8 research outputs found
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ION-1 technical manual
The portable gamma-ray and neutron detector electronics (ION-1) gives a digital readout of the current-mode response produced by gamma rays in an ion chamber and of amplification and scaling of pulses received from a neutron detector. The primary application is the measurement of gamma-ray and neutron activity of irradiated reactor fuels stored at a reactor or at a storage pond away from a reactor. ION-1 is the first such instrument to use a design that allows communication of procedures, response, and results between instrument and inspector. It prompts the inspector through procedures, carries out programmed measurement steps, calculates results and error estimates, and performs internal diagnostic checks. This Technical Manual describes adjustment procedures and limited technical information that enable the inspector to troubleshoot at the board level. 5 figs., 10 tabs
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General-purpose microprocessor-based control chassis
The objective of the Pion Generation for Medical Irradiations (PIGMI) program at the Los Alamos Scientific Laboratory is to develop the technology to build smaller, less expensive, and more reliable proton linear accelerators for medical applications. For this program, a powerful, simple, inexpensive, and reliable control and data acquisition system was developed. The system has a NOVA 3D computer with a real time disk-operating system (RDOS) that communicates with distributed microprocessor-based controllers which directly control data input/output chassis. At the heart of the controller is a microprocessor crate which was conceived at the Fermi National Accelerator Laboratory. This idea was applied to the design of the hardware and software of the controller
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Data acquisition and command system for use with a microprocessor-based control chassis. [PIGMI-Pion Generation for Medical Irradiations]
The Pion Generation for Medical Irradiations (PIGMI) program at the Los Alamos Scientific Laboratory is developing the technology to build smaller, less expensive, and more reliable proton linear accelerators for medical applications, and has designed a powerful, simple, inexpensive, and reliable control and data acquisition system that is central to the program development. The system is a NOVA-3D minicomputer interfaced to several outlying microprocessor-based controllers, which accomplish control and data acquisition through data I/O chasis. The equipment interface chassis, which can issue binary commands, read binary data, issue analog commands, and read timed and untimed analog data is described
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Nondestructive measurement of spent fuel assemblies at the Tokai Reprocessing and Storage Facility. [TASTEX program]
Nondestructive verification of irradiated fuel assemblies is an integral part of any safeguards system for a reprocessing facility. Available techniques are discussed with respect to the level of verification provided by each. A combination of high-resolution gamma spectrometry, neutron detectors, and gross gamma activity profile monitors provide a maximum amount of information in a minimum amount of time
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Application of nondestructive gamma-ray and neutron techniques for the safeguarding of irradiated fuel materials
Nondestructive gamma-ray and neutron techniques were used to characterize the irradiation exposures of irradiated fuel assemblies. Techniques for the rapid measurement of the axial-activity profiles of fuel assemblies have been developed using ion chambers and Be(..gamma..,n) detectors. Detailed measurements using high-resolution gamma-ray spectrometry and passive neutron techniques were correlated with operator-declared values of cooling times and burnup
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New development in nondestructive measurement and verification of irradiated LWR fuels
Nondestructive techniques for characterizing irradiated LWR fuel assemblies are discussed. This includes detection systems that measure the axial activity profile, neutron yield and gamma yield. A multi-element profile monitor has been developed that offers a significant improvement in speed and complexity over existing mechanical scanning systems. New portable detectors and electronics, applicable to safeguard inspection, are presented and results of gamma-ray and neutron measurements at commercial reactor facilities are given