This document provides recommendations to guide reviewers in the application of Programmable Logic Controllers (PLCS) to the control, monitoring and protection of nuclear reactors. The first topics addressed are system-level design issues, specifically including safety. The document then discusses concerns about the PLC manufacturing organization and the protection system engineering organization. Supplementing this document are two appendices. Appendix A summarizes PLC characteristics. Specifically addressed are those characteristics that make the PLC more suitable for emergency shutdown systems than other electrical/electronic-based systems, as well as characteristics that improve reliability of a system. Also covered are PLC characteristics that may create an unsafe operating environment. Appendix B provides an overview of the use of programmable logic controllers in emergency shutdown systems. The intent is to familiarize the reader with the design, development, test, and maintenance phases of applying a PLC to an ESD system. Each phase is described in detail and information pertinent to the application of a PLC is pointed out.

Dr. John W. Gofman was interviewed by representatives of US DOE Office of Human Radiation Experiments (OHRE) concerning his research at the University of California, Berkeley and his biomedical work at Lawrence Livermore Radiation Laboratory. Following a short biographical sketch, Dr. Gofman relates his remembrances with the discovery and chemistry of uranium-233, the Manhattan project, laboratory production of the first milligram of plutonium, pre-1945 medical use of high-dosage radiation, medical treatments with phosphorus 32, and fallout. Dr. Gofman also discusses his relationships with Professor Oppenheimer, Joe Hamilton, Ernest Lawrence, and other. Then Dr. Gofman describes his pioneering work on his true interests concerning heart disease, heparin, and lipoproteins. Finally intra-AEC political issues are discussed relating to testing of atomic weapons.

This sourcebook on building-integrated photovoltaics (BIPV) is intended for architects and designers interested in learning more about today's sustainable solar buildings. The booklet includes 16 design briefs describing actual structures; they illustrate how electricity-generating BIPV products (such as special roofing systems, vertical-wall systems, skylights, and awnings, all of which contain PV cells, modules, and films) can be integrated successfully into many different kinds of buildings. It also contains basic information about BIPV technologies, an overview of US product development activities and development programs, descriptions of major software design tools, and a bibliography.

The purpose of this document is to support the US Department of Energy (DOE) Fissile Materials Disposition Program`s preparation of the draft surplus plutonium disposition environmental impact statement. This is one of several responses to data call requests for background information on activities associated with the operation of the lead assembly (LA) mixed-oxide (MOX) fuel fabrication facility. DOE-MD requested that the DOE Site Operations Offices nominate DOE sites that meet established minimum requirements that could produce MOX LAs. Six initial site combinations were proposed: (1) Argonne National Laboratory-West (ANL-W) with support from Idaho National Engineering and Environmental Laboratory (INEEL), (2) Hanford, (3) Los Alamos National Laboratory (LANL) with support from Pantex, (4) Lawrence Livermore National Laboratory (LLNL), (5) Oak Ridge Reservation (ORR), and (6) Savannah River Site(SRS). After further analysis by the sites and DOE-MD, five site combinations were established as possible candidates for producing MOX LAs: (1) ANL-W with support from INEEL, (2) Hanford, (3) LANL, (4) LLNL, and (5) SRS. SRS has proposed an LA MOX fuel fabrication approach that would be done entirely inside an S and S Category 1 area. An alternate approach would allow fabrication of fuel pellets and assembly of fuel rods in an …

The purpose of this document is to support the US Department of Energy (DOE) Fissile Materials Disposition Program`s preparation of the draft surplus plutonium disposition environmental impact statement. This is one of several responses to data call requests for background information on activities associated with the operation of the lead assembly (LA) mixed-oxide (MOX) fuel fabrication facility. DOE-MD requested that the DOE Site Operations Offices nominate DOE sites that meet established minimum requirements that could produce MOX LAs. Six initial site combinations were proposed: (1) Argonne National Laboratory-West (ANL-W) with support from Idaho National Engineering and Environmental Laboratory (INEEL), (2) Hanford, (3) Los Alamos National Laboratory (LANL) with support from Pantex, (4) Lawrence Livermore National Laboratory (LLNL), (5) Oak Ridge Reservation (ORR), and (6) Savannah River Site (SRS). After further analysis by the sites and DOE-MD, five site combinations were established as possible candidates for producing MOX LAs: (1) ANL-W with support from INEEL, (2) Hanford, (3) LANL, (4) LLNL, and (5) SRS. Hanford has proposed an LA MOX fuel fabrication approach that would be done entirely inside an S and S Category 1 area. An alternate approach would allow fabrication of fuel pellets and assembly of fuel rods in …

A summary of the work is excerpted here. Final design of an MHD channel for the ITC program POC test has been completed. The channel was designed to be capable of 1.5 MW {sub e} power output and a lifetime of 2000 hours. Emphasis was placed upon durability and reliability. Hence, specific measures were taken to design against channel damage due to electric faults. The life-limiting issues associated with electrochemical corrosion and erosion of gas-side surfaces were addressed by the use of various materials with proven wear characteristics in a coal-fired MHD channel environment. Pitting of prototypical sidewall coupons was observed in the CDIF workhorse testing. The most likely cause of the observed pitting, water leaks resulting from cooling water tube braze failures, has been remedied. New brazing procedures and isolation of the sidebar gas-side material from water contact will prevent sidebar pitting in the prototypical channel. Water-side corrosion tests reported in this quarterly report include the latest results of tungsten-copper elements at controlled pH, heat flux and voltage levels. In the combustion subsystem, efforts continued to focus on understanding and improving the current levels of slag recovery and seed utilization achieved by the combustor. Analytical support was also provided …

A summary of the work is excerpted here. Final design of an MHD channel for the ITC program POC test has been completed. The channel was designed to be capable of 1.5 MW {sub e} power output and a lifetime of 2000 hours. Emphasis was placed upon durability and reliability. Hence, specific measures were taken to design against channel damage due to electric faults. The life-limiting issues associated with electrochemical corrosion and erosion of gas-side surfaces were addressed by the use of various materials with proven wear characteristics in a coal-fired MHD channel environment. Pitting of prototypical sidewall coupons was observed in the CDIF workhorse testing. The most likely cause of the observed pitting, water leaks resulting from cooling water tube braze failures, has been remedied. New brazing procedures and isolation of the sidebar gas-side material from water contact will prevent sidebar pitting in the prototypical channel. Water-side corrosion tests reported in this quarterly report include the latest results of tungsten-copper elements at controlled pH, heat flux and voltage levels. In the combustion subsystem, efforts continued to focus on understanding and improving the current levels of slag recovery and seed utilization achieved by the combustor. Analytical support was also provided …

A study of instrumentation and controls (I and C) technology used in nuclear power plants in Europe was conducted by a panel of US specialists. This study plants in Europe was conducted by a panel of US specialists. This study included a review of the literature on the subject, followed by a visit to some of the leading organizations in Europe in the field nuclear I and C. Areas covered are: (1) role of the operator and control room design; (2) transition from analog to digital technology; (3) computerized operator support systems for fault management; (4) control strategies and techniques; (5) Nuclear power plant I and C architecture; (6) instrumentation and (7) computer standards and tools. The finding relate to poor reactions.

The purpose of this document is to support the US Department of Energy (DOE) Fissile Materials Disposition Program`s preparation of the draft surplus plutonium disposition environmental impact statement. This is one of several responses to data call requests for background information on activities associated with the operation of the lead assembly (LA) mixed-oxide (MOX) fuel fabrication facility. The DOE Office of Fissile Materials Disposition (DOE-MD) has developed a dual-path strategy for disposition of surplus weapons-grade plutonium. One of the paths is to disposition surplus plutonium through irradiation of MOX fuel in commercial nuclear reactors. MOX fuel consists of plutonium and uranium oxides (PuO{sub 2} and UO{sub 2}), typically containing 95% or more UO{sub 2}. DOE-MD requested that the DOE Site Operations Offices nominate DOE sites that meet established minimum requirements that could produce MOX LAs. LLNL has proposed an LA MOX fuel fabrication approach that would be done entirely inside an S and S Category 1 area. This includes receipt and storage of PuO{sub 2} powder, fabrication of MOX fuel pellets, assembly of fuel rods and bundles, and shipping of the packaged fuel to a commercial reactor site. Support activities will take place within a Category 1 area. Building 332 …

The purpose of this document is to support the US Department of Energy (DOE) Fissile Materials Disposition Program`s preparation of the draft surplus plutonium disposition environmental impact statement. This is one of several responses to data call requests for background information on activities associated with the operation of the lead assembly (LA) mixed-oxide (MOX) fuel fabrication facility. LANL has proposed an LA MOX fuel fabrication approach that would be done entirely inside an S and S Category 1 area. This includes receipt and storage of PuO{sub 2} powder, fabrication of MOX fuel pellets, assembly of fuel rods and bundles, and shipping of the packaged fuel to a commercial reactor site. Support activities will take place within both Category 1 and 2 areas. Technical Area (TA) 55/Plutonium Facility 4 will be used to store the bulk PuO{sub 2} powder, fabricate MOX fuel pellets, assemble rods, and store fuel bundles. Bundles will be assembled at a separate facility, several of which have been identified as suitable for that activity. The Chemistry and Metallurgy Research Building (at TA-3) will be used for analytical chemistry support. Waste operations will be conducted in TA-50 and TA-54. Only very minor modifications will be needed to accommodate …

The purpose of this document is to support the US Department of Energy (DOE) Fissile Materials Disposition Program`s preparation of the draft surplus plutonium disposition environmental impact statement (EIS). This is one of several responses to data call requests for background information on activities associated with the operation of the lead assembly (LA) mixed-oxide (MOX) fuel fabrication facility. The DOE Office of fissile Materials Disposition (DOE-MD) has developed a dual-path strategy for disposition of surplus weapons-grade plutonium. One of the paths is to disposition surplus plutonium through irradiation of MOX fuel in commercial nuclear reactors. MOX fuel consists of plutonium and uranium oxides (PuO{sub 2} and UO{sub 2}), typically containing 95% or more UO{sub 2}. DOE-MD requested that the DOE Site Operations Offices nominate DOE sites that meet established minimum requirements that could produce MOX LAs. The paper describes the following: Site map and the LA facility; process descriptions; resource needs; employment requirements; wastes, emissions, and exposures; accident analysis; transportation; qualitative decontamination and decommissioning; post-irradiation examination; LA fuel bundle fabrication; LA EIS data report assumptions; and LA EIS data report supplement.

The ALARA Center at Brookhaven National Laboratory publishes a series of bibliographies of selected readings in radiation protection and ALARA in the continuing effort to collect and disseminate information on radiation dose reduction at nuclear power plants. This is volume 7 of the series. The abstracts in this bibliography were selected from proceedings of technical meetings and conferences, journals, research reports, and searches of the Energy Science and Technology database of the US Department of Energy. The subject material of these abstracts relates to radiation protection and dose reduction, and ranges from use of robotics to operational health physics, to water chemistry. Material on the design, planning, and management of nuclear power stations is included, as well as information on decommissioning and safe storage efforts. Volume 7 contains 293 abstract, an author index, and a subject index. The author index is specific for this volume. The subject index is cumulative and lists all abstract numbers from volumes 1 to 7. The numbers in boldface indicate the abstracts in this volume; the numbers not in boldface represent abstracts in previous volumes.

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This is an omnibus publication about the federally-recognized Indian tribes of the Columbia-Snake river basin, as presented by themselves. It showcases several figurative and literal snapshots of each tribe, bits and pieces of each tribe`s story. Each individual tribe or tribal confederation either submitted its own section to this publication, or developed its own section with the assistance of the writer-editor. A federally-recognized tribe is an individual Indian group, or confederation of Indian groups, officially acknowledged by the US government for purposes of legislation, consultation and benefits. This publication is designed to be used both as a resource and as an introduction to the tribes. Taken together, the sections present a rich picture of regional indian culture and history, as told by the tribes.

The possibility of anthropogenic climate change has reached the attention of Government officials and researchers. However, one cannot study climate change without climate data. The CARDS project will produce high-quality upper-air data for the research community and for policy-makers. The authors intend to produce a dataset which is: easy to use, as complete as possible, as free of random errors as possible. They will also attempt to identify biases and remove them whenever possible. In this report, they relate progress toward their goal. They created a robust new format for archiving upper-air data, and designed a relational database structure to hold them. The authors have converted 13 datasets to the new format and have archived over 10,000,000 individual soundings from 10 separate data sources. They produce and archive a metadata summary of each sounding they load. They have researched station histories, and have built a preliminary upper-air station history database. They have converted station-sorted data from their primary database into synoptic-sorted data in a parallel database. They have tested and will soon implement an advanced quality-control procedure, capable of detecting and often repairing errors in geopotential height, temperature, humidity, and wind. This unique quality-control method uses simultaneous vertical, horizontal, and …

The November 1956 monthly report for the Chemical Processing Department of Hanford Atomic Products Operation includes information regarding research and engineering efforts with respect to the Purex and Redox process technology. Also discussed was the production operation, finished product operation, power and general maintenance, financial operation, engineering and research operations, and employee operations. (MB)

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The Ninth National Conference on Undergraduate Research (NCUR 95) was held at Union College in Schenectady, New York. This annual celebration of undergraduate scholarly activity continues to elicit strong nation-wide support and enthusiasm among both students and faculty. Attendance was nearly 1,650, which included 1,213 student oral and poster presenters. For the second year in a row, many student papers had to be rejected for presentation at NCUR due to conference size limitations. Thus, submitted papers for presentation at NCUR 95 were put through a careful review process before acceptance. Those students who have been selected to have their paper appear in these Proceedings have been through yet a second review process. As a consequence, their work has been judged to represent an impressive level of achievement at the undergraduate level. Volume 1 contains papers related to Arts and Humanities (52 papers), and Social and Behavioral Sciences (64 papers).

This is a progress report of the production reactors on the Hanford Reservation for the month of December 1951. This report takes each division (e.g., manufacturing, medical, accounting, occupational safety, security, reactor operations, etc.) of the site and summarizes its accomplishments and employee relations for that month.

The cyclocraft is a proven hybrid aircraft, capable of VTOL, lifting heavy and bulky loads, highly controllable, having high safety characteristics and low operating costs. Mission Research Corporation (MRC), under Department of Energy sponsorship, is evaluating the potential use of cyclocraft in the transport of drill rigs, mud, pipes and other materials and equipment, in a cost effective and environmentally safe manner, to support oil and gas drilling, production, and transportation operations in wetland areas. Based upon the results of an earlier parametric study, a cyclocraft design, having a payload capacity of 45 tons and designated H.1 Cyclocraft, was selected for further study, including the preparation of a preliminary design and a development plan, and the determination of operating costs. This report contains all of the results derived from the program to evaluate the use of cyclocraft in the support of oil and gas drilling and production operations in wetland areas.

This document presents a summary of work and progress at the Hanford Engineer Works for February 1953. The report is divided into sections by department. A plant wide general summary is included at the beginning of the report, after which the departmental summaries begin. The Manufacturing Department reports plant statistics, and summaries for the Metal Preparation, Reactor and Separation sections. The Engineering Department`s section summaries work for the Technical, Design, and Project Sections. Costs for the various departments are presented in the Financial Department`s summary. The Medical, Radiological Sciences, Utilities and General Services, Employee and Public Relations, and Community Real Estate and Service departments have sections presenting their monthly statistics, work, progress, and summaries.

The division was formed in 1946 at the suggestion of Dr. Eugene P. Wigner to attack the problem of the distortion of graphite in the early reactors due to exposure to reactor neutrons, and the consequent radiation damage. It was called the Metallurgy Division and assembled the metallurgical and solid state physics activities of the time which were not directly related to nuclear weapons production. William A. Johnson, a Westinghouse employee, was named Division Director in 1946. In 1949 he was replaced by John H Frye Jr. when the Division consisted of 45 people. He was director during most of what is called the Reactor Project Years until 1973 and his retirement. During this period the Division evolved into three organizational areas: basic research, applied research in nuclear reactor materials, and reactor programs directly related to a specific reactor(s) being designed or built. The Division (Metals and Ceramics) consisted of 204 staff members in 1973 when James R. Weir, Jr., became Director. This was the period of the oil embargo, the formation of the Energy Research and Development Administration (ERDA) by combining the Atomic Energy Commission (AEC) with the Office of Coal Research, and subsequent formation of the Department of …

This is the fifth quarterly report for this project. This project is divided into three phases. Phase 1, which has been completed, involved design, engineering, and procurement for the CZD system, duct and facility modifications, and supporting equipment. Phase 2, also completed, included equipment acquisition and installation, facility construction, startup, and operator training for parametric testing. Phase 3 broadly covers testing, operation and disposition, but only a portion of Phase 3 was included in Budget Period 1. That portion was concerned with parametric testing of the CZD system to establish the optimum conditions for an extended, one-year, continuous demonstration. As of December 31, 1991, the following goals have been achieved. (1) Nozzle Selection - A modified Spraying Systems Company (SSC) atomizing nozzle has been selected for the one-year continuous CZD demonstration. (2) SO{sub 2} and NO{sub x} Reduction - Preliminary confirmation of 50% SO{sub 2} reduction has been achieved, but the NO{sub x} reduction target cannot be confirmed at this time. (3) Lime Selection - Testing indicated an injection rate of 40 to 50 gallons per minute with a lime slurry concentration of 8 to 10% to achieve 50% SO{sub 2} reduction. There has been no selection of the lime …

This is the fifth quarterly report for this project. This project is divided into three phases. Phase 1, which has been completed, involved design, engineering, and procurement for the CZD system, duct and facility modifications, and supporting equipment. Phase 2, also completed, included equipment acquisition and installation, facility construction, startup, and operator training for parametric testing. Phase 3 broadly covers testing, operation and disposition, but only a portion of Phase 3 was included in Budget Period 1. That portion was concerned with parametric testing of the CZD system to establish the optimum conditions for an extended, one-year, continuous demonstration. As of December 31, 1991, the following goals have been achieved. (1) Nozzle Selection - A modified Spraying Systems Company (SSC) atomizing nozzle has been selected for the one-year continuous CZD demonstration. (2) SO[sub 2] and NO[sub x] Reduction - Preliminary confirmation of 50% SO[sub 2] reduction has been achieved, but the NO[sub x] reduction target cannot be confirmed at this time. (3) Lime Selection - Testing indicated an injection rate of 40 to 50 gallons per minute with a lime slurry concentration of 8 to 10% to achieve 50% SO[sub 2] reduction. There has been no selection of the lime …