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Swinhoe, Martyn Thomas

Publications and source records attributed to Swinhoe, Martyn Thomas.

Use of a deuterium-deuterium neutron generator for the Add-A-Source waste matrix correction technique

Neutron generators offer an alternative to radioactive sources in the application of active techniques for nondestructive assay of nuclear materials. The Add-A-Source technique has enabled improvements in the ability to accurately measure waste bearing nuclear materials by measuring and correcting for the non-nuclear matrix effect. The technique has historically been performed with a Cf-252 spontaneous fission source. Here, in this work, we have demonstrated the use of a Deuterium-deuterium neutron generator in place of the Cf-252 source. A DD generator enables operational advantages and allows the simplification of the instrument design, while offering equivalent corrective performance as a Cf-252 source.

46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND ↗

A new generation of uranium coincidence fast neutron collars for assay of LWR fresh fuel assemblies

The active uranium neutron coincidence collar provides a means of non-destructively assaying the fissile linear density of Light Water Reactor fresh fuel assemblies containing low enriched uranium. These neutron collars can operate in two modes: a thermal and a fast mode. In fast mode, a neutron collar has an added cadmium (Cd) liner in the sample cavity of the detector to reduce the impact of the burnable poison (thermal neutron absorber) on the detector signal (doubles). The main advantage for operating in fast mode is a detected signal that is less dependent of the burnable neutron poison content and thus less dependent on facility operator declarations. The drawback is that operating in fast mode requires a longer measurement time (~hour vs tens of minutes for thermal mode) to achieve the statistically needed precision in the measurements. The trend in the modern reactor fuel assemblies is moving to higher burnup by using higher initial enrichment and, consequently, a higher number of burnable poison rods to compensate the initial neutron reactivity. The increase of the burnable poison loading has motivated the development of a new generation of high efficiency fast neutron collars to allow practical measurements in-field by nuclear inspectors. This paper describes the development and performance evaluation of a new generation of neutron collars, for both boiling water reactor (BWR) and pressurized water reactor (PWR) fuels, jointly developed between the US Department of Energy, through Los Alamos National Laboratory, and the Euratom Safeguards Directorate of the European Commission. In this work, we present here calibrations with reference fuel assemblies at Los Alamos National Laboratory as well as the results of in-field measurement campaigns in fuel fabrication plants with modern commercial fuel assemblies. The experimental results show that a typical PWR verification can be made in a total time of 30 min with an uncertainty in the measured mass of 2% at one standard deviation (1σ). A BWR verification can be made in 47 min with an uncertainty in the measured mass of 1.9% at 1σ, or a total time of 20 min with 1σ uncertainty in the measured mass of 2.5%.

46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND ↗

Action Sheet 55 Measurement Campaign Summary

Neutron collars have long been used by international inspectorates to determine the 235 U loading of fresh light water reactor (LWR) fuel in nuclear fuel fabrication facilities. Burnable poisons are strong thermal neutron absorbers that are frequently used to increase the lifetime of LWR fuel in a reactor. These poisons have made the traditionally thermal neutron collar measurements challenging because they force inspectors to rely on operator declarations of the burnable poison content of the fuel in order to correct for the decreased count rate caused by the added thermal neutron absorption of the poison. Work has been conducted internationally to try to eradicate the reliance on operator declarations. The Euratom Fast Collar for BWR Fuel (EFCB) is one promising technique to manage this issue.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

EURATOM Fast Collar for BWR (EFCB) Field Calibration Exercise

A neutron collar for the measurement of fresh BWR fuel assemblies (EFCB) has been designed and built by Los Alamos National Laboratory (LANL) and the Euratom Safeguards Directorate (Euratom). The design was similar to a previous collar designed for the measurement of fresh PWR assemblies. A key feature of both of these collars is that they operate in fast mode (preventing the return of thermal neutrons into the assembly by means of a cadmium liner) to reduce the effect of burnable poisons on the measurement. The current report describes the results of the field calibration exercise that was carried out at the ENUSA Fuel Fabrication Plant in Juzbado, Spain from May 28 to May 31, 2019.

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS↗

Scintillation detectors

Devices/apparatuses are disclosed that include a photoemitting component, a photosensitive component deposited on the photoemitting component, a charge collection component, and a hollow enclosure for housing the photoemitting component, the photosensitive component, the charge collection component, or combinations thereof. Methods for making and using the apparatuses are also disclosed.

Ianakiev, Kiril D.↗