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The development of code inservice inspection (ISI) requirements for Low Temperature Heavy Water Reactors (LTHWR)

Description: DOE Savannah River Field office requested that the American Society of Mechanical Engineers (ASME) develop rules for inservice inspection (ISI) of Savannah River Site (SRS) Low Temperature Heavy Water Reactors (LTHWR's) in January 1990. The request is part of the SRS Reactor Safety Improvement Program (RSIP). RSIP will implement an ASME B PV Code Section XI based ISI program after restart of K Reactor. The establishment of a Code based ISI program at SRS will affect a transition from a standing… more
Date: January 1, 1992
Creator: Cowfer, C.D.
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Partner: UNT Libraries Government Documents Department
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Savannah River Laboratory monthly report, February 1992

Description: This report is a progress report for the Savannah River Laboratory for the month of February 1992. The progress and activities in six categories were described in the report. The categories are reactor, tritium, separations, environmental, waste management, and general. Each category described numerous and varied activities. Some examples of these activities described are such things as radiation monitoring, maintenance, modifications, and remedial action.
Date: February 1, 1992
Creator: Ferrell, J.M. (comp.) & Ice, L.W. (ed.)
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Lecture notes for introduction to nuclear engineering 101

Description: The lecture notes for introductory nuclear engineering are provided for Department of Energy personnel that are recent graduates, transfers from non-nuclear industries, and people with minimum engineering training. The material assumes a knowledge of algebra and elementary calculus. These notes support and supplement a three-hour lecture. The reader is led into the subject from the familiar macroscopic world to the microscopic world of atoms and the parts of atoms called elementary particles. O… more
Date: March 1, 1992
Creator: Fullwood, R. & Cadwell, J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Rcs Pressure Under Reduced Inventory Conditions Following a Loss of Residual Heat Removal

Description: The thermal-hydraulic response of a closed-reactor coolant system to loss of residual heat removal (RHR) cooling is investigated. The processes examined include: core coolant boiling and steam generator reflux condensation, pressure increase on the primary side, heat transfer mechanisms on the steam generator primary and secondary sides, and effects of noncondensible gas on heat transfer processes.
Date: January 1, 1992
Creator: Palmrose, D. E.; Hughes, E. D. & Johnsen, G. W.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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A review of the U sub 3 O sub 8 -aluminum reaction as a potential heat source in research and test reactor accidents

Description: A critical review of the literature on the U{sub 3}O{sub 8}-aluminum reaction has been conducted. The reaction in fabricated fuel plates is found to be less energetic and much slower than in cold-pressed powder mixtures. The difference is at least partially attributable to conversion of up to 50% of the U{sub 3}O{sub 8} to U{sub 4}O{sub 9} during fabrication. No definitive measurements of the amount and rate of energy release have been made. Data are provided upon which to base calculations of … more
Date: January 1, 1992
Creator: Snelgrove, J.L.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Correlation of analysis with high level vibration test results for primary coolant piping

Description: Dynamic tests on a modified 1/2.5-scale model of pressurized water reactor (PWR) primary coolant piping were performed using a large shaking table at Tadotsu, Japan. The High Level Vibration Test (HLVT) program was part of a cooperative study between the United States (Nuclear Regulatory Commission/Brookhaven National Laboratory, NRC/BNL) and Japan (Ministry of International Trade and Industry/Nuclear Power Engineering Center). During the test program, the excitation level of each test run was … more
Date: January 1, 1992
Creator: Park, Y.J.; Hofmayer, C.H. (Brookhaven National Lab., Upton, NY (United States)) & Costello, J.F. (Nuclear Regulatory Commission, Washington, DC (United States))
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Partner: UNT Libraries Government Documents Department
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WSRC Reactor Tank Inspection Program (RTIP) status report

Description: Westinghouse Savannah River Company (WSRC) recently completed the initial phase of nondestructive inspections of the Savannah River Site's (SRS) reactor tanks. This program required almost three years to be conceptualized, fabricated, and tested. An additional 20 months were required to complete the NDE inspection of the P, K and L reactor tanks. The overall cost of the program to date is approximately $25 MM. This status report will address: (1) A brief review of the RTIP program and the const… more
Date: January 1, 1992
Creator: Loibl, M. W.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Chemical Technology Division, Annual technical report, 1991

Description: Highlights of the Chemical Technology (CMT) Division's activities during 1991 are presented. In this period, CMT conducted research and development in the following areas: (1) electrochemical technology, including advanced batteries and fuel cells; (2) technology for fluidized-bed combustion and coal-fired magnetohydrodynamics; (3) methods for treatment of hazardous and mixed hazardous/radioactive waste; (4) the reaction of nuclear waste glass and spent fuel under conditions expected for an uns… more
Date: March 1, 1992
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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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)
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Partner: UNT Libraries Government Documents Department
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Soil-structure interaction effects for laterally excited liquid-tank system

Description: Following a brief review of the mechanical model for liquid-storage tanks which permits consideration of the effects of tank and ground flexibility, and lateral and rocking base excitations, the effects of both kinematic and inertia interaction effects on the response of the tank-liquid system are examined and elucidated. The free-field motion is defined by a power spectral density function and an incoherence function, which characterizes the spatial variability of the ground motion due to the … more
Date: January 1, 1992
Creator: Tang, Yu (Argonne National Lab., IL (United States)) & Veletsos, A.S. (Rice Univ., Houston, TX (United States). Dept. of Civil Engineering)
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Aging assessment of Residual Heat Removal systems in Boiling Water Reactors

Description: The effects of aging on Residual Heat Removal systems in Boiling Water Reactors have been studied as part of the Nuclear Plant Aging Research Program. The aging phenomena has been characterized by analyzing operating experience from various national data bases. In addition, actual plant data was obtained to supplement and validate the data base findings.
Date: January 1, 1992
Creator: Lofaro, R. J. & Aggarwal, S.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Evaluation of seismic interactions: Guidelines and application

Description: It is readily recognized that a significant source of damage from earthquakes is due to interactions between structures and components, such as the fall of a masonry wall or a ceiling on equipment, or the impact of a valve on a wall or structure. There are also other significant, while less intuitively evident, sources of seismic interaction damage, such as flooding, spraying, fires, or electrical shorts. The understanding of all these sources of interaction damage and their evaluation in the f… more
Date: January 1, 1992
Creator: Antaki, G. A.; Flanders, H. E. & Thomas, B. D.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Tensile and burst tests in support of the cadmium safety rod failure evaluation

Description: The reactor safety rods may be subjected to high temperatures due to gamma heating after the core coolant level has dropped during the ECS phase of hypothetical LOCA event. Accordingly, an experimental safety rod testing subtask was established as part of a task to address the response of reactor core components to this accident. This report discusses confirmatory separate effects tests conducted to support the evaluation of failures observed in the safety rod thermal tests. As part of the fail… more
Date: February 1, 1992
Creator: Thomas, J.K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Thermal-hydraulic and structural considerations on the gap variation between fuel bundle and hexcan

Description: One of the safety concerns in reactor operation is the temperature of the fuel elements, which are contained in a hexagonal duct, referred to as the hexcan. There are gaps between the fuel bundle and the hexcan, and the gaps somewhat affect thermal-hydraulic behavior of the fuel element. This paper investigates the impact of gap variations on the thermal-hydraulic responses of the fuel element as well as the possibility of fuel bundle and hexcan interaction. The gap variation between hex duct a… more
Date: January 1, 1992
Creator: Chang, L. K.; Lee, M. J. & Ku, J. Y.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Comparison of two inductive learning methods: A case study in failed fuel identification

Description: Two inductive learning methods, the ID3 and Rg algorithms, are studied as a means for systematically and automatically constructing the knowledge base of expert systems. Both inductive learning methods are general-purpose and use information entropy as a discriminatory measure in order to group objects of a common class. ID3 constructs a knowledge base by building decision trees that discriminate objects of a data set as a function of their class. Rg constructs a knowledge base by grouping obje… more
Date: January 1, 1992
Creator: Reifman, J. (Argonne National Lab., IL (United States)) & Lee, J.C. (Michigan Univ., Ann Arbor, MI (United States). Dept. of Nuclear Engineering)
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Beam characterization at the Neutron Radiography Facility (NRAD)

Description: An ongoing project to characterize the neutron beams at the Neutron Radiography Reactor (NRAD) is described in this paper. The effort has consisted of computer modelling with three dimensional diffusion theory to obtain a trail spectrum, foil activation measurements, and the use of SAND-II unfolding code. It was expected and found that diffusion theory will underpredict the fast flux. However, it is claimed that precise characterization of the entire spectrum is not necessary for comparisons am… more
Date: January 1, 1992
Creator: Imel, G.R. & Urbatsch, T.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Mechanical tests for validation of seismic isolation elastomer constitutive models

Description: High damping laminated elastomeric bearings are becoming the preferred device for seismic isolation of large buildings and structures, such as nuclear power plants. The key component of these bearings is a filled natural rubber elastomer. This material exhibits nonlinear behavior within the normal design range. The material damping cannot be classified as either viscous or hysteritic, but it seems to fall somewhere in between. This paper describes a series of tests that can be used to character… more
Date: January 1, 1992
Creator: Kulak, R.F. & Hughes, T.H.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Nuclear Regulatory Commission Information Digest 1992 edition. Volume 4

Description: The Nuclear Regulatory Commission Information Digest provides a summary of information about the US Nuclear Regulatory Commission (NRC), NRC's regulatory responsibilities, the activities NRC licenses, and general information on domestic and worldwide nuclear energy. This digest is a compilation of nuclear- and NRC-related data and is designed to provide a quick reference to major facts about the agency and industry it regulates. In general, the data cover 1975 through 1991, with exceptions note… more
Date: March 1, 1992
Creator: Olive, K
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Hanford production reactor heat releases 1951--1971

Description: The purpose of this report is to document and detail the thermal releases from the Hanford nuclear production reactors during the period 1951 through 1971, and to put these releases in historical perspective with respect to changing Columbia River flows and temperatures. This information can also be used as a foundation for further ecological evaluations. When examining Hanford production reactor thermal releases to the Columbia River all related factors affecting the releases and the character… more
Date: April 1, 1992
Creator: Kannberg, L.D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Phase distribution measurements in narrow rectangular channels using image-processing techniques

Description: Phase distribution of air-water flow in a narrow rectangular channel is examined using image-processing techniques. Ink is added to the water, and clear channel walls were used to allow high-speed, still photographs and video tape to be taken of the air-water flow field. Flow field images are digitized and stored in a Macintosh IIci computer using a frame grabber board. Local grey levels are related to liquid thickness in the flow channel using a calibration fixture. Image-processing shareware … more
Date: June 1, 1992
Creator: Bentley, C. L. & Ruggles, A. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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PHEBUS on-line aerosol monitor development test program

Description: EG G Idaho, Inc. developed an on-line aerosol monitor (OLAM) for the French PHEBUS Fission Product Project. Part of the development was to manufacture and test an OLAM prototype. This report presents the results of the testing which determined the mechanical integrity of the monitor at operating temperature and pressure and performed a preliminary test of the optical system. A series of twenty different tests was conducted during the prototype testing sequence. Since no leaks were detected, the… more
Date: March 1, 1992
Creator: Sprenger, M. H. & Pentecost, C. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Packed bed reactor treatment of liquid hazardous and mixed wastes

Description: We are developing thermal-based packed bed reactor (PBR) technology as an alternative to incineration for treatment of hazardous organic liquid wastes. The waste streams targeted by this technology are machining fluids contaminated with chlorocarbons and/or chlorofluorocarbons and low levels of plutonium or tritium The PBR offers several distinct advantages including simplistic design, rugged construction, ambient pressure processing, economical operations, as well as ease of scalability and ma… more
Date: January 1, 1992
Creator: Tennant, R.A.; Wantuck, P.J. & Vargas, R.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Effect of component aging on PWR control rod drive systems

Description: An aging assessment of PWR control rod drive (CRD) systems has been completed as part of the US NRC Nuclear Plant Aging Research (NPAR) Program. The design, construction, maintenance, and operation of the Babcock Wilcox (B W), Combustion Engineering (CE), and Westinghouse (W) systems were evaluated to determine the potential for degradation as each system ages. Operating experience data were evaluated to identify the predominant failure modes, causes, and effects. This, coupled with an assessme… more
Date: January 1, 1992
Creator: Grove, E.; Gunther, W. & Sullivan, K.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Life testing of a low voltage air circuit breaker

Description: A DS-416 low voltage air circuit breaker manufactured by Westinghouse was mechanically cycled to identify age-related degradation in the various breaker subcomponents, specifically the power-operated mechanism. This accelerated aging test was performed on one breaker unit for over 36,000 cycles. Three separate pole shafts, one with a 60-degree weld, one with a 120-degree weld, and one with a 180-degree weld in the third pole lever were used to characterize cracking in the welds. In addition, du… more
Date: January 1, 1992
Creator: Subudhi, M. (Brookhaven National Lab., Upton, NY (United States)) & Aggarwal, S. (Nuclear Regulatory Commission, Washington, DC (United States))
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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