Optimization of the Spent Fuel Attribute Tester using radiation transport calculations
Creators
- 1. Sandia National Labs., Albuquerque, NM (United States)
- 2. International Atomic Energy Agency, Vienna (Austria). Dept. of Safeguards
Description
The International Atomic Energy Agency uses the Spent Fuel Attribute Tester (SFAT) to measure gamma signatures from fuel assemblies stored in spent fuel pools. It consists of a shielded, collimated NaI(Tl) detector attached to an air-filled pipe. The purpose of the present study was to define design changes, within operational constraints, that would improve the target assembly 137Cs signal relative to the background signals from adjacent assemblies. This improvement is essential to reducing to an acceptable level the measurement time during an inspection. Monte Carlo calculations of the entire geometry were impractical; therefore, a hybrid method was developed that combined one-dimensional discrete ordinates models of the spent fuel pool, three-dimensional Monte Carlo calculations of the SFAT, and detector response calculations. The method compared well with measurements taken with the existing baseline SFAT. Calculations predicted significant improvements in signal-to-noise ratio. Recommended changes included shortening the pipe and increasing its wall thickness, placing low-Z filters in the crystal line of sight, reducing the thickness of shielding around the collimator aperture and adding shielding around the crystal, and reducing the diameter of the crystal. An instrument incorporating these design changes is being fabricated in Finland and will be tested this year
Additional details
Publishing Information
- Publisher
- Institute of Nuclear Materials Management.
- Imprint Place
- Northbrook, IL (United States)
- Imprint Title
- Nuclear materials management. 34th Annual meeting proceedings: Volume 22
- Imprint Pagination
- 1190 p.
- Journal Page Range
- p. 1059-1065.
Conference
- Title
- 34. annual meeting of the Institute of Nuclear Materials Management.
- Dates
- 18-21 Jul 1993.
- Place
- Scottsdale, AZ (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 26067358
- Subject category
- S46: INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND TECHNOLOGY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- BWR TYPE REACTORS; CALCULATION METHODS; CESIUM 137; DESIGN; EXPERIMENTAL DATA; FUEL STORAGE POOLS; GAMMA DETECTION; MATHEMATICAL MODELS; MODIFICATIONS; NAI DETECTORS; PERFORMANCE; RADIOMETRIC ANALYSIS; RECOMMENDATIONS; SOURCE TERMS; SPENT FUEL ELEMENTS; SPENT FUELS
- Descriptors DEC
- BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; CESIUM ISOTOPES; CHEMICAL ANALYSIS; DATA; DETECTION; ENERGY SOURCES; ENRICHED URANIUM REACTORS; FUEL ELEMENTS; FUELS; INFORMATION; INTERMEDIATE MASS NUCLEI; ISOTOPES; MATERIALS; MEASURING INSTRUMENTS; NUCLEAR FUELS; NUCLEI; NUMERICAL DATA; ODD-EVEN NUCLEI; POWER REACTORS; QUANTITATIVE CHEMICAL ANALYSIS; RADIATION DETECTION; RADIATION DETECTORS; RADIOISOTOPES; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; SCINTILLATION COUNTERS; SOLID SCINTILLATION DETECTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; YEARS LIVING RADIOISOTOPES
Optional Information
- Secondary number(s)
- CONF-930749--.