CSNI0007 LOFT/LP-FW-1. (Abstract last modified 20-SEP-1989)
1.
NAME OR DESIGNATION - LOFT/LP-FW-1. 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.
Machines used:
Package-ID Orig.Computer Test Computer
CSNI0007/01 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 first OECD LOFT experiment was conducted on February 20, 1983. It was designed to evaluate the generic PWR system response during a complete loss-of-feedwater transient. The objective of the experiment was to investigate the performance of primary "feed and bleed" using a "bleed" from the PORV and "feed" from the HPIS to provide decay heat removal and system pressure reduction while maintaining the primary coolant inventory. 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 10.
REFERENCES - 11.
TEST DESIGNATION - LP-FW-1 12.
PROGRAMMING LANGUAGE(S) USED - 15.
ESTABLISHMENT - 16.
MATERIAL AVAILABLE - 17.
CATEGORIES - Keywords: DATA, LOSS-OF-COOLANT ACCIDENT, TRANSIENTS
Program-name Package-ID Status
LOFT/LP-FW-1 CSNI0007/01 Arrived
CSNI0007/01: 20-SEP-1989 Arrived at NEADB
CSNI0007/01:
- 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.
- Tape Descriptions and Supplementary Information
- 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)
CSNI0007/01:
Idaho National Engineering Laboratory
EG&G Idaho
Idaho Falls, Idaho 83415.
U.S.A.
CSNI0007/01:
Directory (TOTAL: 73.0 MB )
Control valves 2.5 MB
Computed parameters 10.4 MB
Densities 3.1 MB
Flow velocities 6.7 MB
Frequencies 1.2 MB
Mass flows 3.1 MB
Level measurements 1.2 MB
Level measurements 3.7 MB
Momentum flux 5.5 MB
Neutron detector 4.3 MB
Differential pressure 11.7 MB
Pressure 12.9 MB
Pump parameters 1.2 MB
NIS power range 1.8 MB
ROD position 3.7 MB
Directory (TOTAL:116.4 MB )
Temperatures 116.4 MB
- Y. Integral Experiments Data, Databases, Benchmarks
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