Holcombe et al., 2013 - Google Patents
Feasibility of identifying leaking fuel rods using gamma tomographyHolcombe et al., 2013
View PDF- Document ID
- 9507530748024878968
- Author
- Holcombe S
- Svärd S
- Eitrheim K
- Hallstadius L
- Willman C
- Publication year
- Publication venue
- Annals of Nuclear Energy
External Links
Snippet
In cases of fuel failure in irradiated nuclear fuel assemblies, causing leakage of fission gasses from a fuel rod, there is a need for reliable non-destructive measurement methods that can determine which rod is failed. Methods currently in use include visual inspection …
- 239000000446 fuel 0 title abstract description 143
Classifications
-
- 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
- G21C17/04—Detecting burst slugs
-
- 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
- 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
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/02—Fuel elements
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/10—Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21Y—INDEXING SCHEME RELATING TO NUCLEAR REACTORS, POWER PLANTS AND EXPLOSIVES, TO PROTECTION AGAINST RADIATION, TO THE TREATMENT OF RADIOACTIVELY CONTAMINATED MATERIAL, TO APPLICATIONS OF RADIOACTIVE SOURCES AND TO THE UTILISATION OF COSMIC RADIATION
- G21Y2004/00—SOLUTION
- G21Y2004/30—Improving a design
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21Y—INDEXING SCHEME RELATING TO NUCLEAR REACTORS, POWER PLANTS AND EXPLOSIVES, TO PROTECTION AGAINST RADIATION, TO THE TREATMENT OF RADIOACTIVELY CONTAMINATED MATERIAL, TO APPLICATIONS OF RADIOACTIVE SOURCES AND TO THE UTILISATION OF COSMIC RADIATION
- G21Y2002/00—PROBLEM
- G21Y2002/104—Inadequate performance, deformation, cracks, rupture
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21Y—INDEXING SCHEME RELATING TO NUCLEAR REACTORS, POWER PLANTS AND EXPLOSIVES, TO PROTECTION AGAINST RADIATION, TO THE TREATMENT OF RADIOACTIVELY CONTAMINATED MATERIAL, TO APPLICATIONS OF RADIOACTIVE SOURCES AND TO THE UTILISATION OF COSMIC RADIATION
- G21Y2002/00—PROBLEM
- G21Y2002/304—Lack of versatility, compatibility
-
- G—PHYSICS
- G01—MEASURING; TESTING
- G01T—MEASUREMENT OF NUCLEAR OR X-RADIATION
- G01T1/00—Measuring X-radiation, gamma radiation, corpuscular radiation, or cosmic radiation
- G01T1/29—Measurement performed on radiation beams, e.g. position or section of the beam; Measurement of spatial distribution of radiation
- G01T1/2914—Measurement of spatial distribution of radiation
-
- 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
- G01—MEASURING; TESTING
- G01T—MEASUREMENT OF NUCLEAR OR X-RADIATION
- G01T7/00—Details of radiation-measuring instruments
-
- 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
Similar Documents
Publication | Publication Date | Title |
---|---|---|
Parker et al. | The use of ionising radiation to image nuclear fuel: A review | |
Holcombe et al. | A Novel gamma emission tomography instrument for enhanced fuel characterization capabilities within the OECD Halden Reactor Project | |
Vaccaro et al. | Advancing the Fork detector for quantitative spent nuclear fuel verification | |
Svärd et al. | Applicability of a set of tomographic reconstruction algorithms for quantitative SPECT on irradiated nuclear fuel assemblies | |
Smith et al. | A viability study of gamma emission tomography for spent fuel verification: JNT 1955 phase I technical report | |
Biard | Quantitative analysis of the fission product distribution in a damaged fuel assembly using gamma-spectrometry and computed tomography for the Phébus FPT3 test | |
Tupasela et al. | Passive neutron albedo reactivity measurements of spent nuclear fuel | |
Lafleur | Development of self-interrogation neutron resonance densitometry (SINRD) to measure the fissile content in nuclear fuel | |
Lee et al. | Investigation of a fast partial defect detection method for safeguarding PWR spent fuel assemblies | |
Holcombe et al. | Feasibility of identifying leaking fuel rods using gamma tomography | |
Trellue et al. | Spent fuel nondestructive assay integrated characterization from active neutron, passive neutron, and passive gamma | |
Lafleur et al. | Development of self-interrogation neutron resonance Densitometry to improve detection of possible diversions for PWR spent fuel assemblies | |
Levi et al. | Nondestructive measurements of residual 235U mass of Israeli Research Reactor-1 fuel using the Advanced Experimental Fuel Counter | |
Branger et al. | Comparison of prediction models for Cherenkov light emissions from nuclear fuel assemblies | |
Akyurek et al. | Spent fuel interrogation using delayed fast neutron spectrum at Missouri University of Science and Technology Reactor | |
Sagara et al. | Feasibility study of passive gamma spectrometry of molten core material from Fukushima Daiichi Nuclear Power Station unit 1, 2, and 3 cores for special nuclear material accountancy–low-volatile FP and special nuclear material inventory analysis and fundamental characteristics of gamma-rays from fuel debris: Fukushima NPP Accident Related | |
Svärd et al. | Nondestructive experimental determination of the pin-power distribution in nuclear fuel assemblies | |
Jacobsson et al. | Outcomes of the JNT 1955 phase I viability study of gamma emission tomography for spent fuel verification | |
Bagheri et al. | An efficient method for detecting damaged FAs; burnup and PPF estimations by gamma spectroscopy | |
Plukienė et al. | Actinides in irradiated graphite of RBMK-1500 reactor | |
Shiba et al. | MLEM reconstruction method applied to partial defect verification using simulated data | |
Fensin et al. | A Monte Carlo based spent fuel analysis safeguards strategy assessment | |
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 | |
Holcombe et al. | Determination of the rod-wise fission gas release fraction in a complete fuel assembly using non-destructive gamma emission tomography | |
Matsumura et al. | Development of monitoring technique for the confirmation of spent fuel integrity during storage |