTemperatures                    50.7 MB    CVMTP
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17. CATEGORIES
  • Y. Integral Experiments Data, Databases, Benchmarks

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