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Computerized 50 liter volume calibration system

Description: A system has been designed for the Savannah River Site that will be used to calibrate product shipping containers. For accountability purposes, it is necessary that these containers be calibrated to a very high precision. The Computerized 50 Liter Volume Calibration System (CVCS), which is based on the Ideal Gas Law (IGL), will use reference volumes with precision of no less {plus minus}0.03%, and helium to calibrate the containers to have a total error of no greater than {plus minus}0.10%. A statistical interpretation of the system has given a theoretical total calculated error of {plus minus}0.08%. Tests with the system will be performed once fabrication is complete to experimentally verify the calculated error. Since the total error was calculated using the worst case scenario, the actual error should be significantly less than the calculated value. The computer controlled, totally automated system is traceable to the National Institute of Standards and Technology. The design, calibration procedure, and statistical interpretation of the system will be discussed. 1 ref.
Date: January 1, 1990
Creator: Proffitt, T.H.

TMI-2 lower head creep rupture analysis

Description: The TMI-2 accident resulted in approximately 40% of the reactor's core melting and collecting on the lower head of the reactor pressure vessel. The severity of the accident has raised questions about the margin of safety against rupture of the lower head in this accident since all evidence seems to indicate no major breach of the vessel occurred. Scoping heat transfer analyses of the relocated core debris and lower head have been made based upon assumed core melting scenarios and core material debris formations while in contact with the lower head. This report describes the structural finite element creep rupture analysis of the lower head using a temperature transient judged most likely to challenge the structural capacity of the vessel. This evaluation of vessel response to this transient has provided insight into the creep mechanisms of the vessel wall, a realistic mode of failure, and a means by which margin to failure can be evaluated once examination provides estimated maximum wall temperatures. Suggestions for more extensive research in this area are also provided. 6 refs., 15 figs.
Date: August 1, 1988
Creator: Thinnes, G.L.

(Evaluations of neutron reactions with sup 52 Cr, sup 56 Fe, sup 58 Ni)

Description: The traveler organized and chaired the meeting of the NEANDC/NEACRP Nuclear Data Evaluation Cooperation Subgroup-I: Intercomparison of USA, European, and Japanese Evaluations for {sup 52}Cr, {sup 56}Fe, and {sup 58}Ni, held on December 3, 1990, at the NEA Data Bank in Saclay, France. The traveler held discussions with Subgroup-II members to keep track of the activities of this group in which the traveler is a member. Highlights and/or recommendations of these meetings, as well as observations of the EAF, EFF, and JEF meetings, are included in this report.
Date: December 21, 1990
Creator: Fu, C.Y.

Considerations of beta and electron transport in internal dose calculations

Description: Ionizing radiation has broad uses in modern science and medicine. These uses often require the calculation of energy deposition in the irradiated media and, usually, the medium of interest is the human body. Energy deposition from radioactive sources within the human body and the effects of such deposition are considered in the field of internal dosimetry. In July of 1988, a three-year research project was initiated by the Nuclear Engineering Department at Texas A M University under the sponsorship of the US Department of Energy. The main thrust of the research was to consider, for the first time, the detailed spatial transport of electron and beta particles in the estimation of average organ doses under the Medical Internal Radiation Dose (MIRD) schema. At the present time (December of 1990), research activities are continuing within five areas. Several are new initiatives begun within the second or third year of the current contract period. They include: (1) development of small-scale dosimetry; (2) development of a differential volume phantom; (3) development of a dosimetric bone model; (4) assessment of the new ICRP lung model; and (5) studies into the mechanisms of DNA damage. A progress report is given for each of these tasks within the Comprehensive Report. In each use, preliminary results are very encouraging and plans for further research are detailed within this document. 22 refs., 13 figs., 1 tab.
Date: December 1, 1990
Creator: Bolch, W.E. & Poston, J.W. Sr. (Texas A and M Univ., College Station, TX (USA). Dept. of Nuclear Engineering)

The role of microstructural phenomena in magnetic thin films

Description: This progress report discusses two areas of research, namely the sputtering of Co-Ni-Cr films onto single crystal underlayers and the production of Co-Sm thin films with high coercivity. Included are a listing of papers submitted for publication, proposed research for year II (August 1991--July 1992), and the year II budget. (JDL)
Date: January 1, 1990
Creator: Laughlin, D.E. & Lambeth, D.N.

Simplified containment event tree analysis for the Sequoyah Ice Condenser containment

Description: An evaluation of a Pressurized Water Reactor (PWR) ice condenser containment was performed. In this evaluation, simplified containment event trees (SCETs) were developed that utilized the vast storehouse of information generated by the NRC's Draft NUREG-1150 effort. Specifically, the computer programs and data files produced by the NUREG-1150 analysis of Sequoyah were used to electronically generate SCETs, as opposed to the NUREG-1150 accident progression event trees (APETs). This simplification was performed to allow graphic depiction of the SCETs in typical event tree format, which facilitates their understanding and use. SCETs were developed for five of the seven plant damage state groups (PDSGs) identified by the NUREG-1150 analyses, which includes: both short- and long-term station blackout sequences (SBOs), transients, loss-of-coolant accidents (LOCAs), and anticipated transient without scram (ATWS). Steam generator tube rupture (SGTR) and event-V PDSGs were not analyzed because of their containment bypass nature. After being benchmarked with the APETs, in terms of containment failure mode and risk, the SCETs were used to evaluate a number of potential containment modifications. The modifications were examined for their potential to mitigate or prevent containment failure from hydrogen burns or direct impingement on the containment by the core, (both factors identified as significant contributors to risk in the NUREG-1150 Sequoyah analysis). However, because of the relatively low baseline risk postulated for Sequoyah (i.e., 12 person-rems per reactor year), none of the potential modifications appear to be cost effective. 15 refs., 10 figs. , 17 tabs.
Date: December 1, 1990
Creator: Galyean, W.J.; Schroeder, J.A. & Pafford, D.J. (EG and G Idaho, Inc., Idaho Falls, ID (USA))

Fielding The Automated Container Offering System: An interim report

Description: The Automated Container Offering System (TACOS) is a cargo booking assistant currently being fielded in the International Traffic Directorate of the Military Traffic Management Command (MTMC). The expert system automates the selection process for type and size of SEAVAN containers, ports, carrier, and ship for containerized military cargo moving from the continental US to Europe. It is designed to perform all processing on simple cases and provide assistance to the human booker on complex cases. MTMC processes requests for {approximately}1000 containers per week on these routes. This paper is a case history which describes factors guiding development of TACOS to illustrate several themes which occur in other (military) logistics expert system projects.
Date: January 1, 1990
Creator: Dixon, B. (EG and G Idaho, Inc., Idaho Falls, ID (USA)); Rochette, D. (Army Artificial Intelligence Center, Washington, DC (USA)) & Crandell, J. (Military Traffic Management Command, Falls Church, VA (USA))

The development of an ultra-low-emission gas-fired combustor for space heaters

Description: An ultra-low-emission as-fired combustor has been developed for relatively low-temperature direct-air heating applications. High-lean premixed cyclonic combustion with a flame stabilizer is employed to achieve ultra-low emissions and high turndown operation. On the basis of analytical studies and cold modeling a 350-kW test combustor was designed and successfully tested. Experimental results obtained using natural gas and ambient air demonstrated that the test combustor can operate steadily at high excess air up to 80% to 100% over a large turndown range up to 40:1. At design operating conditions, NO{sub x} emissions as low as 0.6 vppm and CO and total hydrocarbon (THC) emissions below 3 vppm were achieved. Over the full operating range, NO{sub x} emissions from 0.3 to 1.0 vppm and CO and THC emissions below 4 vppm were demonstrated. In all tests, concentrations of NO{sub 2} were less than 40% of the total NO{sub 2} emissions from combustion processes required for good indoor air quality (0.5 vppm). This paper presents the concept of high-lean premixed ultra-low-emission cyclonic combustion, design specifications for the combustion system, and the major experimental results, including flame stability, emissions, and turndown performance. 15 refs., 10 figs., 1 tab.
Date: January 1, 1991
Creator: Xiong, Tian-yu; Khinkis, M.J. (Institute of Gas Technology, Chicago, IL (United States)) & Coppin, W.P. (Maxon Corp., Muncie, IN (United States))

Technical specification for the Product Evaluation Management Information System (PREMIS) Version 1. 1. 2

Description: This document contains the technical specifications and implementation details for the Product Evaluation Management Information System (PREMIS) Version 1.1.2. This document does not include the requirements analysis or design information and is not intended as a user's guide. The INGRES Applications-by-Forms (ABF) software development tool was used to specify and define the modules and screens which comprise the PREMIS application. Several external procedures are called by the ABF procedures; these have been written in VAX/VMS DCL (Digital Command Language) and SQL (Standard Query Language). These specifications together with the PREMIS information model and corresponding database definition constitute the PREMIS Version 1.1.2 technical specification and implementation description presented herein.
Date: June 1, 1990
Creator: Eaton, D.S.; Hall, R.C.; Orman, J.L. & Klamerus, J.

Project Management Plan

Description: The mission of the Uranium Mill Tailings Remedial Action (UMTRA) Project is explicitly stated and directed in the Uranium Mill Tailings Radiation Control Act of 1978, Public Law 95-604, 42 USC 7901 (hereinafter referred to as the Act''). Title I of the Act authorizes the Department of Energy (DOE) to undertake remedial actions at 24 designated inactive uranium processing sites and associated vicinity properties containing uranium mill tailings and other residual radioactive materials derived from the processing sites. The Act, amended in January 1983, by Public Law 97-415, also authorizes DOE to perform remedial actions at vicinity properties in Edgemont, South Dakota. Cleanup of the Edgemont processing site is the responsibility of the Tennessee Valley Authority. This document describes the plan, organization, system, and methodologies used to manage the design, construction, and other activities required to clean up the designated sites and associated vicinity properties in accordance with the Act. The plan describes the objectives of the UMTRA Project, defines participants' roles and responsibilities, outlines the technical approach for accomplishing the objectives, and describes the planning and managerial controls to be used in integrating and performing the Project mission. 21 figs., 21 tabs.
Date: January 1, 1988
Creator: Available, Not