Proof-of-principle measurements for an NDA-based core discharge monitor
- Los Alamos National Lab., NM (USA)
- International Atomic Energy Agency, Vienna (Austria)
The feasibility of using nondestructive assay instruments as a core discharge monitor for CANDU reactors was investigated at the Ontario Hydro Bruce Nuclear Generating Station A, Unit 3, in Ontario, Canada. The measurements were made to determine if radiation signatures from discharged irradiated fuel could be measured unambiguously and used to count the number of fuel pushes from a reactor face. Detectors using the ({gamma},n) reaction thresholds of beryllium and deuterium collected the data, but data from shielded and unshielded ion chambers were collected as well. The detectors were placed on a fueling trolley that carried the fueling machine between the reactors and the central service area. A microprocessor-based electronics system (the GRAND-I, which also resided on the trolley) provided detector biases and preamplifier power and acquired and transferred the data. It was connected by an RS-232 serial link to a lap-top computer adjacent to the fueling control console in the main-reactor control room. The lap-top computer collected and archived the data on a 3.5-in. floppy disk. The results clearly showed such an approach to be a adaptable as a core discharge monitor. 4 refs., 8 figs.
- Research Organization:
- Los Alamos National Laboratory (LANL), Los Alamos, NM (United States)
- Sponsoring Organization:
- DOE/DP
- DOE Contract Number:
- W-7405-ENG-36
- OSTI ID:
- 7084901
- Report Number(s):
- LA-UR-90-2357; CONF-9007106-45; ON: DE90014927; TRN: 90-025948
- Resource Relation:
- Conference: Institute of nuclear materials management conference, Los Angeles, CA (USA), 15-18 Jul 1990
- Country of Publication:
- United States
- Language:
- English
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11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
98 NUCLEAR DISARMAMENT, SAFEGUARDS, AND PHYSICAL PROTECTION
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND TECHNOLOGY
99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE
BRUCE-3 REACTOR
RADIATION MONITORING
SPENT FUEL ELEMENTS
CANDU TYPE REACTORS
COUNTING TECHNIQUES
FEASIBILITY STUDIES
GAMMA DETECTION
IAEA
MATERIALS HANDLING
NEUTRON DETECTION
NUCLEAR MATERIALS MANAGEMENT
PERFORMANCE
POWER DENSITY
RADIOACTIVE WASTE STORAGE
REACTIVITY
REACTOR CORES
REACTOR MAINTENANCE
REACTOR MONITORING SYSTEMS
SAFEGUARDS
DETECTION
FUEL ELEMENTS
HEAVY WATER COOLED REACTORS
HEAVY WATER MODERATED REACTORS
INTERNATIONAL ORGANIZATIONS
MAINTENANCE
MANAGEMENT
MONITORING
NATURAL URANIUM REACTORS
PHWR TYPE REACTORS
POWER REACTORS
PRESSURE TUBE REACTORS
RADIATION DETECTION
REACTOR COMPONENTS
REACTORS
STORAGE
THERMAL REACTORS
WASTE MANAGEMENT
WASTE STORAGE
210400* - Power Reactors
Nonbreeding
Otherwise Moderated or Unmoderated
050900 - Nuclear Fuels- Transport
Handling
& Storage
055000 - Nuclear Fuels- Safeguards
Inspection
& Accountability
052002 - Nuclear Fuels- Waste Disposal & Storage
440101 - Radiation Instrumentation- General Detectors or Monitors & Radiometric Instruments
990200 - Mathematics & Computers