A microprocessor tester for the treat upgrade reactor trip system

Conference · Fri Feb 01 04:00:00 EST 1985 · IEEE Trans. Nucl. Sci.; (United States)

OSTI ID:6135225

Lenkszus, F R; Bucher, R G

The upgrading of the Transient Reactor Test (TREAT) Facility at ANL-Idaho has been designed to provide additional experimental capabilities for the study of core disruptive accident (CDA) phenomena. To improve the analytical extrapolation of test results to full-size assembly bundles, the facility upgrade will increase the maximum size of the test bundle from 7 to 37 fuel pins. By creating a core convertor zone around the test location, the neutron spectrum incident on the test assembly will be hardened and the maximum energy deposited in the sample will be increased. In addition, a programmable Automated Reactor Control System (ARCS) will permit high-power transients up to 11,000 MW having a controlled reactor period of from 15 to 0.1 sec. These modifications to the core neutronics will improve simulation of LMFBR accident conditions. Finally, a sophisticated, multiply-redundant safety system, the Reactor Trip System (RTS), will provide safe operation for both steady state and transient production operating modes. To insure that this complex safety system is functioning properly, a Dedicated Microprocessor Tester (DMT) has been implemented to perform a thorough checkout of the RTS prior to all TREAT operations. A quantitative reliability analysis of the RTS shows that the unreliability, that is, the probability of failure, is acceptable for a 10 hour mission time or risk interval.

• Research Organization: Argonne National Lab., Argonne, IL
• OSTI ID: 6135225
• Report Number(s): CONF-841007-
• Conference Information: Journal Name: IEEE Trans. Nucl. Sci.; (United States) Journal Volume: NS-32:1
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
220400* -- Nuclear Reactor Technology-- Control Systems
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
ACCIDENTS
AIR COOLED REACTORS
BREEDER REACTORS
COMPUTERIZED CONTROL SYSTEMS
COMPUTERIZED SIMULATION
COMPUTERS
CONTROL SYSTEMS
ELECTRONIC CIRCUITS
ENRICHED URANIUM REACTORS
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FUEL ASSEMBLIES
FUEL ELEMENT CLUSTERS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HOMOGENEOUS REACTORS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MICROELECTRONIC CIRCUITS
MICROPROCESSORS
PERFORMANCE TESTING
REACTOR ACCIDENTS
REACTOR CONTROL SYSTEMS
REACTOR CORE DISRUPTION
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY
REACTORS
RESEARCH AND TEST REACTORS
SAFETY
SIMULATION
SOLID HOMOGENEOUS REACTORS
SPECTRAL HARDENING
SYSTEMS ANALYSIS
TEST REACTORS
TESTING
THERMAL REACTORS
TREAT REACTOR