Estimation of burnup in Taiwan research reactor fuel pins by using nondestructive techniques
Journal Article
·
· Nuclear Technology; (United States)
OSTI ID:6480731
- Chung Cheng Inst. of Tech., Taoyuan (Taiwan, Province of China)
- Inst. of Nuclear Energy Research, Taoyuan (Taiwan, Province of China)
A nondestructive measurement of spent fuel pins from the Taiwan Research Reactor has been performed at the Institute of Nuclear Energy Research. The analysis is based on a simplified balance equation for integrated flux and a series of one-group burnup-dependent microscopic cross-section libraries. A semiempirical test is used for evaluating the burnup values of two different kinds of spent fuel pins [natural uranium (0.7% [sup 235]U) and enriched uranium (7.0 % [sup 235]U)] by the [sup 134]Cs/ [sup 137]Cs activity ratio. Results are compared with radio-chemical burnup measurements. The agreement is within 3.8%, which verifies the accuracy of this method. The results are also compared with a theoretical estimation by the ORIGEN-II code. This indicates that the ORIGEN-II code's library might have an overestimated [sigma][sub a]([sup 133]Cs), which leads to a [sup 134]Cs/[sup 137]Cs ratio that would result in a burnup value [approximately]24 to 35% lower than the measured data.
- OSTI ID:
- 6480731
- Journal Information:
- Nuclear Technology; (United States), Journal Name: Nuclear Technology; (United States) Vol. 102:3; ISSN 0029-5450; ISSN NUTYBB
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
220600* -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
ACTINIDES
ACTIVITY LEVELS
ALKALI METAL ISOTOPES
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
BURNUP
CESIUM 134
CESIUM 137
CESIUM ISOTOPES
CHEMICAL ANALYSIS
COMPARATIVE EVALUATIONS
ELECTRON CAPTURE RADIOISOTOPES
ELEMENTS
ENRICHED URANIUM
EVALUATION
FISSION PRODUCTS
FUEL ELEMENTS
FUEL PINS
GAMMA SPECTROSCOPY
HOURS LIVING RADIOISOTOPES
INTERMEDIATE MASS NUCLEI
INTERNAL CONVERSION RADIOISOTOPES
ISOMERIC TRANSI
ISOTOPE ENRICHED MATERIALS
ISOTOPES
MATERIALS
METALS
NATURAL URANIUM
NONDESTRUCTIVE ANALYSIS
NUCLEI
ODD-EVEN NUCLEI
RADIOACTIVE MATERIALS
RADIOISOTOPES
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SPECTROSCOPY
SPENT FUEL ELEMENTS
URANIUM
YEARS LIVING RADIOISOTOPES
220600* -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
ACTINIDES
ACTIVITY LEVELS
ALKALI METAL ISOTOPES
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
BURNUP
CESIUM 134
CESIUM 137
CESIUM ISOTOPES
CHEMICAL ANALYSIS
COMPARATIVE EVALUATIONS
ELECTRON CAPTURE RADIOISOTOPES
ELEMENTS
ENRICHED URANIUM
EVALUATION
FISSION PRODUCTS
FUEL ELEMENTS
FUEL PINS
GAMMA SPECTROSCOPY
HOURS LIVING RADIOISOTOPES
INTERMEDIATE MASS NUCLEI
INTERNAL CONVERSION RADIOISOTOPES
ISOMERIC TRANSI
ISOTOPE ENRICHED MATERIALS
ISOTOPES
MATERIALS
METALS
NATURAL URANIUM
NONDESTRUCTIVE ANALYSIS
NUCLEI
ODD-EVEN NUCLEI
RADIOACTIVE MATERIALS
RADIOISOTOPES
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SPECTROSCOPY
SPENT FUEL ELEMENTS
URANIUM
YEARS LIVING RADIOISOTOPES