Journal Article10.1109/TNS.1973.4327174
A Modular Control System Utilizing CAMAC Hardware for Interfacing Remote Components at NAL
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TL;DR: This link allows data to be transferred from devices into memory at a 40 KHz word rate independent of programmed instructions, thus allowing the normal operating program and serial data link to function uninterrupted.
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Abstract: Introduction The execution of a data transfer on this link is initiated by a command function on the standard data link. The MDC receiver, upon receipt of a 16 bit data word, will send a service request to the MDC which idles the CPU between instructions, initiates a read cycle, and stores the word in mIemory. The operating program automatically resumes execution after each request is serviced. Upon receipt of the prescribed number of data words in memory, the computer is automatically interrupted to process the data. This link allows data to be transferred from devices into memory at a 40 KHz word rate independent of programmed instructions, thus allowing the normal operating program and serial data link to function uninterrupted. Figure 1 is a block diagram of the 8 GeV/Switchyard Control System. The diversification and physical remoteness of components constituting the NAL proton beam switchyard and site-wide fire detection systems necessitated the use of mini-computers to centralize monitoring and control. Devices are interfaced to the computers by series connected local controllers. The local controllers utilize a standard CAMAC crate with a simplified dataway to achieve economic modular construction. Serial data transfers are used between controllers for reliable operation in a high noise environment. Bulk data transfers to the Switchyard System Computer are implemented on a special high speed serial link which operates independent of, but initiated by, the local controllers. A special Minicontroller module with an emergency back-up power source is used to monitor NAL fire detection
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Nuclear Instruments and Methods
João B. Manteigas
- 01 Jan 2004
TL;DR: In this paper, the MCNP code is used to calculate the pertubation of the neutron thermal flux by a sample in the presence of a moderator Monte Carlo calculations have been carried out in the field of the projects PDCT/FP/FNU/50276/2003, and Preliminary design of an Accelerator Driven System- PDS-XADS_FIS2001-00089.