Proof-of-principle measurements for an NDA-based core discharge monitor
Description
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 … continued below
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6 pages
Creation Information
Halbig, J. K. (Los Alamos National Lab., NM (USA)) & Monticone, A. C. (International Atomic Energy Agency, Vienna (Austria)) January 1, 1990.
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Los Alamos National Laboratory
Publisher Info: Los Alamos National Lab., NM (USA)Place of Publication: New Mexico
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Description
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.
Physical Description
6 pages
Notes
NTIS, PC A02/MF A01; OSTI; INIS; GPO Dep.
Subjects
Keywords
- Bruce-3 Reactor
- Candu Type Reactors
- Counting Techniques
- Detection
- Feasibility Studies
- Fuel Elements
- Gamma Detection
- Heavy Water Cooled Reactors
- Heavy Water Moderated Reactors
- Iaea
- International Organizations
- Maintenance
- Management
- Materials Handling
- Monitoring
- Natural Uranium Reactors
- Neutron Detection
- Nuclear Materials Management
- Performance
- Phwr Type Reactors
- Power Density
- Power Reactors
- Pressure Tube Reactors
- Radiation Detection
- Radiation Monitoring
- Radioactive Waste Storage
- Reactivity
- Reactor Components
- Reactor Cores
- Reactor Maintenance
- Reactor Monitoring Systems
- Reactors
- Safeguards
- Spent Fuel Elements
- Storage
- Thermal Reactors
- Waste Management
- Waste Storage 210400* -- Power Reactors, Nonbreeding, Otherwise Moderated Or Unmoderated
STI Subject Categories
- 050900 -- Nuclear Fuels-- Transport, Handling, & Storage
- 052002 -- Nuclear Fuels-- Waste Disposal & Storage
- 055000 -- Nuclear Fuels-- Safeguards, Inspection, & Accountability
- 11 Nuclear Fuel Cycle And Fuel Materials
- 12 Management Of Radioactive And Non-Radioactive Wastes From Nuclear Facilities
- 21 Specific Nuclear Reactors And Associated Plants
- 440101 -- Radiation Instrumentation-- General Detectors Or Monitors & Radiometric Instruments
- 46 Instrumentation Related To Nuclear Science And Technology
- 98 Nuclear Disarmament, Safeguards, And Physical Protection
- 99 General And Miscellaneous//Mathematics, Computing, And Information Science
- 990200 -- Mathematics & Computers
Source
- Institute of nuclear materials management conference, Los Angeles, CA (USA), 15-18 Jul 1990
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- Other: DE90014927
- Report No.: LA-UR-90-2357
- Report No.: CONF-9007106--45
- Grant Number: W-7405-ENG-36
- Office of Scientific & Technical Information Report Number: 7084901
- Archival Resource Key: ark:/67531/metadc1415684
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- January 1, 1990
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- Jan. 23, 2019, 12:54 p.m.
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- July 18, 2019, 6:31 p.m.
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Halbig, J. K. (Los Alamos National Lab., NM (USA)) & Monticone, A. C. (International Atomic Energy Agency, Vienna (Austria)). Proof-of-principle measurements for an NDA-based core discharge monitor, article, January 1, 1990; New Mexico. (https://digital.library.unt.edu/ark:/67531/metadc1415684/: accessed July 16, 2024), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.