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Neutron induced current pulses in fission chambers. [LMFBR]

Description: The mechanism of neutron induced current pulse generation in fission chambers is discussed. By application of the calculated detector transfer function to proposed detector current pulse shapes, and by comparison with actually observed detector output voltage pulses, a credible, semi-empirical, trapezoidal pulse shape of chamber current is obtained.
Date: January 1, 1978
Creator: Taboas, A.L. & Buck, W.L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Radiochemical analysis of the first plateout probe from the Fort St. Vrain high-temperature gas-cooled reactor

Description: This report presents the analysis of radioactive elements on the first plateout probe from the Fort St. Vrain high-temperature gas-cooled reactor. The plateout probe is a device which samples the primary coolant for condensible fission products. Circuit inventories of individual radionuclides are estimated from the probe analysis. The analysis shows that the radioactive contamination in the primary circuit is remarkable low, with activation product concentrations much greater than that of fissi… more
Date: June 1, 1982
Creator: Burnette, R. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Reviewing the impact of advanced control room technology

Description: Progress to date on assessing the nature of the expected changes in human performance and risk associated with the introduction of digital control, instrumentation, and display systems is presented. Expected changes include the shift toward more supervisory tasks, development of intervention strategies, and reallocation of function between human and machine. Results are reported in terms of the scope of new technology, human performance issues, and crews experience with digital control systems … more
Date: January 1, 1992
Creator: Wilhelmsen, C. A.; Gertman, D. I.; Ostrom, L. T.; Nelson, W. R.; Galyean, W. J. & Byers, J. C.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Experimental results of direct containment heating by high-pressure melt ejection into the Surtsey vessel: The DCH-3 and DCH-4 tests

Description: Two experiments, DCH-3 and DCH-4, were performed at the Surtsey test facility to investigate phenomena associated with a high-pressure melt ejection (HPME) reactor accident sequence resulting in direct containment heating (DCH). These experiments were performed using the same experimental apparatus with identical initial conditions, except that the Surtsey test vessel contained air in DCH-3 and argon in DCH-4. Inerting the vessel with argon eliminated chemical reactions between metallic debris … more
Date: August 1, 1991
Creator: Allen, M.D.; Pilch, M.; Brockmann, J.E.; Tarbell, W.W. (Sandia National Labs., Albuquerque, NM (United States)); Nichols, R.T. (Ktech Corp., Albuquerque, NM (United States)) & Sweet, D.W. (AEA Technology, Winfrith (United Kingdom))
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Response of LOFT SPNDs to reactor coolant density variations during a LOCA simulation

Description: Analysis of self-powered neutron detector (SPND) data taken during loss-of-coolant experiment (LOCE) L2-3 conducted in the Loss-of-Fluid Test (LOFT) facility has shown that the detectors are sensitive, in a qualitative sense, to coolant density variations in the reactor core. These results provide a strong impetus for determining the applicability of self-powered nuclear flux detectors for liquid level measurement in the reactor vessel of a pressurized water reactor (PWR) during transient condi… more
Date: January 1, 1980
Creator: Adams, J.P. & Berta, V.T.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Transformer failure and common-mode loss of instrument power at Nine Mile Point Unit 2 on August 13, 1991

Description: On August 13, 1991, at Nine Mile Point Unit 2 nuclear power plant, located near Scriba, New York, on Lake Ontario, the main transformer experienced an internal failure that resulted in degraded voltage which caused the simultaneous loss of five uninterruptible power supplies, which in turn caused the loss of several nonsafety systems, including reactor control rod position indication, some reactor power and water indication, control room annunciators, the plant communications system, the plant … more
Date: October 1, 1991
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

User's guide for revised SPEC-4 neutron spectrum unfolding code

Description: The SPEC-4 computer code was developed in the United Kingdom to solve the spectrum unfolding problem for spherical gas-filled proton-recoil neutron spectrometers. This report describes the ORNL version of SPEC-4 which has been applied to the analysis of data from the Tower Shielding Facility. Recent modifications are described which largely pertain to the graphical output routines. In addition, the input requirements are presented in considerable detail including suggestions and recommendations… more
Date: August 1, 1980
Creator: Johnson, J.O. & Ingersoll, D.T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Meeting commercial reactor instrumentation needs

Description: Commercial nuclear reactors are instrumented for two reasons: (1) to provide information to the operators, and (2) to support automatic safety systems. The key questions the operators want answered are: Is the core being cooled and what is the temperature. Two instruments currently installed in LOFT are providing these answers. The commercial application of liquid level probes and fuel thermocouples will undoubtably bring argument from some quarters, but properly working instruments of their ty… more
Date: January 1, 1980
Creator: Stanley, M.L.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Treatment of measurement uncertainties at the power burst facility

Description: The treatment of measurement uncertainty at the Power Burst Facility provides a means of improving data integrity as well as meeting standard practice reporting requirements. This is accomplished by performing the uncertainty analysis in two parts, test independent uncertainty analysis and test dependent uncertainty analysis. The test independent uncertainty analysis is performed on instrumentation used repeatedly from one test to the next, and does not have to be repeated for each test except … more
Date: January 1, 1980
Creator: Meyer, L.C.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Barium silicate glass/Inconel X-750 interaction. [PWR]

Description: Water reactor safety programs at the Idaho National Engineering Laboratory have required the development of specialized instrumentation. An example is the electrical conductivity-sensitive liquid level transducer developed for use in pressurized-water reactors (PWRs) in which the operation of the sensing probe relies upon the passage of current through the water between the center pin of the electrode and its shell such that when water is present the resulting voltage is low, and conversely, wh… more
Date: January 1, 1980
Creator: Kelsey, P.V. Jr.; Siegel, W.T. & Miley, D.V.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Severe accident testing of electrical penetration assemblies

Description: This report describes the results of tests conducted on three different designs of full-size electrical penetration assemblies (EPAs) that are used in the containment buildings of nuclear power plants. The objective of the tests was to evaluate the behavior of the EPAs under simulated severe accident conditions using steam at elevated temperature and pressure. Leakage, temperature, and cable insulation resistance were monitored throughout the tests. Nuclear-qualified EPAs were produced from D. … more
Date: November 1, 1989
Creator: Clauss, D.B. (Sandia National Labs., Albuquerque, NM (USA))
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Fast Flux Test Facility loose-parts monitor

Description: This paper summarizes the development testing in progress at the FFTF to determine the effectiveness of high temperature microphones as acoustic monitors in the upper plenum of the FFTF. The specific goal of this testing is development of an automated loose parts monitor for the upper plenum. A description of the acoustic probe is included, as well as a discussion of the signal processing. A summary of the results to date is also given.
Date: February 1, 1982
Creator: Sloan, W.R.; King, D.C. & Robles, M.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Torsional ultrasonic technique for reactor vessel liquid level measurement

Description: We have undertaken a detailed study of an ultrasonic waveguide employed as a level, density, and temperature sensor. The purpose of this study was to show how such a device might be used in the nuclear power industry to provide reliable level information with a multifunction sensor, thus overcomming several of the errors that led to the accident at Three Mile Island. Some additional work is needed to answer the questions raised by the current study, most noticably the damping effects of flowing… more
Date: January 1, 1983
Creator: Dress, W. B.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

LOFT differential pressure uncertainty analysis

Description: A performance analysis of the LOFT differential pressure (..delta..P) measurement is presented. Along with completed descriptions of test programs and theoretical studies that have been conducted on the ..delta..P, specific sources of measurement uncertainty are identified, quantified, and combined to provide an assessment of the ability of this measurement to satisfy the SDD 1.4.1C (June 1975) requirement of measurement of differential pressure.
Date: March 1, 1977
Creator: Evans, R.P.; Biladeau, G.L. & Quinn, P.A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Feasibility of using a conductivity or ultrasonic type detector to measure void fraction in the LOFT reactor core inlet and outlet

Description: The feasibility of a conductivity or ultrasonic type detector meeting the LOFT reactor core inlet and outlet void fraction measurement requirements is explored. The tests that were performed to evaluate the existing LOFT liquid level detector electrode configuration as a conductivity void fraction detector and a prototype ultrasonic detector (fabricated by Panametrics, Inc.) are described. The results of these tests and the recommendations for improving the performance of each detector system a… more
Date: January 1, 1978
Creator: Buchanan, M.E. & Shurtliff, R.W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Detection of sensor failures in nuclear plants using analytic redundancy

Description: A method for on-line, nonperturbative detection and identification of sensor failures in nuclear power plants was studied to determine its feasibility. This method is called analytic redundancy, or functional redundancy. Sensor failure has traditionally been detected by comparing multiple signals from redundant sensors, such as in two-out-of-three logic. In analytic redundancy, with the help of an assumed model of the physical system, the signals from a set of sensors are processed to reproduce… more
Date: January 1, 1980
Creator: Kitamura, M.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

275/sup 0/C thick-film hybrid microcircuitry fabrication technology

Description: High-temperature electronics is needed for geothermal well-logging tools, jet engine monitors, nuclear reactor instruments, and fossil fuel exploration and production systems. The step-by-step fabrication technology of thick-film hybrids useful for at least 1000 hours at 275/sup 0/C is described. Hybrid technology, qualified to standard military specifications, was modified both in materials and fabrication processes to achieve this high-temperature operation. In addition to documenting this Sa… more
Date: July 1, 1980
Creator: Bonn, P.A. & Palmer, D.W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Spectrum-transformed sequential testing method for signal validation applications

Description: The Sequential Probability Ratio Test (SPRT) has proven to be a valuable tool in a variety of reactor applications for signal validation and for sensor and equipment operability surveillance. One drawback of the conventional SPRT method is that its domain of application is limited to signals that are contaminated by gaussian white noise. Nongaussian process variables contaminated by serial correlation can produce higher-than-specified rates of false alarms and missed alarms for SPRT-based surve… more
Date: January 1, 1992
Creator: Gross, K.C. (Argonne National Lab., IL (United States)) & Hoyer, K.K. (Northwestern Univ., Evanston, IL (United States). Dept. of Industrial Engineering and Management Sciences)
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Accuracy of various alternate methods of calculating total mass flow rate for PKL instrumented pipe spool prototype tests in single- and two-phase steam-water flows

Description: Instrumented spool pieces for installation in the piping of the German Primarkreislauf (PKL) test reactor have been designed and tested. The primary objective of the spools is to provide measurements of two-phase steam-water flow parameters (pressure, temperature, velocity) from which mass flow rates can be calculated. Each spool contains a three-beam densitometer, flow turbine, drag screen, and pressure and temperature sensors. The spools were prototype tested in single- and two-phase steam-wa… more
Date: December 1, 1979
Creator: Stein, W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

HTGR Safety Research at the Los Alamos National Laboratory

Description: This paper summarizes activities undertaken at the Los Alamos National Laboratory as part of the High-Temperature Gas-Cooled Reactor (HTGR) Safety Research Program sponsored by the US Nuclear Regulatory Commission. Technical accomplishments and analysis capabilities in six broad-based task areas are described. These tasks are: fission-product technology, primary-coolant impurities, structural investigations, safety instrumentation and control systems, accident delineation, and phenomena modelin… more
Date: January 1, 1982
Creator: Stroh, K. R.; Anderson, C. A. & Kirk, W. L.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Theoretical characterization of a dual-purpose gamma thermometer for local power-generation measurement in an LMFBR

Description: A preliminary analytical and computational study was performed to investigate the potential of a modified gamma thermometer (GT) as both a local power level monitor and a sodium flow blockage monitor for a Liquid Metal Fast Breeder Reactor. This study consisted of two fundamental parts: a radiation field characterization and a thermal-hydraulic analysis. The radiation transport analysis was performed to determine the volumetric heat source within the GT resulting from gamma and neutron heating.… more
Date: April 1, 1982
Creator: Johnson, J. O. & Burns, T. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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