Baseline data for LOFT Level I core requalification

Technical Report · Tue Dec 12 04:00:00 EST 1978

OSTI ID:5433122

Cannon, J W; Briscoe, A V; Carpenter, W R; Chick, D R; Knight, D W; Serrano, W; Talbert, R J; Yarbrough, W M; Zentner, M D; Zimmerman, W L

Fuel Module Requalification (FMR) is performed prior to achieving significant power levels after each Loss of Coolant Experiment (LOCE). Level I Requalification consists of a progressive series of tests designed to determine whether sufficient core damage has occurred to make Levels II or III Requalification testing necessary. It includes an examination of LOCE data to determine whether core damage is probable and a series of functional and physics tests to examine operational characteristics of the reactor system. This series of tests is basically a comparison of data obtained before (baseline) and after the LOCE for differences which may indicate core damage has occurred. This report is written to support the Level I Requalification. It presents the pre-LOCE baseline data and contains a discussion of this data and of pertinent items to consider when performing the tests to make Level I Requalification as reliable as possible. The data, which were acquired during Zero Power Physics testing (completed March 13, 1978), are presented in the form of plots and tables for efficient data analysis during future requalification testing. Additional detailed, raw test data are presented in the Appendices so that, when necessary, detailed test conditions and results may be compared. The nuclear signature test results, which are not readily reduceible and require specialized expertise for analysis, are contained entirely in Appendix E. 6 refs., 46 figs., 14 tabs.

• Research Organization: EG and G Idaho, Inc., Idaho Falls (USA)
• DOE Contract Number: AC07-76ID01570
• OSTI ID: 5433122
• Report Number(s): EGG/LTR-111-102; RE-P-78-075; ON: DE85015429
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
CONTROL ELEMENTS
DAMAGE
KINETICS
LOFT REACTOR
LOSS OF COOLANT
OPERATION
POWER DENSITY
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CORES
REACTOR KINETICS
REACTOR OPERATION
REACTOR SAFETY EXPERIMENTS
REACTOR START-UP
REACTORS
RESEARCH AND TEST REACTORS
START-UP
TANK TYPE REACTORS
TEST REACTORS
TESTING
WATER COOLED REACTORS
WATER MODERATED REACTORS