Owen, 1963 - Google Patents
Measurement of power and burn-up in irradiated nuclear reactor fuel by a non-destructive methodOwen, 1963
- Document ID
- 14785760926667338518
- Author
- Owen T
- Publication year
- Publication venue
- British Journal of Applied Physics
External Links
Snippet
A simple non-descructive test for measuring power and burn-up in irradiated nuclear reactor fuel is described. The method involves scanning the fuel elements via a slit in shielding for the gamma activity of two specific fission products. A short half-life fission product gives a …
- 239000003758 nuclear fuel 0 title abstract description 9
Classifications
-
- 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
- G21C17/108—Measuring reactor flux
-
- 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
- G21C3/42—Selection of substances for use as reactor fuel
-
- 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
- G01T—MEASUREMENT OF NUCLEAR OR X-RADIATION
- G01T1/00—Measuring X-radiation, gamma radiation, corpuscular radiation, or cosmic radiation
- G01T1/16—Measuring radiation intensity
-
- 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
- G01V5/04—Prospecting or detecting by the use of nuclear radiation, e.g. of natural or induced radioactivity specially adapted for well-logging
- G01V5/08—Prospecting or detecting by the use of nuclear radiation, e.g. of natural or induced radioactivity specially adapted for well-logging using primary nuclear radiation sources or X-rays
- G01V5/10—Prospecting or detecting by the use of nuclear radiation, e.g. of natural or induced radioactivity specially adapted for well-logging using primary nuclear radiation sources or X-rays using neutron sources
- G01V5/107—Prospecting or detecting by the use of nuclear radiation, e.g. of natural or induced radioactivity specially adapted for well-logging using primary nuclear radiation sources or X-rays using neutron sources and detecting reflected or back-scattered neutrons
-
- G—PHYSICS
- G01—MEASURING; TESTING
- G01T—MEASUREMENT OF NUCLEAR OR X-RADIATION
- G01T3/00—Measuring neutron radiation
- G01T3/06—Measuring neutron radiation with scintillation detectors
-
- G—PHYSICS
- G01—MEASURING; TESTING
- G01T—MEASUREMENT OF NUCLEAR OR X-RADIATION
- G01T7/00—Details of radiation-measuring instruments
- G01T7/02—Collecting means for receiving or storing samples to be investigated and possibly directly transporting the samples to the measuring arrangement; particularly for investigating radioactive fluids
-
- 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
Similar Documents
Publication | Publication Date | Title |
---|---|---|
Phillips et al. | Application of nondestructive gamma-ray and neutron techniques for the safeguarding of irradiated fuel materials | |
Bartolome et al. | Neutron radiative capture and transmission measurements of W and Zr isotopes in the keV region | |
EP1576618A1 (en) | Method and apparatus for carrying out a mox fuel rod quality control | |
Matsson et al. | Developments in gamma scanning irradiated nuclear fuel | |
Owen | Measurement of power and burn-up in irradiated nuclear reactor fuel by a non-destructive method | |
Edwards | A review of recent studies of nondestructive assay methods for irradiated nuclear fuels | |
Tunnicliffe et al. | A Method for the Accurate Determination of Relative Initial Conversion Ratios | |
US4881247A (en) | Measuring nuclear fuel burnup | |
Khan et al. | TRIGA fuel burn-up calculations and its confirmation | |
Ariemma et al. | Experimental and Theoretical Determination of Burnup and Heavy Isotope Content in a Fuel Assembly Irradiated in the Garigliano Boiling Water Reactor. EUR 4638. | |
Chen et al. | Non-destructive determination of burnup by gamma-scanning: an assessment of cesium-134/cesium-137 activity ratio as a fission monitor in CANDU fuels | |
Forsyth et al. | Burn-up determination by high resolution gamma spectrometry: axial and diametral scanning experiments | |
Parker et al. | PASSIVE ASSAY: INNOVATIONS AND APPLICATIONS. | |
Bunin et al. | OPERATING EXPERIENCE WITH IBR REACTOR, ITS USE FOR NEUTRON INVESTIGATIONS AND ITS CHARACTERISTICS ON NEUTRON INJECTION FROM A MICROTRON | |
Holschuh et al. | Reactor Metrology for TREAT Experiments [PowerPoint] | |
Johnson et al. | Integral measurements in a simulated fast breeder reactor blanket | |
Lipsett et al. | Study of gamma-ray spectroscopy for spent fuel verification at the bruce candu reactors | |
Dawson et al. | Measurement of thermal power density distributions by fuel pin gamma scanning | |
Christensen et al. | DETERMINATION OF RELATIVE BURNUP BY GAMMA SCANNING EBWR FUEL RODS. | |
Driscoll et al. | REACTOR PHYSICS PROJECT PROGRESS REPORT NO. 2. | |
Menlove et al. | A photoneutron antimony-124-beryllium system for fissile materials assay | |
Dickens et al. | Experiment for accurate measurements of fission product energy release for short times after thermal-neutron fission of 235U and 239Pu | |
RU2316064C2 (en) | Method and device for quality control of mox fuel rods | |
JPH0549198B2 (en) | ||
Kull | CATALOGUE OF NUCLEAR MATERIAL SAFEGUARDS INSTRUMENTS. |