Summary of LOCE L2-2/L2-3 analysis and LOFT/zion prototypic study
To date, two 200% double-ended cold leg break experiments have been completed in the LOFT Power Ascension Test Series. LOCE L2-3 was conducted with maximum linear heat generation rate, core fluid temperature rise (..delta..T), and system pressure characteristic of the normal operating conditions of a commercial pressurized water reactor (PWR). The thermal behavior of the core in both experiments was dominated by a self-induced cooling mechanism which occurred soon after experiment initiation. The dominance of this phenomena versus current licensing calculation restrictions raises the question of the prototypicality of the LOFT results. The ensuing discussion summarizes both an analysis of the most significant experimental results and a prototypic study of the LOFT results relative to ZION, a commercial PWR. ZION is similar to TROJAN, the commercial PWR to which LOFT was scaled.
- Research Organization:
- Idaho National Engineering Lab., Idaho Falls (USA)
- DOE Contract Number:
- EY-76-C-07-1570
- OSTI ID:
- 5687224
- Report Number(s):
- IDO-1570-T29
- Country of Publication:
- United States
- Language:
- English
Similar Records
Analysis of LOFT large break experiments L2-3 and L2-5 using RELAP5/MOD1. [PWR]
Preliminary posttest analysis of LOFT loss-of-coolant experiment L2-2
Quick look report on LOFT nuclear experiment L2-2. [PWR]
Conference
·
Fri Dec 31 23:00:00 EST 1982
·
OSTI ID:5444854
Preliminary posttest analysis of LOFT loss-of-coolant experiment L2-2
Technical Report
·
Fri Jun 01 00:00:00 EDT 1979
·
OSTI ID:6200503
Quick look report on LOFT nuclear experiment L2-2. [PWR]
Technical Report
·
Thu Nov 30 23:00:00 EST 1978
·
OSTI ID:6158786
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
COMPARATIVE EVALUATIONS
COMPUTER CALCULATIONS
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
LOFT REACTOR
LOSS OF COOLANT
MECHANICS
POWER REACTORS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
RESEARCH AND TEST REACTORS
SAFETY
SIMULATION
TANK TYPE REACTORS
TEST REACTORS
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZION-1 REACTOR
ZION-2 REACTOR
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
COMPARATIVE EVALUATIONS
COMPUTER CALCULATIONS
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
LOFT REACTOR
LOSS OF COOLANT
MECHANICS
POWER REACTORS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
RESEARCH AND TEST REACTORS
SAFETY
SIMULATION
TANK TYPE REACTORS
TEST REACTORS
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZION-1 REACTOR
ZION-2 REACTOR