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Description: The major objective of this program is to upgrade and replace instruments and equipment that significantly improve the performance, control and operational capability of the Purdue University nuclear reactor (PUR-1). Under this major objective one project on design and installation of interface cards for channel four detector was considered. This report is the final report and gives the efforts and progress achieved on these projects from August 2002 to July 2004.
Date: September 24, 2004
Creator: Revankar, S. T.
Partner: UNT Libraries Government Documents Department

LOFT Monthly Progress Report for April 1980

Description: During April, activities continued in preparation for Tests L6-5 and L3-7, currently scheduled for June 1 and June 23. April activities at the LOFT facility were particularly centered around the installation of new and improved instrumentation. During April, a new baseline budget was established for FY-1980, the third major change this fiscal year. This baseline plan reflects a revised test sequence and dates reflecting test needs (particularly instrumentation), and current funding. Costs to date are in good agreement with the current budgets and the authorized funding levels. During April, a revised budget was proposed for FY-1981 and a new budget was proposed for FY-1982. These budgets and their assumptions were presented to NRC in mid-year reviews and important decision elements were identified. A reorganization of the LOFT personnel was announced this month. The LOFT Experimental Program Division was replaced with the LOFT Program Division, managed by Dr. C. W. Solbrig, and with the LOFT Measurements Division, managed by D. J. Hanson.
Date: May 1, 1980
Creator: Kaufman, N. C.
Partner: UNT Libraries Government Documents Department

Studies in nondestructive testing with potential for in-service inspection of LMFBRs

Description: A variety of nondestructive examination techniques have been and are being developed at ORNL with potential for ISI in LMFBRs. Among these are radiographic techniques for radiation environment and image enhancement, advanced eddy-current techniques and equipment for flaw detection and thickness measurement and ISI of steam generator tubing, and ultrasonic methods for quantitative flaw evaluation using frequency-analysis and bore-side ultrasonic techniques for steam generator tubing. Further developments should result in positive application to ISI.
Date: January 1, 1976
Creator: McClung, R.W.
Partner: UNT Libraries Government Documents Department

Report on the Brookhaven Nuclear Reactor Prepared for Reactor Safeguard Committee of the Atomic Energy Commission

Description: This technical report provides a general description of the Brookhaven National Laboratory, describing the nuclear characteristics of the Brookhaven reactor and more detailed descriptions of the features and instrumentation of the reactor.
Date: June 22, 1948
Creator: Brookhaven National Laboratory
Partner: UNT Libraries Government Documents Department

Upgrade of the NCSU PULSTAR instrumentation power channels. Final technical report, September 1, 1992--August 31, 1994

Description: The Nuclear Reactor Program at North Carolina State University initiated an upgrade program at the NCSU PULSTAR Reactor in 1990. The originally supplied instrumentation has been replaced with solid-state and current technology equipment. The financial assistance from the US Department of Energy has been the primary source of support. This is the final report for the Instrumentation Upgrade.
Date: November 13, 1998
Creator: Perez, P. B.
Partner: UNT Libraries Government Documents Department

Cost-effective instrumentation and control upgrades for commercial nuclear power plants using surety principles developed at Sandia National Laboratories

Description: Many nuclear power plants use instrument and control systems based on analog electronics. The state of the art in process control and instrumentation has advanced to use digital electronics and incorporate advanced technology. This technology includes distributed microprocessors, fiber optics, intelligent systems (neural networks), and advanced displays. The technology is used to optimize processes and enhance the man-machine interface while maintaining control and safety of the processes. Nuclear power plant operators have been hesitant to install this technology because of the cost and uncertainty in the regulatory process. This technology can be directly applied in an operating nuclear power plant provided a surety principle-based {open_quotes}administrator{close_quotes} hardware system is included in parallel with the upgrade Sandia National Laboratories has developed a rigorous approach to High Consequence System Surety (HCSS). This approach addresses the key issues of safety, security, and control while satisfying requirements for reliability and quality. HCSS principles can be applied to nuclear power plants in a manner that allows the off-the-shelf use of process control instrumentation while maintaining a high level of safety and enhancing the plant performance. We propose that an HCSS administrator be constructed as a standardized approach to address regulatory issues. Such an administrator would allow a plant control system to be constructed with commercially available, state-of-the-art equipment and be customized to the needs of the individual plant operator.
Date: November 1, 1997
Creator: Rochau, G.E. & Dalton, L.J.
Partner: UNT Libraries Government Documents Department

Application of Microprocessor-Based Equipment in Nuclear Power Plants - Technical Basis for a Qualification Methodology

Description: This document (1) summarizes the most significant findings of the ''Qualification of Advanced Instrumentation and Control (I&C) Systems'' program initiated by the Nuclear Regulatory Commission (NRC); (2) documents a comparative analysis of U.S. and European qualification standards; and (3) provides recommendations for enhancing regulatory guidance for environmental qualification of microprocessor-based safety-related systems. Safety-related I&C system upgrades of present-day nuclear power plants, as well as I&C systems of Advanced Light-Water Reactors (ALWRs), are expected to make increasing use of microprocessor-based technology. The Nuclear Regulatory Commission (NRC) recognized that the use of such technology may pose environmental qualification challenges different from current, analog-based I&C systems. Hence, it initiated the ''Qualification of Advanced Instrumentation and Control Systems'' program. The objectives of this confirmatory research project are to (1) identify any unique environmental-stress-related failure modes posed by digital technologies and their potential impact on the safety systems and (2) develop the technical basis for regulatory guidance using these findings. Previous findings from this study have been documented in several technical reports. This final report in the series documents a comparative analysis of two environmental qualification standards--Institute of Electrical and Electronics Engineers (IEEE) Std 323-1983 and International Electrotechnical Commission (IEC) 60780 (1998)--and provides recommendations for environmental qualification of microprocessor-based systems based on this analysis as well as on the findings documented in the previous reports. The two standards were chosen for this analysis because IEEE 323 is the standard used in the U.S. for the qualification of safety-related equipment in nuclear power plants, and IEC 60780 is its European counterpart. In addition, the IEC document was published in 1998, and should reflect any new qualification concerns, from the European perspective, with regard to the use of microprocessor-based safety systems in power plants.
Date: August 24, 2001
Creator: Korsah, K.
Partner: UNT Libraries Government Documents Department

Time series analysis of nuclear instrumentation in EBR-II

Description: Results of a time series analysis of the scaler count data from the 3 wide range nuclear detectors in the Experimental Breeder Reactor-II are presented. One of the channels was replaced, and it was desired to determine if there was any statistically significant change (ie, improvement) in the channel`s response after the replacement. Data were collected from all 3 channels for 16-day periods before and after detector replacement. Time series analysis and statistical tests showed that there was no significant change after the detector replacement. Also, there were no statistically significant differences among the 3 channels, either before or after the replacement. Finally, it was determined that errors in the reactivity change inferred from subcritical count monitoring during fuel handling would be on the other of 20-30 cents for single count intervals.
Date: May 1, 1996
Creator: Imel, G.R.
Partner: UNT Libraries Government Documents Department

Effects of smoke on functional circuits

Description: Nuclear power plants are converting to digital instrumentation and control systems; however, the effects of abnormal environments such as fire and smoke on such systems are not known. There are no standard tests for smoke, but previous smoke exposure tests at Sandia National Laboratories have shown that digital communications can be temporarily interrupted during a smoke exposure. Another concern is the long-term corrosion of metals exposed to the acidic gases produced by a cable fire. This report documents measurements of basic functional circuits during and up to 1 day after exposure to smoke created by burning cable insulation. Printed wiring boards were exposed to the smoke in an enclosed chamber for 1 hour. For high-resistance circuits, the smoke lowered the resistance of the surface of the board and caused the circuits to short during the exposure. These circuits recovered after the smoke was vented. For low-resistance circuits, the smoke caused their resistance to increase slightly. A polyurethane conformal coating substantially reduced the effects of smoke. A high-speed digital circuit was unaffected. A second experiment on different logic chip technologies showed that the critical shunt resistance that would cause failure was dependent on the chip technology and that the components used in the smoke exposures were some of the most smoke tolerant. The smoke densities in these tests were high enough to cause changes in high impedance (resistance) circuits during exposure, but did not affect most of the other circuits. Conformal coatings and the characteristics of chip technologies should be considered when designing circuitry for nuclear power plant safety systems, which must be highly reliable under a variety of operating and accident conditions. 10 refs., 34 figs., 18 tabs.
Date: October 1997
Creator: Tanaka, T. J.
Partner: UNT Libraries Government Documents Department

Prometheus Reactor I&C Software Development Methodology, for Action

Description: The purpose of this letter is to submit the Reactor Instrumentation and Control (I&C) software life cycle, development methodology, and programming language selections and rationale for project Prometheus to NR for approval. This letter also provides the draft Reactor I&C Software Development Process Manual and Reactor Module Software Development Plan to NR for information.
Date: July 30, 2005
Creator: Hamilton, T.
Partner: UNT Libraries Government Documents Department

Plant Process Surveillance System for N Reactor systems study. Rev.1

Description: This Systems Study is submitted in accordance with the requirements of AEC Manual Chapter 1801, and proposes the procurement and implementation of a Plant Process Surveillance System for N Reactor. The envisioned system consists of instrumentation, data acquisition equipment, a digital computer, and input/output equipment. It is intended that the system will be a tool for reliable administration of safety limits and standards, simplification of plant operation, and reduction of operating costs by replacing the tasks of shift operations personnel, an instrument technician and a process engineer.
Date: November 8, 1969
Partner: UNT Libraries Government Documents Department
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