Holcombe et al., 2016 - Google Patents
Determination of the rod-wise fission gas release fraction in a complete fuel assembly using non-destructive gamma emission tomographyHolcombe et al., 2016
- Document ID
- 12676859719233116145
- Author
- Holcombe S
- Andersson P
- Svärd S
- Hallstadius L
- Publication year
- Publication venue
- Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment
External Links
Snippet
A gamma tomography instrument has been developed at the Halden Boiling Water Reactor (HBWR) in cooperation between the Institute for Energy Technology, Westinghouse (Sweden) and Uppsala University. The instrument is used to record the gamma radiation …
- 239000000446 fuel 0 title abstract description 192
Classifications
-
- G—PHYSICS
- G01—MEASURING; TESTING
- G01N—INVESTIGATING OR ANALYSING MATERIALS BY DETERMINING THEIR CHEMICAL OR PHYSICAL PROPERTIES
- G01N23/00—Investigating or analysing materials by the use of wave or particle radiation not covered by G01N21/00 or G01N22/00, e.g. X-rays or neutrons
- G01N23/02—Investigating or analysing materials by the use of wave or particle radiation not covered by G01N21/00 or G01N22/00, e.g. X-rays or neutrons by transmitting the radiation through the material
- G01N23/06—Investigating or analysing materials by the use of wave or particle radiation not covered by G01N21/00 or G01N22/00, e.g. X-rays or neutrons by transmitting the radiation through the material and measuring the absorption
- G01N23/08—Investigating or analysing materials by the use of wave or particle radiation not covered by G01N21/00 or G01N22/00, e.g. X-rays or neutrons by transmitting the radiation through the material and measuring the absorption using electric detection means
-
- G—PHYSICS
- G01—MEASURING; TESTING
- G01T—MEASUREMENT OF NUCLEAR OR X-RADIATION
- G01T1/00—Measuring X-radiation, gamma radiation, corpuscular radiation, or cosmic radiation
- G01T1/16—Measuring radiation intensity
- G01T1/169—Exploration, location of contaminated surface areas in situ measurement, e.g. floor contamination monitor
-
- G—PHYSICS
- G01—MEASURING; TESTING
- G01N—INVESTIGATING OR ANALYSING MATERIALS BY DETERMINING THEIR CHEMICAL OR PHYSICAL PROPERTIES
- G01N23/00—Investigating or analysing materials by the use of wave or particle radiation not covered by G01N21/00 or G01N22/00, e.g. X-rays or neutrons
- G01N23/02—Investigating or analysing materials by the use of wave or particle radiation not covered by G01N21/00 or G01N22/00, e.g. X-rays or neutrons by transmitting the radiation through the material
- G01N23/04—Investigating or analysing materials by the use of wave or particle radiation not covered by G01N21/00 or G01N22/00, e.g. X-rays or neutrons by transmitting the radiation through the material and forming a picture
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/06—Devices or arrangements for monitoring or testing fuel or fuel elements outside the reactor core, e.g. for burn-up, for contamination
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/02—Devices or arrangements for monitoring coolant or moderator
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/02—Fuel elements
-
- G—PHYSICS
- G01—MEASURING; TESTING
- G01N—INVESTIGATING OR ANALYSING MATERIALS BY DETERMINING THEIR CHEMICAL OR PHYSICAL PROPERTIES
- G01N2223/00—Investigating materials by wave or particle radiation
- G01N2223/60—Specific applications or type of materials
-
- G—PHYSICS
- G01—MEASURING; TESTING
- G01T—MEASUREMENT OF NUCLEAR OR X-RADIATION
- G01T7/00—Details of radiation-measuring instruments
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21G—CONVERSION OF CHEMICAL ELEMENTS; RADIOACTIVE SOURCES
- G21G1/00—Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation or particle bombardment, e.g. producing radioactive isotopes
-
- G—PHYSICS
- G01—MEASURING; TESTING
- G01V—GEOPHYSICS; GRAVITATIONAL MEASUREMENTS; DETECTING MASSES OR OBJECTS
- G01V5/00—Prospecting or detecting by the use of nuclear radiation, e.g. of natural or induced radioactivity
- G01V5/0008—Detecting hidden objects, e.g. weapons, explosives
-
- G—PHYSICS
- G01—MEASURING; TESTING
- G01T—MEASUREMENT OF NUCLEAR OR X-RADIATION
- G01T5/00—Recording of movements or tracks of particles; Processing or analysis of such tracks
Similar Documents
Publication | Publication Date | Title |
---|---|---|
Holcombe et al. | A Novel gamma emission tomography instrument for enhanced fuel characterization capabilities within the OECD Halden Reactor Project | |
Favalli et al. | Determining initial enrichment, burnup, and cooling time of pressurized-water-reactor spent fuel assemblies by analyzing passive gamma spectra measured at the Clab interim-fuel storage facility in Sweden | |
Vaccaro et al. | PWR and BWR spent fuel assembly gamma spectra measurements | |
Hellesen et al. | Nuclear spent fuel parameter determination using multivariate analysis of fission product gamma spectra | |
Svärd et al. | Applicability of a set of tomographic reconstruction algorithms for quantitative SPECT on irradiated nuclear fuel assemblies | |
Terremoto et al. | Gamma-ray spectroscopy on irradiated MTR fuel elements | |
Smith et al. | A viability study of gamma emission tomography for spent fuel verification: JNT 1955 phase I technical report | |
Caruso et al. | Design, development and utilisation of a tomography station for γ-ray emission and transmission analyses of light water reactor spent fuel rods | |
Andersson et al. | A computerized method (UPPREC) for quantitative analysis of irradiated nuclear fuel assemblies with gamma emission tomography at the Halden reactor | |
Biard | Quantitative analysis of the fission product distribution in a damaged fuel assembly using gamma-spectrometry and computed tomography for the Phébus FPT3 test | |
Kirchknopf et al. | Determining burnup, cooling time and operational history of VVER-440 spent fuel assemblies based on in-situ gamma spectrometry at Paks Nuclear Power Plant | |
Holcombe et al. | Determination of the rod-wise fission gas release fraction in a complete fuel assembly using non-destructive gamma emission tomography | |
Košťál et al. | Neutron deep penetration through reactor pressure vessel and biological concrete shield of VVER-1000 Mock-Up in LR-0 reactor | |
Andersson et al. | Inspection of a LOCA test rod at the Halden reactor project using gamma emission tomography | |
Lee et al. | Investigation of a fast partial defect detection method for safeguarding PWR spent fuel assemblies | |
Fakhr et al. | Investigation and comparison of neutron image quality using monochromatic and polychromatic beams of Tehran Research Reactor by Monte Carlo simulation | |
Caruso et al. | Validation of 134Cs, 137Cs and 154Eu single ratios as burnup monitors for ultra-high burnup UO2 fuel | |
Grape et al. | Verifying nuclear fuel assemblies in wet storages on a partial defect level: A software simulation tool for evaluating the capabilities of the Digital Cherenkov Viewing Device | |
Kilby et al. | Multi-modal tomographic imaging system for poolside characterization of nuclear test fuels: Design considerations and studies | |
Ansari et al. | Burnup studies of spent fuels of varying types and enrichment | |
Holcombe et al. | Feasibility of identifying leaking fuel rods using gamma tomography | |
Cheng et al. | Feasibility study for wax deposition imaging in oil pipelines by PGNAA technique | |
Prokopowicz et al. | Determination of nuclear fuel burn-up axial profile by neutron emission measurement | |
Caruso et al. | Comparison of optimised germanium gamma spectrometry and multicollector inductively coupled plasma mass spectrometry for the determination of 134Cs, 137Cs and 154Eu single ratios in highly burnt UO2 | |
Maslov et al. | Application of Cdznte detectors for control of initial enrichment of fresh nuclear fuel at refueling |