CSNI0012: LOFT/LP-FP-1B, Loss of Fluid Test, Fission Product Release Experiment

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CSNI0012 LOFT/LP-FP-1B. (Abstract last modified 20-SEP-1989)

LOFT/LP-FP-1B, Loss of Fluid Test, Fission Product Release Experiment

Abstract Table of Contents:

OPERATING SYSTEM

OTHER RESTRICTIONS

1. NAME OR DESIGNATION - LOFT/LP-FP-1B.

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/LP-FP-1B CSNI0012/01 Arrived

Machines used: Package-ID Orig.Computer Test Computer CSNI0012/01 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 - The seventh OECD LOFT experiment was conducted on 19 December 1984. It was the first of the two experiments to be performed in the LOFT facility with intentional release of fission products. Its objectives were to obtain data on fission product release from the fuel-cladding gap into vapor and reflood water and to collect data on transport of these fission products through and out of the reactor coolant system. The experiment was initiated by a reactor scram with one second delayed opening of the quick-opening blowdown valves.

5. EXPERIMENTAL LIMITATIONS OR SHORTCOMINGS - Short core and steam generator, excessive core bypass, other scaling compromises, and lack of adequate measurements in certain areas.

6. PHENOMENA TESTED - Phase separation, core heat transfer, ECC bypass and penetration, and quench front propagation.

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

8. COUNTERPART EXPERIMENTS - Semiscale.

9. STATUS
CSNI0012/01: 20-SEP-1989 Arrived at NEADB

10. REFERENCES -
CSNI0012/01:
- OECD Loft Experiment LP-FP-1 Data results
- The OECD/LOFT Project, Achievements and Significant Results
Proceedings of an Open Forum, 9-11 May 1990, Madrid, Spain
printed in 1991
- 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.
- 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)
- 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)
- E.W. Coryell:
OECD LOFT Fission Product Experiment LP-FP-1
Fission Product Data Report and Appendices (Volumes 1 and 2) OECD LOFT-T-3708
Revision 1
- J.M. Broughton:
Errata Summary for LP-FP-1
Fission Product Data Report JMB-48-87, June 22, 1988
- J.P. Adams et al.:
Quick-Look Report on OECD LOFT Experiment LP-FP-1 (OECD LOFT-T-3704, March 1985)
- A.B. Wahba:
Thermal Hydraulic EASR of OECD LOFT LP-FP-1 Volume 1 (OECD-LOFT-T-3709 V1 Rev.
November 1986)

11. TEST DESIGNATION - LP-FP-1B

12. PROGRAMMING LANGUAGE(S) USED -
CSNI0012/01:

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

16. MATERIAL AVAILABLE -
CSNI0012/01:
Directory              (Total: 92.5 MB)
Control valves                 15.5 MB
Computed parameters            15.5 MB
Densities                       8.1 MB
Flows                          10.8 MB
Gross gamma measurements        1.8 MB
Levels                          5.4 MB
Momentum flux                   5.4 MB
Neutron detector                1.8 MB
Differential pressure           6.6 MB
Pressure                       15.0 MB
Power                           1.2 MB
NIS power range                 1.8 MB
ROD position                    2.4 MB
Rotational speed                1.2 MB
Directory              (Total: 98.8 MB)
Temperatures                   98.8 MB
Directory (long vers.) (Total: 24.0 MB)
Computed parameters            0.8 MB
Levels                         1.1 MB
Differential pressure          0.5 MB
Pressure                       1.3 MB
Temperature                   20.3 MB

17. CATEGORIES -

- Y. Integral Experiments Data, Databases, Benchmarks

Keywords: DATA, FISSION GAS RELEASE, LOSS-OF-COOLANT ACCIDENT, TRANSIENTS

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