IAEA/USDOE senior management workshop on promotion of safety culture for the NPPS with RBMK reactors. Working material

International Nuclear Information System (INIS)

1997-01-01

The current workshop, co-sponsored by the IAEA and USDOE, was a continuation of the previous effort for further promotion of safety culture at RBMK NPPs. The objective of the workshop was to provide a forum for senior managers from governmental organizations and operating organizations to further exchange experience in understanding the factors influencing safety culture, in assessing safety culture at their own organizations and developing safety culture at RBMK NPPs. The workshop consisted of a broad scope of presentations to review the basic concepts and major elements of safety culture (ownership, accountability, pride, job satisfaction, trust, openness, etc.), to identify and discuss the various approaches used in different countries in attaining a strong safety culture, and to explain, through the use of practical examples, what the benefits of a strong safety culture are; how to improve the behavior of people, how to gain trust and openness, how to overcome difficulties in changing staff's attitudes, and how to manage safety culture. 2 figs

System Definition Document: Reactor Data Necessary for Modeling Plutonium Disposition in Catawba Nuclear Station Units 1 and 2

International Nuclear Information System (INIS)

Ellis, R.J.

2000-01-01

The US Department of Energy (USDOE) has contracted with Duke Engineering and Services, Cogema, Inc., and Stone and Webster (DCS) to provide mixed-oxide (MOX) fuel fabrication and reactor irradiation services in support of USDOE's mission to dispose of surplus weapons-grade plutonium. The nuclear station units currently identified as mission reactors for this project are Catawba Units 1 and 2 and McGuire Units 1 and 2. This report is specific to Catawba Nuclear Station Units 1 and 2, but the details and materials for the McGuire reactors are very similar. The purpose of this document is to present a complete set of data about the reactor materials and components to be used in modeling the Catawba reactors to predict reactor physics parameters for the Catawba site. Except where noted, Duke Power Company or DCS documents are the sources of these data. These data are being used with the ORNL computer code models of the DCS Catawba (and McGuire) pressurized-water reactors

Organization of Control Units with Operational Addressing

OpenAIRE

Alexander A. Barkalov; Roman M. Babakov; Larysa A. Titarenko

2012-01-01

The using of operational addressing unit as the block of control unit is proposed. The new structure model of Moore finite-state machine with reduced hardware amount is developed. The generalized structure of operational addressing unit is suggested. An example of synthesis process for Moore finite-state machine with operational addressing unit is given. The analytical researches of proposed structure of control unit are executed.

Summary of the CEC/USDOE workshop on uncertainty analysis

International Nuclear Information System (INIS)

Elderkin, C.E.; Kelly, G.N.

1990-06-01

There is uncertainty in all aspects of assessing the consequences of accidental releases of radioactive material, from understanding and describing the environmental and biological transfer processes to modeling emergency response. The need for an exchange of views and a comparison of approaches between the diverse disciplines led to the organization of a CEC/USDOE Workshop on Uncertainty Analysis held in Santa Fe, New Mexico, in November 1989. The workshop brought together specialists in a number of disciplines, including those expert in the mathematics and statistics of uncertainty analysis, in expert judgment elicitation and evaluation, and in all aspects of assessing the radiological and environmental consequences of accidental releases of radioactive material. In addition, there was participation from users of the output of accident consequences assessment in decision making and/or regulatory frameworks. The main conclusions that emerged from the workshop are summarized in this paper. These are discussed in the context of three different types of accident consequence assessment: probabilistic assessments of accident consequences undertaken as inputs to risk analyses of nuclear installations, assessments of accident consequences in real time to provide inputs to decisions on the introduction of countermeasures, and the reconstruction of doses and risks resulting form past releases of radioactive material

Operable Unit Boundaries

Data.gov (United States)

U.S. Environmental Protection Agency — This dataset consists of operable unit data from multiple Superfund sites in U.S. EPA Region 8. These data were acquired from multiple sources at different times and...

The in-depth safety assessment (ISA) pilot projects in Ukraine

International Nuclear Information System (INIS)

Kot, C. A.

1998-01-01

Ukraine operates pressurized water reactors of the Soviet-designed type, VVER. All Ukrainian plants are currently operating with annually renewable permits until they update their safety analysis reports (SARs). After approval of the SARS by the Ukrainian Nuclear Regulatory Authority, the plants will be granted longer-term operating licenses. In September 1995, the Nuclear Regulatory Authority and the Government Nuclear Power Coordinating Committee of Ukraine issued a new contents requirement for the safety analysis reports of VVERs in Ukraine. It contains requirements in three major areas: design basis accident (DBA) analysis, probabilistic risk assessment (PRA), and beyond design-basis accident (BDBA) analysis. The DBA requirements are an expanded version of the older SAR requirements. The last two requirements, on PRA and BDBA, are new. The US Department of Energy (USDOE), through the International Nuclear Safety Program (INSP), has initiated an assistance and technology transfer program to Ukraine to assist their nuclear power stations in developing a Western-type technical basis for the new SARS. USDOE sponsored In-Depth Safety Assessments (ISAs) have been initiated at three pilot nuclear reactor units in Ukraine, South Ukraine Unit 1, Zaporizhzhya Unit 5, and Rivne Unit 1. USDOE/INSP have structured the ISA program in such a way as to provide maximum assistance and technology transfer to Ukraine while encouraging and supporting the Ukrainian plants to take the responsibility and initiative and to perform the required assessments

HRB-22 capsule irradiation test for HTGR fuel. JAERI/USDOE collaborative irradiation test

Energy Technology Data Exchange (ETDEWEB)

Minato, Kazuo; Sawa, Kazuhiro; Fukuda, Kousaku [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment; and others

1998-03-01

As a JAERI/USDOE collaborative irradiation test for high-temperature gas-cooled reactor fuel, JAERI fuel compacts were irradiated in the HRB-22 irradiation capsule in the High Flux Isotope Reactor at the Oak Ridge National Laboratory (ORNL). Postirradiation examinations also were performed at ORNL. This report describes 1) the preirradiation characterization of the irradiation samples of annular-shaped fuel compacts containing the Triso-coated fuel particles, 2) the irradiation conditions and fission gas releases during the irradiation to measure the performance of the coated particle fuel, 3) the postirradiation examinations of the disassembled capsule involving visual inspection, metrology, ceramography and gamma-ray spectrometry of the samples, and 4) the accident condition tests on the irradiated fuels at 1600 to 1800degC to obtain information about fuel performance and fission product release behavior under accident conditions. (author)

200-BP-5 operable unit treatability test report

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-04-01

The 200-BP-5 Operable Unit was established in response to recommendations presented in the 200 East Groundwater Aggregate Area Management Study Report (AAMSR) (DOE-RL 1993a). Recognizing different approaches to remediation, the groundwater AAMSR recommended separating groundwater from source and vadose zone operable units and subdividing 200 East Area groundwater into two operable units. The division between the 200-BP-5 and 200-PO-1 Operable Units was based principally on source operable unit boundaries and distribution of groundwater plumes derived from either B Plant or Plutonium/Uranium Extraction (PUREX) Plant liquid waste disposal sites.

200-BP-5 operable unit treatability test report

International Nuclear Information System (INIS)

1996-04-01

The 200-BP-5 Operable Unit was established in response to recommendations presented in the 200 East Groundwater Aggregate Area Management Study Report (AAMSR) (DOE-RL 1993a). Recognizing different approaches to remediation, the groundwater AAMSR recommended separating groundwater from source and vadose zone operable units and subdividing 200 East Area groundwater into two operable units. The division between the 200-BP-5 and 200-PO-1 Operable Units was based principally on source operable unit boundaries and distribution of groundwater plumes derived from either B Plant or Plutonium/Uranium Extraction (PUREX) Plant liquid waste disposal sites

Integrated Ground Operations Demonstration Units

Data.gov (United States)

National Aeronautics and Space Administration — The overall goal of the AES Integrated Ground Operations Demonstration Units (IGODU) project is to demonstrate cost efficient cryogenic operations on a relevant...

Physical protection of nuclear operational units

International Nuclear Information System (INIS)

1981-07-01

The general principles of and basic requirements for the physical protection of operational units in the nuclear field are established. They concern the operational units whose activities are related with production, utilization, processing, reprocessing, handling, transport or storage of materials of interest for the Brazilian Nuclear Program. (I.C.R.) [pt

Analysis on Isolation Condenser Operation by Fukushima Daiichi Unit 1 Operators

International Nuclear Information System (INIS)

Kim, Man Cheol

2014-01-01

Fukushima Daiichi nuclear accident resulted in the core damage in three reactors and the release of considerable amount of radioactive material to the environment, not to mention significant social impact and anti-nuclear atmosphere all around the world. This paper provides a review of the findings related to shift operators' operation of the isolation condenser in Unit 1 to examine shift operators' response to the situation. Based on the review of the findings, a situation assessment model was developed to analyze shift operators' understanding on whether core cooling was successfully performed in Unit 1 through the operation of isolation condenser. It was found that lack of information could be one of the main causes for the failure in core cooling by the IC in Unit 1. It is also recommended that the differences in the mathematical model for the situation assessment and that of the real operator need to be further investigated

Analysis on Isolation Condenser Operation by Fukushima Daiichi Unit 1 Operators

Energy Technology Data Exchange (ETDEWEB)

Kim, Man Cheol [Chungang University, Seoul (Korea, Republic of)

2014-08-15

Fukushima Daiichi nuclear accident resulted in the core damage in three reactors and the release of considerable amount of radioactive material to the environment, not to mention significant social impact and anti-nuclear atmosphere all around the world. This paper provides a review of the findings related to shift operators' operation of the isolation condenser in Unit 1 to examine shift operators' response to the situation. Based on the review of the findings, a situation assessment model was developed to analyze shift operators' understanding on whether core cooling was successfully performed in Unit 1 through the operation of isolation condenser. It was found that lack of information could be one of the main causes for the failure in core cooling by the IC in Unit 1. It is also recommended that the differences in the mathematical model for the situation assessment and that of the real operator need to be further investigated.

Nuclear units operating improvement by using operating experience

International Nuclear Information System (INIS)

Rotaru, I.; Bilegan, I.C.

1997-01-01

The paper presents how the information experience can be used to improve the operation of nuclear units. This areas include the following items: conservative decision making; supervisory oversight; teamwork; control room distraction; communications; expectations and standards; operator training and fundamental knowledge, procedure quality and adherence; plant status awareness. For each of these topics, the information illustrate which are the principles, the lessons learned from operating experience and the most appropriate exemplifying documents. (authors)

Operation and Maintenance Plan for the 300-FF-5 Operable Unit

International Nuclear Information System (INIS)

Singleton, K.M.

1996-09-01

This document is the operation and maintenance plan for the 300-FF-5 groundwater operable unit. The purpose of this plan is to identify tasks necessary to verify the effectiveness of the selected alternative. This plan also describes the monitoring program and administrative tasks that will be used as the preferred alternative for the remediation of groundwater in the 300-FF-5 Operable Unit. The preferred alternative selected for remediation of groundwater consists of institutional controls

Occupational radiation exposure history of Idaho Field Office Operations at the INEL

International Nuclear Information System (INIS)

Horan, J.R.; Braun, J.B.

1993-10-01

An extensive review has been made of the occupational radiation exposure records of workers at the Idaho National Engineering Laboratory (INEL) over the period of 1951 through 1990. The focus has been on workers employed by contractors and employees of the Idaho Field Operations Office (ID) of the United States Department of Energy (USDOE) and does not include the Naval Reactors Facility (NRF), the Argonne National Laboratory (ANL), or other operations field offices at the INEL. The radiation protection guides have decreased from 15 rem/year to 5 rem/year in 1990 for whole body penetrating radiation exposure. During these 40 years of nuclear operations (in excess of 200,000 man-years of work), a total of twelve individuals involved in four accidents exceeded the annual guidelines for exposure; nine of these exposures were received during life saving efforts on January 3, 1961 following the SL-1 reactor accident which killed three military personnel. These exposures ranged from 8 to 27 rem. Only one individual has exceeded the annual whole body penetrating radiation protection guidelines in the last 29 years

Occupational radiation exposure history of Idaho Field Office Operations at the INEL

Energy Technology Data Exchange (ETDEWEB)

Horan, J.R.; Braun, J.B.

1993-10-01

An extensive review has been made of the occupational radiation exposure records of workers at the Idaho National Engineering Laboratory (INEL) over the period of 1951 through 1990. The focus has been on workers employed by contractors and employees of the Idaho Field Operations Office (ID) of the United States Department of Energy (USDOE) and does not include the Naval Reactors Facility (NRF), the Argonne National Laboratory (ANL), or other operations field offices at the INEL. The radiation protection guides have decreased from 15 rem/year to 5 rem/year in 1990 for whole body penetrating radiation exposure. During these 40 years of nuclear operations (in excess of 200,000 man-years of work), a total of twelve individuals involved in four accidents exceeded the annual guidelines for exposure; nine of these exposures were received during life saving efforts on January 3, 1961 following the SL-1 reactor accident which killed three military personnel. These exposures ranged from 8 to 27 rem. Only one individual has exceeded the annual whole body penetrating radiation protection guidelines in the last 29 years.

Junior Leader Training Development in Operational Units

Science.gov (United States)

2012-04-01

UNITS Successful operational units do not arise without tough, realistic, and challenging training. Field Manual (FM) 7-0, Training Units and D...operations. The manual provides junior leaders with guidance on how to conduct training and training management. Of particular importance is the definition...1 Relation htp between ADDIE and the Anny Training Management Model. The Army Training Management Model and ADDIE process appear in TRADOC PAM 350

Analysis of Serbian Military Riverine Units Capability for Participation in the United Nations Peacekeeping Operations

Directory of Open Access Journals (Sweden)

Slobodan Radojevic

2017-06-01

Full Text Available This paper analyses required personnel, training capacities and equipment for participation in the United Nations peacekeeping operations with the riverine elements. In order to meet necessary capabilities for engagement in United Nations peacekeeping operations, Serbian military riverine units have to be compatible with the issued UN requirements. Serbian Armed Forces have the potential to reach such requirements with the River Flotilla as a pivot for the participation in UN missions. Serbian Military Academy adopted and developed educational and training program in accordance with the provisions and recommendations of the IMO conventions and IMO model courses. Serbian Military Academy has opportunities for education and training military riverine units for participation in the United Nations peacekeeping operations. Moreover, Serbia has Multinational Operations Training Center and Peacekeeping Operations Center certified to provide selection, training, equipping and preparations of individuals and units to the United Nations multinational operations.

Steel corrosion in radioactive waste storage tanks

International Nuclear Information System (INIS)

Carranza, Ricardo M.; Giordano, Celia M.; Saenz, E.; Weier, Dennis R.

2004-01-01

A collaborative study is being conducted by CNEA and USDOE (Department of Energy of the United States of America) to investigate the effects of tank waste chemistry on radioactive waste storage tank corrosion. Radioactive waste is stored in underground storage tanks that contain a combination of salts, consisting primarily of sodium nitrate, sodium nitrite and sodium hydroxide. The USDOE, Office of River Protection at the Hanford Site, has identified a need to conduct a laboratory study to better understand the effects of radioactive waste chemistry on the corrosion of waste storage tanks at the Hanford Site. The USDOE science need (RL-WT079-S Double-Shell Tanks Corrosion Chemistry) called for a multi year effort to identify waste chemistries and temperatures within the double-shell tank (DST) operating limits for corrosion control and operating temperature range that may not provide the expected corrosion protection and to evaluate future operations for the conditions outside the existing corrosion database. Assessment of corrosion damage using simulated (non-radioactive) waste is being made of the double-shell tank wall carbon steel alloy. Evaluation of the influence of exposure time, and electrolyte composition and/or concentration is being also conducted. (author) [es

200-UP-2 Operable Unit technical baseline report

International Nuclear Information System (INIS)

Deford, D.H.

1991-02-01

This report is prepared in support of the development of a Remedial Investigation/Feasibility Study (RI/FS) Work Plan for the 200-UP-2 Operable Unit by EBASCO Environmental, Incorporated. It provides a technical baseline of the 200-UP-2 Operable Unit and results from an environmental investigation undertaken by the Technical Baseline Section of the Environmental Engineering Group, Westinghouse Hanford Company (Westinghouse Hanford). The 200-UP-2 Operable Unit Technical Baseline Report is based on review and evaluation of numerous Hanford Site current and historical reports, Hanford Site drawings and photographs and is supplemented with Hanford Site inspections and employee interviews. No field investigations or sampling were conducted. Each waste site in the 200-UP-2 Operable Unit is described separately. Close relationships between waste units, such as overflow from one to another, are also discussed. The 200-UP-2 Operable Unit consists of liquid-waste disposal sites in the vicinity of, and related to, U Plant operations in the 200 West Area of the Hanford Site. The ''U Plant'' refers to the 221-U Process Canyon Building, a chemical separations facility constructed during World War 2. It also includes the Uranium Oxide (UO 3 ) Plant, which was constructed at the same time and, like the 221-U Process Canyon Building, was later converted for other missions. Waste sites in the 200-UP-2 Operable Unit are associated with the U Plant Uranium Metal Recovery Program mission that occurred between 1952 and 1958 and the UO 3 Plant's ongoing uranium oxide mission and include one or more cribs, reverse wells, french drains, septic tanks and drain fields, trenches, catch tanks, settling tanks, diversion boxes, waste vaults, and the lines and encasements that connect them. 11 refs., 1 tab

Phase-IIC experiments of the JAERI/USDOE collaborative program on fusion blanket neutronics

International Nuclear Information System (INIS)

Oyama, Yukio

1992-12-01

Neutronics experiments on two types of heterogeneous blankets have been performed as the Phase-IIC experiment of JAERI/USDOE collaborative program on fusion blanket neutronics. The experimental system was used in the same geometry as the previous Phase-IIA series which was a closed geometry using neutron source enclosure of lithium carbonate. The heterogeneous blankets selected here are the beryllium edge-on and the water coolant channel assemblies. In the former the beryllium and lithium-oxide layers are piled up alternately in the front part of test blanket. In the latter, the three simulated water cooling channels are settled in the Li 2 O blanket. These are producing steep gradient of neutron flux around material boundary. The calculation accuracy and measurement method for these features is a key of interest in the experiments. The measurements were performed for tritium production rate and the other nuclear parameters as well as the previous experiments. This report describes the experimental detail and the results enough to use for the benchmark data for testing the data and method of design calculation of fusion reactors. (author)

Analysis of operating reliability of WWER-1000 unit

International Nuclear Information System (INIS)

Bortlik, J.

1985-01-01

The nuclear power unit was divided into 33 technological units. Input data for reliability analysis were surveys of operating results obtained from the IAEA information system and certain indexes of the reliability of technological equipment determined using the Bayes formula. The missing reliability data for technological equipment were used from the basic variant. The fault tree of the WWER-1000 unit was determined for the peak event defined as the impossibility of reaching 100%, 75% and 50% of rated power. The period was observed of the nuclear power plant operation with reduced output owing to defect and the respective time needed for a repair of the equipment. The calculation of the availability of the WWER-1000 unit was made for different variant situations. Certain indexes of the operating reliability of the WWER-1000 unit which are the result of a detailed reliability analysis are tabulated for selected variants. (E.S.)

Licensed operating reactors. Operating units status report, data as of 2-28-79

International Nuclear Information System (INIS)

1979-03-01

This report is divided into three sections: the first contains monthly highlights and statistics for commercial operating units, and errata from previously reported data; the second is a compilation of detailed information on each unit, provided by NRC Regional Offices and IE Headquarters; and the third section is an appendix containing comparative statistics of U.S. nuclear/fossil capacity, identification of nuclear power plants within regional Electric Reliability Councils, the relative status of U.S. nuclear electric production to all U.S. electric production by state, and selected Edison Electric Institute operating statistics. Throughout the report, statistical factors for periods greater than a report month, or for more than one unit, are computed as the arithmetic average of each unit's individual operating statistics. The statistical factors for each unit for the report month are computed from actual power production for the month. The factors for the life-span of each unit (the ''Cumulative'' column) are reported by the utility and are not entirely re-computed by NRC. Utility power production data is checked for consistency with previously submitted statistics

Initial startup and operations of Yonggwang Units 3 and 4

International Nuclear Information System (INIS)

Collier, T.J.; Chari, D.R.; Kiraly, F.

1996-01-01

A significant milestone in the nuclear power industry was achieved in 1995, when Yonggwang (YGN) Units 3 and 4 were accepted into in commercial operation by Korea Electric Power Corporation (KEPCO). YGN Unit 3 was accepted into commercial operation on March 31, 1995, the original date established during project initiation. YGN Unit 4 was accepted into operation on January 1, 1996, 3 months ahead of schedule. Each YGN unit produces approximately 1,050 Mwe and supplies approximately ten percent of the total electric power demand in the Republic of Korea (ROK). The overall plant efficiency is approximately 37% which is at least 1% higher than most nuclear units. Since achieving commercial operation, YGN Unit 3 has operated at essentially full power which has resulted in an annual performance rate in excess of 85%. YGN Unit 3 is the first of six pressurized water reactors which are currently under design and construction in the ROK and serves as the reference design for the Korean Standard Nuclear Power Plant program. Both YGN Units 3 and 4 include a System 800 Nuclear Steam Supply System (NSSS). The NSSS is rated at 2,815 Mwth and is the ABB-CE standard design. The design includes numerous advanced design features which enhance plant safety, performance and operability. A well executed startup test program was successfully completed on both units prior to commercial operation. A summary of the YGN NSSS design features, the startup test program and selected test results demonstrating the performance of those features are presented in this paper

Operating performance of LWR nuclear generating units

International Nuclear Information System (INIS)

Pia, S.

1984-01-01

This work aims at reviewing, on the basis of historical data, the operational problem areas which explain the degree of availability and productivity achieved up to now by nuclear power plants in commercial operation in the world. The operating performance data of nuclear power plants area analysed with respect to plant type, size and other significant reference parameters and they are evaluated also by comparison with fossil generating unit data. Major performance indices data are presented for both nuclear and fossil units type and distribution of outage causes. Unplanned full outages caused by nuclear power plant equipment and components failure are particulary emphasized. The trend for unplanned full outages due to the failure of components shows decreasing numerical values in 1981 with respect to the previous years. But this result should be weighed with the increasing plant unavailability hours needed for maintenance and repair action (chiefly preventive maintenance on critical components). This means that the number and downtime of forced outage must be drastically reduced for economic reasons (production losses and problems associated with the unavailable unit unplanned replacement) as well as for plant safe and reliable operation (sudden unavailability of key components and frequency of transients associated with plant shutdown and routine startup operation)

Forum: House of Cards--or--Trojan Horse?: A Response to Ralf St. Clair's House of Cards: Analyzing "Making Skills Everyone's Business"

Science.gov (United States)

Scully-Russ, Ellen

2015-01-01

In this article, Ellen Scully-Russ responds to St. Clair's analysis (EJ1072357) of the recent policy report from the Office of Career, Technical and Adult Education, "Making Skills Everyone's Business: A Call to Transform Adult Learning in the United States" (MSEB) (United States Department of Education [USDoE], 2015). While Scully-Russ…

Biota of the 300-FF-1 operable unit. [Westinghouse Hanford Company

Energy Technology Data Exchange (ETDEWEB)

Rickard, W.H. Jr.; Fitzner, R.E.; Brandt, C.A.

1990-10-01

This report summarizes Task 5a-2 of the Phase I Remedial Investigation -- Operable Unit Characterization of the 300-FF-1 Operable Unit on the Hanford Site, near Richland, Washington. The ultimate goal of Phase I is to determine the nature and extent of the threat to public health and the environment from releases of hazardous substances from the operable unit. The purpose of Task 5a-2 was to determine what species inhabit the 300-FF-1 Operable Unit and how they use the unit. The focus is on those species listed as endangered or threatened, those that are economically important, or those that constitute significant components of the human food chain. 39 refs., 5 figs., 5 tabs.

Feasibility study report for the 200-BP-1 operable unit

Energy Technology Data Exchange (ETDEWEB)

1993-06-01

This feasibility study examines a range of alternatives and provides recommendations for selecting a preferred alternative for remediating contamination at the 200-BP-1 operable unit. The 200-BP-1 operable unit is located in the center of the Hanford Site along the northern boundary of the 200 East Area. The 241-BY Tank Farm is located immediately to the south of the operable unit. 200-BP-1 is a source operable unit with contaminated soils associated primarily with nine inactive cribs (known as the 216-B cribs). These cribs were used for disposal of low-level radioactive liquid waste from U Plant uranium recovery operations, and waste storage tank condensate from the adjacent 241-BY Tank Farm. The cribs used for disposal of U Plant waste were in operation from 1955--1965, and the cribs used for disposal of tank condensate were in operation from 1965--1975. In addition to the cribs, four unplanned releases of radioactive materials have occurred within the operable unit. Contaminated surface soils associated with the unplanned releases have been consolidated over the cribs and covered with clean soil to reduce contaminant migration and exposure. Discharge of wastes to the cribs has resulted in soil and groundwater contamination. The groundwater is being addressed as part of the 200 East Aggregate Area, groundwater operable unit. Contaminated soils at the site can be categorized by the types of contaminants, their distribution in the soil column, and the risk posed by the various potential exposure pathways. Below the clean soil cover, the near surface soils contain low-levels of contamination with cesium-137, radium-226, strontium-90, thorium-228, and uranium. The lifetime incremental cancer risk associated with these soils if they were exposed at the surface is 9{times}10{sup {minus}5}.

Feasibility study report for the 200-BP-1 operable unit

International Nuclear Information System (INIS)

1993-06-01

This feasibility study examines a range of alternatives and provides recommendations for selecting a preferred alternative for remediating contamination at the 200-BP-1 operable unit. The 200-BP-1 operable unit is located in the center of the Hanford Site along the northern boundary of the 200 East Area. The 241-BY Tank Farm is located immediately to the south of the operable unit. 200-BP-1 is a source operable unit with contaminated soils associated primarily with nine inactive cribs (known as the 216-B cribs). These cribs were used for disposal of low-level radioactive liquid waste from U Plant uranium recovery operations, and waste storage tank condensate from the adjacent 241-BY Tank Farm. The cribs used for disposal of U Plant waste were in operation from 1955--1965, and the cribs used for disposal of tank condensate were in operation from 1965--1975. In addition to the cribs, four unplanned releases of radioactive materials have occurred within the operable unit. Contaminated surface soils associated with the unplanned releases have been consolidated over the cribs and covered with clean soil to reduce contaminant migration and exposure. Discharge of wastes to the cribs has resulted in soil and groundwater contamination. The groundwater is being addressed as part of the 200 East Aggregate Area, groundwater operable unit. Contaminated soils at the site can be categorized by the types of contaminants, their distribution in the soil column, and the risk posed by the various potential exposure pathways. Below the clean soil cover, the near surface soils contain low-levels of contamination with cesium-137, radium-226, strontium-90, thorium-228, and uranium. The lifetime incremental cancer risk associated with these soils if they were exposed at the surface is 9x10 -5

Feasibility study report for the 200-BP-1 operable unit

International Nuclear Information System (INIS)

1994-01-01

This feasibility study (FS) examines a range of alternatives and provides recommendations for selecting a preferred altemative for remediating contamination at the 200-BP-1 operable unit. The 200-BP-1 operable unit is located in the center of the Hanford Site along the northern boundary of the 200 East Area. The 241-BY Tank Farm is located immediately to the south of the operable unit. 200-BP-1 is a source operable unit with contaminated soils associated primarily with nine inactive cribs (known as the 216-B cribs). These cribs were used for disposal of low-level radioactive liquid waste from U Plant uranium recovery operations, and waste storage tank condensate from the adjacent 241-BY Tank Farm. The cribs used for disposal of U Plant waste were in operation from 1955--1965, and the cribs used for disposal of tank condensate were in operation from 1965-1975. In addition to the cribs, four unplanned releases of radioactive materials have occurred within the operable unit. Contaminated surface soils associated with the unplanned releases have been consolidated over the cribs and covered with clean soil to reduce contaminant migration and exposure. Discharge of wastes to the cribs has resulted in soil and groundwater contamination. The groundwater is being addressed as part of the 200 East Aggregate Area groundwater operable unit. Contaminated soils at the site can be categorized by the types of contaminants, their distribution in the soil column, and the risk posed by the various potential exposure pathways. Below the clean soil cover, the near surface soils contain low-:levels of contamination with cesium-137, radium-226, strontium-90, thorium-228 and uranium. The lifetime incremental cancer risk associated with these soils if they were exposed at the surface is 9 x 10 5

Electric and Hybrid Vehicle Program, Site Operator Program. Quarterly progress report, October--December 1995 (first quarter of fiscal year 1996)

Energy Technology Data Exchange (ETDEWEB)

Francfort, J.E. [Lockheed Idaho Technologies Co., Idaho Falls, ID (United States); Bassett, R.R. [Sandia National Labs., Albuquerque, NM (United States); Briasco, S. [Los Angeles Dept. of Water and Power, CA (United States)] [and others

1996-03-01

This is the Site Operator Program quarterly report for USDOE electric and hybrid vehicle research. Its mission now includes the three major activity categories of advancement of electric vehicle (EV) technologies, development of infrastructure elements needed to support significant EV use and increasing public awareness and acceptance of EVs. The 11 Site Operator Program participants, their geographic locations, and the principal thrusts of their efforts are identified. The EV inventories of the site operators totals about 250 vehicles. The individual fleets are summarized.

200-BP-5 operable unit Technical Baseline report

International Nuclear Information System (INIS)

Jacques, I.D.; Kent, S.K.

1991-10-01

This report supports development of a remedial investigation/feasibility study work plan for the 200-BP-5 operable unit. The report summarizes baseline information for waste sites and unplanned release sites located in the 200-BP-5 operable unit. The sites were investigated by the Technical Baseline Section of the Environmental Engineering Group, Westinghouse Hanford Company (Westinghouse Hanford). The investigation consisted of review and evaluation of current and historical Hanford Site reports, drawings, and photographs, and was supplemented with recent inspections of the Hanford Site and employee interviews. No field investigations or sampling were conducted

Unpacking Referent Units in Fraction Operations

Science.gov (United States)

Philipp, Randolph A.; Hawthorne, Casey

2015-01-01

Although fraction operations are procedurally straightforward, they are complex, because they require learners to conceptualize different units and view quantities in multiple ways. Prospective secondary school teachers sometimes provide an algebraic explanation for inverting and multiplying when dividing fractions. That authors of this article…

Centrifugal microfluidic platforms: advanced unit operations and applications.

Science.gov (United States)

Strohmeier, O; Keller, M; Schwemmer, F; Zehnle, S; Mark, D; von Stetten, F; Zengerle, R; Paust, N

2015-10-07

Centrifugal microfluidics has evolved into a mature technology. Several major diagnostic companies either have products on the market or are currently evaluating centrifugal microfluidics for product development. The fields of application are widespread and include clinical chemistry, immunodiagnostics and protein analysis, cell handling, molecular diagnostics, as well as food, water, and soil analysis. Nevertheless, new fluidic functions and applications that expand the possibilities of centrifugal microfluidics are being introduced at a high pace. In this review, we first present an up-to-date comprehensive overview of centrifugal microfluidic unit operations. Then, we introduce the term "process chain" to review how these unit operations can be combined for the automation of laboratory workflows. Such aggregation of basic functionalities enables efficient fluidic design at a higher level of integration. Furthermore, we analyze how novel, ground-breaking unit operations may foster the integration of more complex applications. Among these are the storage of pneumatic energy to realize complex switching sequences or to pump liquids radially inward, as well as the complete pre-storage and release of reagents. In this context, centrifugal microfluidics provides major advantages over other microfluidic actuation principles: the pulse-free inertial liquid propulsion provided by centrifugal microfluidics allows for closed fluidic systems that are free of any interfaces to external pumps. Processed volumes are easily scalable from nanoliters to milliliters. Volume forces can be adjusted by rotation and thus, even for very small volumes, surface forces may easily be overcome in the centrifugal gravity field which enables the efficient separation of nanoliter volumes from channels, chambers or sensor matrixes as well as the removal of any disturbing bubbles. In summary, centrifugal microfluidics takes advantage of a comprehensive set of fluidic unit operations such as

Twenty years of operation of WWER 440/230 units in Jaslovske Bohunice

International Nuclear Information System (INIS)

Tomek, J.

1998-01-01

It is twenty years this year since the first unit WWER 440 of Slovak Nuclear Power Plant Jaslovske Bohunice was commissioned. There are four units WWER 440 in operation Jaslovske Bohunice site. First two units of older soviet PWR design V-230 (also known as V-1) and other two units of newer V-213 type (also known as V-2). The goal of this presentation is to summarize and evaluate the operation of Unit 1 and 2 for this period of time and mainly to describe what has been done and what is planned to be done to increase the nuclear safety and operational reliability of both units. The operating organization and regulatory authority assume that an internationally acceptable level of safety will be reached by accomplishing of the upgrading program.(author)

Applications of Ecological Engineering Remedies for Uranium Processing Sites, USA

Energy Technology Data Exchange (ETDEWEB)

Waugh, William [Navarro Research and Engineering

2016-05-23

The U.S. Department of Energy (USDOE) is responsible for remediation of environmental contamination and long-term stewardship of sites associated with the legacy of nuclear weapons production during the Cold War in the United States. Protection of human health and the environment will be required for hundreds or even thousands of years at many legacy sites. USDOE continually evaluates and applies advances in science and technology to improve the effectiveness and sustainability of surface and groundwater remedies (USDOE 2011). This paper is a synopsis of ecological engineering applications that USDOE is evaluating to assess the effectiveness of remedies at former uranium processing sites in the southwestern United States. Ecological engineering remedies are predicated on the concept that natural ecological processes at legacy sites, once understood, can be beneficially enhanced or manipulated. Advances in tools for characterizing key processes and for monitoring remedy performance are demonstrating potential. We present test cases for four ecological engineering remedies that may be candidates for international applications.

A cooperative agreement for research on radioactive waste management between the United States Department of Energy and Atomic Energy of Canada Limited

International Nuclear Information System (INIS)

Dormuth, K.W.; Levich, R.A.

1994-01-01

The United States Department of Energy (USDOE) and Atomic Energy of Canada Limited (AECL) have a history of more than ten years of bilateral cooperation in the management of high level radioactive waste. In 1982, the USDOE and AECL executed a five year information-exchange agreement, for open-quotes Cooperation in Radioactive Waste Managementclose quotes. Since that time, this bilateral umbrella agreement has been renewed twice and the third renewal is currently being processed. International cooperation in high level radioactive waste management is highly beneficial to all concerned. Each nation involved in high level waste disposal has a single coordinated program for developing, testing, and evaluating approaches, hardware, and techniques for high level waste disposal. Thus there is limited opportunity for researchers in each country to exchange views regarding disposal technology with experienced researchers external to their own program, and to share research and development activities. The international arena, however, provides a host of organizations who have similar responsibilities and therefore similar interests and needs

Eielson Air Force Base Operable Unit 2 baseline risk assessment

Energy Technology Data Exchange (ETDEWEB)

Lewis, R.E.; Jarvis, T.T.; Jarvis, M.R.; Whelan, G.

1994-10-01

Operable Unit 2 at Eielson Air Force Base (AFB) near Fairbanks, is one of several operable units characterized by petroleum, oil, and lubricant contamination, and by the presence of organic products floating at the water table, as a result of Air Force operations since the 1940s. The base is approximately 19,270 acres in size, and comprises the areas for military operations and a residential neighborhood for military dependents. Within Operable Unit 2, there are seven source areas. These source areas were grouped together primarily because of the contaminants released and hence are not necessarily in geographical proximity. Source area ST10 includes a surface water body (Hardfill Lake) next to a fuel spill area. The primary constituents of concern for human health include benzene, toluene, ethylbenzene, and xylenes (BTEX). Monitored data showed these volatile constituents to be present in groundwater wells. The data also showed an elevated level of trace metals in groundwater.

Operational safety experience reporting in the United States

International Nuclear Information System (INIS)

Hartfield, R.A.

1978-01-01

Licensees of nuclear power plants in the United States have many reporting requirements included in their technical specifications and the code of federal regulations, title 10. The Nuclear Regulatory Commisson receives these reports and utilizes them in its regulatory program. Part of this usage includes collecting and publishing this operating experience data in various reports and storing information in various data systems. This paper will discuss the data systems and reports on operating experience published and used by the NRC. In addition, some observations on operating experience will be made. Subjects included will be the Licensee Event Report (LER) Data File, the Operating Unit Status Report (Gray Book), Radiation Exposure Reports, Effluents Reports, the Nuclear Plant Reliability Data System, Current Events, Bulletin Wrapups and Annual Summaries. Some of the uses of the reports and systems will be discussed. The Abnormal Occurence Report to the US Congress will also be described and discussed. (author)

US/DOE Man-Machine Integration program for liquid metal reactors

International Nuclear Information System (INIS)

D'Zmura, A.P.; Seeman, S.E.

1985-03-01

The United States Department of Energy (DOE) Man-Machine Integration program was started in 1980 as an addition to the existing Liquid Metal Fast Breeder Reactor safety base technology program. The overall goal of the DOE program is to enhance the operational safety of liquid metal reactors by optimum integration of humans and machines in the overall reactor plant system and by application of the principles of human-factors engineering to the design of equipment, subsystems, facilities, operational aids, procedures and environments. In the four years since its inception the program has concentrated on understanding the control process for Liquid Metal Reactors (LMRs) and on applying advanced computer concepts to this process. This paper describes the products that have been developed in this program, present computer-related programs, and plans for the future

200-UP-2 operable unit radiological surveys

International Nuclear Information System (INIS)

Wendling, M.A.

1994-01-01

This report summarizes and documents the results of the radiological surveys conducted from August 17 through December 16, 1993 over a partial area of the 200-UP-2 Operable Unit, 200-W Area, Hanford Site, Richland, Washington. In addition, this report explains the survey methodology of the Mobile Surface Contamination Monitor 11 (MSCM-II) and the Ultra Sonic Ranging And Data System (USRADS). The radiological survey of the 200-UP-2 Operable Unit was conducted by the Site Investigative Surveys/Environmental Restoration Health Physics Organization of the Westinghouse Hanford Company. The survey methodology for the majority of area was based on utilization of the MSCM-II or the USRADS for automated recording of the gross beta/gamma radiation levels at or near six (6) inches from the surface soil

Statement of Basis/Proposed Plan for the P-Area Burning Rubble Pit (131-P)

International Nuclear Information System (INIS)

Bland, T.

2002-01-01

The Statement of Basis/Proposed Plan (SB/PP) is being issued by the United States Department of Energy (USDOE), which functions as the lead agency for Savannah River Site (SRS) remedial activities, with concurrence by the United States Environmental Protection Agency (USEPA) and the South Carolina Department of Health and Environmental Control (SCDHEC). The purpose of this SB/PP is to describe the preferred remedial alternatives for the P-Area Burning/Rubble Pit (131-P) (PBRP) Operable Unit (OU) and to provide for public involvement in the decision-making process

Increasing the flexibility of base-load generating units in operation on fossil fuel

Energy Technology Data Exchange (ETDEWEB)

Girshfel' d, V Ya; Khanaev, V A; Volkova, E D; Gorelov, V A; Gershenkroi, M L

1979-01-01

Increasing the flexibility of base-load generating units operating on fossil fuel by modifying them is a necessary measure. The highest economic effect is attained with modification of gas- and oil-fired generating units in the Western United Power Systems of the European part of the SPSS. On the basis of available experience, 150- and 200-MW units can be extensively used to regulate the power in the European part of the SPSS through putting them into reserve for the hours of the load dip at night. The change under favorable conditions of 150- and 200-MW units operating on coal to a district-heating operating mode does not reduce the possibilities for flexible operation of these units because it is possible greatly to unload the turbines while the minimum load level of the pulverized fuel fired boiler is retained through transferring a part of the heat load to the desuperheater. It is necessary to accumulate and analyze experience with operation of generating units (especially of supercritical units) with regular shutdowns and starts of groups of units and to solve the problems of modification of generating units, with differentiation with respect to types of fuel and to the united power supply system.

Experiences with a Japanese-American fusion fuel processing hardware project

International Nuclear Information System (INIS)

Barnes, J.W.; Anderson, J.L.; Bartlit, J.R.; Carlson, R.V.; Konishi, S.; Inoue, M.; Naruse, Y.

1992-01-01

This paper reports that the United States Department of Energy (USDOE) and the Japan Atomic Energy Research Institute (JAERI) have installed a full-sale fuel cleanup system (JFCU) for testing at Los Alamos. The JFCU was designed by JAERI and built by Mitsubishi Heavy Industries (MHI) in Kobe, Japan. Experience gained by Japanese working at Los Alamos facilitated development of a system consistent with Los Alamos operations and standards. US or equivalent Japanese standards were generally used for design resulting in minor problems at electrical interfaces. Frequent written interchanges were essential to project success, as spoken communications can be misunderstood. Differing work styles required detailed pre-planning, separation of responsibilities, and daily scheduling meetings. Safety and operational documentation drafted by JAERI personnel was revised at Los Alamos to assure conformance with USDOE and Los Alamos standards. The project was successful because both Japanese and American participants worked hard to overcome potential problems. These experiences will be valuable in conducting future international fusion projects

100-KR-1 Operable Unit focused feasibility study report

International Nuclear Information System (INIS)

1994-11-01

The standard Comprehensive Environmental Response, Compensation, and Liability Act of 1980 Feasibility Study (FS) includes development and screening of alternatives and the detailed analysis of alternatives. This focused feasibility study (FFS) was conducted for the 100-KR-1 Operable Unit at the Hanford Site in southeastern Washington. The objective of this operable unit-specific FFS is to provide decision makers with sufficient information to allow appropriate and timely selection of interim remedial measures (IRM) for the five sites (116-K-1 crib, 116-K-2 trench, 116-KE-4 and 116-KW-3 retention basins, and process effluent pipelines) associated with the 100-KR-1 Operable Unit. The IRM candidate waste sites are determined in the limited field investigation. Site profiles are developed for each of these waste site. The site profiles are used in the application of the plug-in approach. The waste site either plugs into the analysis of the alternatives for the group, or deviations from the developed group alternatives are described and documented

Pioneer Robot Testing Program and Status

International Nuclear Information System (INIS)

Herndon, J.N.

2001-01-01

The U.S. Department of Energy (USDOE) and Ukraine established a joint program in 1997 to address the need for remotely operated systems for unstructured environments in Ukraine such as the highly hazardous conditions inside the failed Chernobyl Nuclear Power Plant (ChNPP) Unit 4, or Shelter Object. The environment inside Shelter Object is extremely hazardous due to ionizing radiation fields, high airborne contamination, and major industrial safety issues. Although Ukrainian workers have explored and mapped much of the internals of Unit 4 in the time since the accident during the morning hours of April 26, 1986, there remain areas where humans have not entered to this date. Based on the agreement between USDOE and Ukraine, the USDOE, in cooperation with the U.S. National Aeronautics and Space Administration (NASA), developed the Pioneer Robot and has provided it to the ChNPP within the framework of international technical assistance. Pioneer is capable of mobile platform movement and manipulation under teleoperated control, 3-dimensional mapping, and environmental data collection. The Pioneer is radiation hardened for conditions like those of Shelter Object. Pioneer has been evaluated on site in Ukraine for use in both the Shelter Object environment and the more general conditions of ChNPP decommissioning. This paper summarizes the results of these testing activities and describes the status and near-term activities in support of the Pioneer Robot integration into Ukraine

100 Area source operable unit focused feasibility study report. Draft A

International Nuclear Information System (INIS)

1994-09-01

In accordance with the Hanford Past-Practice Strategy (HPPS), a focused feasibility study (FFS) is performed for those waste sites which have been identified as candidates for interim remedial measures (IRM) based on information contained in applicable work plans and limited field investigations (LFI). The FFS process for the 100 Area source operable units will be conducted in two stages. This report, hereafter referred to as the Process Document, documents the first stage of the process. In this stage, IRM alternatives are developed and analyzed on the basis of waste site groups associated with the 100 Area source operable units. The second stage, site-specific evaluation of the IRM alternatives presented in this Process Document, is documented in a series of operable unit-specific reports. The objective of the FFS (this Process Document and subsequent operable unit-specific reports) is to provide decision makers with sufficient information to allow appropriate and timely selection of IRM for sites associated with the 100 Area source operable units. Accordingly, the following information is presented: a presentation of remedial action objectives; a description of 100 Area waste site groups and associated group profiles; a description of IRM alternatives; and detailed and comparative analyses of the IRM alternatives

2014 Highlights of Ferry Operations in the United States

Science.gov (United States)

2016-05-01

Based on information provided by operators who responded to the 2014 National Census of Ferry Operators (NCFO), the Bureau of Transportation Statistics (BTS) conservatively estimates that ferries in the United States carried just over 115 million pas...

HDS unit revamp and operating experience

Energy Technology Data Exchange (ETDEWEB)

Reinhardt, J. [Veba Oel Verarbeitungs-GmbH, Gelsenkirchen (Germany); Balfanz, U. [Aral Forschung, Gelsenkirchen (Germany); Dimmig, T. [TU Bergakademie Freiberg, Freiberg (Germany)

2002-12-01

Ruhr Oel GmbH, a joint venture between BP and PDVSA, operates a HDS unit at its Gelsenkirchen-Scholven site. The unit produces a major blend component for diesel fuel. Driven by ambitious German environmental policy and by an agreement between the German car and oil industries on the one hand and the government on the other, more stringent low sulphur fuel specifications will be enforced in Germany much earlier than in the rest of the European Union. In view of this situation a project was developed to fulfill the new product specifications with minimum investment. In a joint effort involving the refinery, the company research facilities and the catalyst supplier (AKZO NOBEL), pilot plant tests were performed to develop the best catalyst system and the new process conditions. Based on these results, an existing HDS unit was accordingly revamped. After the revamp, the unit produced diesel fuel with 50 ppm sulphur content and furthermore test runs at 10 ppm were carried out successfully. These results are displayed in this article. (orig.)

Simulation and operation of the EBR-II automatic control rod drive system

International Nuclear Information System (INIS)

Lehto, W.K.; Larson, H.A.; Dean, E.M.; Christensen, L.J.

1985-01-01

An automatic control rod drive system (ACRDS) installed at EBR-II produces shaped power transients from 40% to full reactor power at a linear ramp rate of 4 MWt/s. A digital computer and modified control-rod-drive provides this capability. Simulation and analysis of ACRDS experiments establish the safety envelope for reactor transient operation. Tailored transients are required as part of USDOE Operational Reliability Testing program for prototypic fast reactor fuel cladding breach behavior studies. After initial EBR-II driver fuel testing and system checkout, test subassemblies were subjected to both slow and fast transients. In addition, the ACRDS is used for steady-state operation and will be qualified to control power ascent from initial critical to full power

Simulation and operation of the EBR-II automatic control rod drive system

International Nuclear Information System (INIS)

Lehto, W.K.; Larson, H.A.; Dean, E.M.; Christensen, L.J.

1985-01-01

An automatic control rod drive system (ACRDS) installed at EBR-II produces shaped power transients from 40% to full reactor power at a linear ramp rate of 4 MWt/s. A digital computer and modified control-rod-drive provides this capability. Simulation and analysis of ACRDS experiments establish the safety envelope for reactor transient operation. Tailored transients are required as part of USDOE Operational Reliability Testing program for prototypic fast reactor fuel cladding breach behavior studies. After initial EBR-II driver fuel testing and system checkout, test subassemblies were subjected to both slow and fast transients. In additions, the ACRDS is used for steady-state operation and will be qualified to control power ascent from initial critical to full power

Joint operation of the TSTA under the collaboration between JAERI and U.S.-DOE

International Nuclear Information System (INIS)

Hayashi, Takumi; Konishi, Satoshi; Nakamura, Hirofumi

1993-03-01

A first complete integrated test of the J-FCU (JAERI Fuel Cleanup System) and the ISS (Isotope Separation System) with full four cryogenic distillation columns was performed successfully with 100 grams of tritium. This test was performed as a part of a 25 day TSTA extended loop run on April - May 1992. Through this operation, the J-FCU operated stably and safely. No significant problems was caused on the interaction between the J-FCU and the ISS. J-FCU processed more than 5 N1/min of simulated fusion-fuel exhaust with wide range of impurities and transferred pure hydrogen isotopes to the ISS and exhausted tritium free impurities to the TWT (Tritium Waste Treatment System) continuously. This report describes the detail result of the J-FCU part test under a 25 day TSTA extended loop run and discuss the JFCU performance. (author)

The role of PRA in the safety assessment of VVER Nuclear Power Plants in Ukraine

International Nuclear Information System (INIS)

Kot, C.

1999-01-01

Ukraine operates thirteen (13) Soviet-designed pressurized water reactors, VVERS. All Ukrainian plants are currently operating with annually renewable permits until they update their safety analysis reports (SARs), in accordance with new SAR content requirements issued in September 1995, by the Nuclear Regulatory Authority and the Government Nuclear Power Coordinating Committee of Ukraine. The requirements are in three major areas: design basis accident (DBA) analysis, probabilistic risk assessment (PRA), and beyond design-basis accident (BDBA) analysis. The last two requirements, on PRA and BDBA, are new, and the DBA requirements are an expanded version of the older SAR requirements. The US Department of Energy (USDOE), as part of its Soviet-Designed Reactor Safety activities, is providing assistance and technology transfer to Ukraine to support their nuclear power plants (NPPs) in developing a Western-type technical basis for the new SARs. USDOE sponsored In-Depth Safety Assessments (ISAs) are in progress at three pilot nuclear reactor units in Ukraine, South Ukraine Unit 1, Zaporizhzhya Unit 5, and Rivne Unit 1, and a follow-on study has been initiated at Khmenytskyy Unit 1. The ISA projects encompass most areas of plant safety evaluation, but the initial emphasis is on performing a detailed, plant-specific Level 1 Internal Events PRA. This allows the early definition of the plant risk profile, the identification of risk significant accident sequences and plant vulnerabilities and provides guidance for the remainder of the safety assessments

Phase 1 remedial investigation report for 200-BP-1 operable unit

International Nuclear Information System (INIS)

1993-09-01

The US Department of Energy (DOE) Hanford Site, in Washington State is organized into numerically designated operational areas including the 100, 200, 300, 400, 600, and 1100 Areas. The US Environmental Protection Agency (EPA), in November 1989 included the 200 Areas of the Hanford Site on the National Priority List (NPL) under the Comprehensive Environmental Response, Compensation and Liability Act of 1980 (CERCLA). Inclusion on the NPL initiated the remedial investigation (RD process for the 200-BP-1 operable unit. These efforts are being addressed through the Hanford Federal Facility Agreement and Consent Order (Ecology et al. 1989) which was negotiated and approved by the DOE, the EPA, and the State of Washington Department of Ecology (Ecology) in May 1989. This agreement, known as the Tri-Party Agreement, governs all CERCLA efforts at Hanford. In March of 1990, the Department of Energy, Richland Operations (DOE-RL) issued a Remedial Investigation/Feasibility Study (RI/FS) work plan (DOE-RL 1990a) for the 200-BP-1 operable unit. The work plan initiated the first phase of site characterization activities associated with the 200-BP-1 operable unit. The purpose of the 200-BP-1 operable unit RI is to gather and develop the necessary information to adequately understand the risks to human health and the environment posed by the site and to support the development and analysis of remedial alternatives during the FS. The RI analysis will, in turn, be used by Tri-Party Agreement signatories to make a risk-management-based selection of remedies for the releases of hazardous substances that have occurred from the 200-BP-1 operable unit

Environmental Control Plan for the 300-FF-1 Operable Unit Remedial Action

International Nuclear Information System (INIS)

Carlson, R.A.

2000-01-01

This environmental control plan is for the 300-FF-1 Operable Unit Remedial Action Project. The purpose of this plan is to identify environmental requirements for the 300-FF-1 operable unit Remedial Action/Waste Disposal Project

Phase I remedial investigation report for the 300-FF-5 operable unit, Volume 1

Energy Technology Data Exchange (ETDEWEB)

NONE

1994-01-01

The focus of this remedial investigation (RI) is the 300-FF-5 operable unit, one of five operable units associated with the 300 Area aggregate of the U.S. Department of Energy`s (DOE`s) Hanford Site. The 300-FF-5 operable unit is a groundwater operable unit beneath the 300-FF-1, 300-FF-2, and 300-FF-3 source operable units. This operable unit was designated to include all contamination detected in the groundwater and sediments below the water table that emanates from the 300-FF-1, 300-FF-2, and 300-FF-3 operable units (DOE-RL 1990a). In November 1989, the U.S. Environmental Protection Agency (EPA) placed the 300 Area on the National Priorities List (NPL) contained within Appendix B of the National Oil and Hazardous Substance Pollution Contingency Plan (NCP, 53 FR 51391 et seq.). The EPA took this action pursuant to their authority under the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA, 42 USC 9601 et seq.). The DOE Richland Operations Office (DOE-RL), the EPA and Washington Department of Ecology (Ecology) issued the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement), in May 1989 (Ecology et al. 1992, Rev. 2). This agreement, among other matters, governs all CERCLA efforts at the Hanford Site. In June 1990, a remedial investigation/feasibility study (RI/FS) workplan for the 300-FF-5 operable unit was issued pursuant to the Tri-Party Agreement.

Phase I remedial investigation report for the 300-FF-5 operable unit, Volume 1

International Nuclear Information System (INIS)

1994-01-01

The focus of this remedial investigation (RI) is the 300-FF-5 operable unit, one of five operable units associated with the 300 Area aggregate of the U.S. Department of Energy's (DOE's) Hanford Site. The 300-FF-5 operable unit is a groundwater operable unit beneath the 300-FF-1, 300-FF-2, and 300-FF-3 source operable units. This operable unit was designated to include all contamination detected in the groundwater and sediments below the water table that emanates from the 300-FF-1, 300-FF-2, and 300-FF-3 operable units (DOE-RL 1990a). In November 1989, the U.S. Environmental Protection Agency (EPA) placed the 300 Area on the National Priorities List (NPL) contained within Appendix B of the National Oil and Hazardous Substance Pollution Contingency Plan (NCP, 53 FR 51391 et seq.). The EPA took this action pursuant to their authority under the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA, 42 USC 9601 et seq.). The DOE Richland Operations Office (DOE-RL), the EPA and Washington Department of Ecology (Ecology) issued the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement), in May 1989 (Ecology et al. 1992, Rev. 2). This agreement, among other matters, governs all CERCLA efforts at the Hanford Site. In June 1990, a remedial investigation/feasibility study (RI/FS) workplan for the 300-FF-5 operable unit was issued pursuant to the Tri-Party Agreement

Preparation status for continuous operation of Kori unit 1 NPP in Korea

International Nuclear Information System (INIS)

Choi, C.H. . E-mail : chechee@khnp.co.kr

2005-01-01

Kori unit 1 Nuclear Power Plant is the first commercial operation plant in Korea. In Korea, the life extension of NPP beyond design lifetime reached practically application stage. Preparations status for continuous operation of Kori unit 1, Many researches have demonstrated that life extension beyond design lifetime is possible in terms of technology. This paper is to introduce and to share the continuous operation preparations status and schedule for Kori unit 1 License Renewal Process an additional every 10 years beyond the design life 30 years term. (author)

Biblis 1,300 MW unit B in operation for thirty years

International Nuclear Information System (INIS)

Lauer, H.

2006-01-01

Over the past thirty years, unit B of the Biblis nuclear power station has contributed towards safe, reliable and non-polluting electricity generation. Unit B was the first 1,300 MW unit in the world confirming the good experience accumulated in the construction and operation of plants this size. It laid the foundation for the advanced development of nuclear power plants up to the convoy line. The good availability this plant has achieved in its operating cycles proves the mature state of technology and the high level of qualification and motivation of the power plant staff and the personnel of external firms contracted to work for Biblis. Biblis B has served as a reference plant in German nuclear safety research, demonstrating that units this size can be operated safely. Unit B is also living proof of the possibility to raise nuclear power plants built in the seventies to the current state of the art by implementing the appropriate backfitting and modernization measures. Today, Biblis B is operated at a safety level clearly higher than that to be achieved for new plants internationally. This is also evident from comparison with the guiding values for the safety of new facilities as published by the International Atomic Energy Agency (IAEA). (orig.)

Expert system for operational personnel support during power unit operation control in regulation range

International Nuclear Information System (INIS)

Yanitskij, V.A.

1992-01-01

The problems met when developing the systems for NPP operator support in the process of power unit operation are considered. The expert system for NPP personnel intelligent support combining the properties belonging to the artificial intelligence systems including selection of the analysis method taking into account the concrete technological situation and capability of application of algothmic calculations of the equipment characteristics using the information accumulated during the system development, erection and operation is described

Stability Analysis for Operation of DG Units in Smart Grids

DEFF Research Database (Denmark)

Pouresmaeil, Edris; Shaker, Hamid Reza; Mehrasa, Majid

2015-01-01

This paper presents a multifunction control strategy for the stable operation of Distributed Generation (DG) units during grid integration. The proposed control model is based on Direct Lyapunov Control (DLC) theory and provides a stable region for the appropriate operation of DG units during grid....... Application of this concept can guarantee to reduce the stress on the grid during the energy demand peak. Simulation results are presented to demonstrate the proficiency and performance of the proposed DLC technique in DG technology....

Implementation of Active Learning Method in Unit Operations II Subject

OpenAIRE

Ma'mun, Sholeh

2018-01-01

ABSTRACT: Active Learning Method which requires students to take an active role in the process of learning in the classroom has been applied in Department of Chemical Engineering, Faculty of Industrial Technology, Islamic University of Indonesia for Unit Operations II subject in the Even Semester of Academic Year 2015/2016. The purpose of implementation of the learning method is to assist students in achieving competencies associated with the Unit Operations II subject and to help in creating...

Decommissioning strategy of the operating WWER type units in the Ukraine

International Nuclear Information System (INIS)

Litvinsky, L.L.; Lobach, Yu.N.; Skripov, A.E.

2002-01-01

At present in Ukraine, 13 WWER type units are in operation and two other ones are in the final stage of construction. Decommissioning of these units is expected after the year 2010. General planning of their decommissioning is developed in the framework of the decommissioning strategy of operating WWER type units. The strategy contains the objectives, principles and main tasks of the decommissioning as well as the activities at each phase of decommissioning. It is considered a broad range of factors important for the planning and implementation of decommissioning. (author)

Multi-unit Operations in Non-Nuclear Systems: Lessons Learned for Small Modular Reactors

Energy Technology Data Exchange (ETDEWEB)

OHara J. M.; Higgins, J.; DAgostino, A.

2012-01-17

The nuclear-power community has reached the stage of proposing advanced reactor designs to support power generation for decades to come. Small modular reactors (SMRs) are one approach to meet these energy needs. While the power output of individual reactor modules is relatively small, they can be grouped to produce reactor sites with different outputs. Also, they can be designed to generate hydrogen, or to process heat. Many characteristics of SMRs are quite different from those of current plants and may be operated quite differently. One difference is that multiple units may be operated by a single crew (or a single operator) from one control room. The U.S. Nuclear Regulatory Commission (NRC) is examining the human factors engineering (HFE) aspects of SMRs to support licensing reviews. While we reviewed information on SMR designs to obtain information, the designs are not completed and all of the design and operational information is not yet available. Nor is there information on multi-unit operations as envisioned for SMRs available in operating experience. Thus, to gain a better understanding of multi-unit operations we sought the lesson learned from non-nuclear systems that have experience in multi-unit operations, specifically refineries, unmanned aerial vehicles and tele-intensive care units. In this paper we report the lessons learned from these systems and the implications for SMRs.

Preparing nuclear power plant units for operation

International Nuclear Information System (INIS)

Hudcovic, R.; Telgarsky, K.; Kmosena, J.

1984-01-01

The factors are listed which have to be taken into consideration for planning the unit operation, i.e., the implementation of planned repairs, checks of equipment and refuellings. All basic input data were evaluated as the basic for drawing up the schedule of routine repairs and overhauls for the coming period. (E.S.)

Nurse managers' decision-making in daily unit operation in peri-operative settings: a cross-sectional descriptive study.

Science.gov (United States)

Siirala, Eriikka; Peltonen, Laura-Maria; Lundgrén-Laine, Heljä; Salanterä, Sanna; Junttila, Kristiina

2016-09-01

To describe the tactical and the operational decisions made by nurse managers when managing the daily unit operation in peri-operative settings. Management is challenging as situations change rapidly and decisions are constantly made. Understanding decision-making in this complex environment helps to develop decision support systems to support nurse managers' operative and tactical decision-making. Descriptive cross-sectional design. Data were collected from 20 nurse managers with the think-aloud method during the busiest working hours and analysed using thematic content analysis. Nurse managers made over 700 decisions; either ad hoc (n = 289), near future (n = 268) or long-term (n = 187) by nature. Decisions were often made simultaneously with many interruptions. Ad hoc decisions covered staff allocation, ensuring adequate staff, rescheduling surgical procedures, confirmation tangible resources and following-up the daily unit operation. Decisions in the near future were: planning of surgical procedures and tangible resources, and planning staff allocation. Long-term decisions were: human recourses, nursing development, supplies and equipment, and finances in the unit. Decision-making was vulnerable to interruptions, which sometimes complicated the managing tasks. The results can be used when planning decision support systems and when defining the nurse managers' tasks in peri-operative settings. © 2016 John Wiley & Sons Ltd.

Prospects and requirements for an operational modelling unit in flood crisis situations

Directory of Open Access Journals (Sweden)

Anders Katharina

2016-01-01

Full Text Available Dike failure events pose severe flood crisis situations on areas in the hinterland of dikes. In recent decades the importance of being prepared for dike breaches has been increasingly recognized. However, the pre-assessment of inundation resulting from dike breaches is possible only based on scenarios, which might not reflect the situation of a real event. This paper presents a setup and workflow that allows to model dike breachinduced inundation operationally, i.e. when an event is imminent or occurring. A comprehensive system setup of an operational modelling unit has been developed and implemented in the frame of a federal project in Saxony-Anhalt, Germany. The modelling unit setup comprises a powerful methodology of flood modelling and elaborated operational guidelines for crisis situations. Nevertheless, it is of fundamental importance that the modelling unit is instated prior to flood events as a permanent system. Moreover the unit needs to be fully integrated in flood crisis management. If these crucial requirements are met, a modelling unit is capable of fundamentally supporting flood management with operational prognoses of adequate quality even in the limited timeframe of crisis situations.

77 FR 62247 - Dynamic Positioning Operations Guidance for Vessels Other Than Mobile Offshore Drilling Units...

Science.gov (United States)

2012-10-12

... Operations Guidance for Vessels Other Than Mobile Offshore Drilling Units Operating on the U.S. Outer... ``Mobile Offshore Drilling Unit Dynamic Positioning Guidance''. The notice recommended owners and operators of Mobile Offshore Drilling Units (MODUs) follow Marine Technology Society (MTS) Dynamic Positioning...

Thunderstorm Algorithm for Determining Unit Commitment in Power System Operation

Directory of Open Access Journals (Sweden)

Arif Nur Afandi

2016-12-01

Full Text Available Solving the unit commitment problem is an important task in power system operation for deciding a balanced power production between various types of generating units under technical constraints and environmental limitations. This paper presents a new intelligent computation method, called the Thunderstorm Algorithm (TA, for searching the optimal solution of the integrated economic and emission dispatch (IEED problem as the operational assessment for determining unit commitment. A simulation using the IEEE-62 bus system showed that TA has smooth convergence and is applicable for solving the IEED problem. The IEED’s solution is associated with the total fuel consumption and pollutant emission. The proposed TA method seems to be a viable new approach for finding the optimal solution of the IEED problem.

Optimal operation of cogeneration units. State of art and perspective

International Nuclear Information System (INIS)

Polimeni, S.

2001-01-01

Optimal operation of cogeneration plants and of power plant fueling waste products is a complex challenge as they have to fulfill, beyond the contractual obligation of electric power supply, the constraints of supplying the required thermal energy to the user (for cogeneration units) or to burn completely the by-products of the industrial complex where they are integrated. Electrical power market evolution is pushing such units to a more and more volatile operation caused by uncertain selling price levels. This work intends to pinpoint the state of art in the optimization of these units outlining the important differences among the different size and cycles. The effect of the market liberalization on the automation systems and the optimization algorithms will be discussed [it

Analysis of Fukushima unit 2 accident considering the operating conditions of RCIC system

Energy Technology Data Exchange (ETDEWEB)

Kim, Sung Il, E-mail: sikim@kaeri.re.kr; Park, Jong Hwa; Ha, Kwang Soon; Cho, Song-Won; Song, JinHo

2016-03-15

Highlights: • Fukushima unit 2 accident was analyzed using MELCOR 1.8.6. • RCIC operating conditions were assumed and best case was selected. • Effect of RCIC operating condition on accident scenario was found. - Abstract: A severe accident in Fukushima occurred on March 11, 2011 and units 1, 2 and 3 were damaged severely. A tsunami following an earthquake made the supply of electricity power stop, and the safety systems, which use AC or DC power in plants could not operate properly. It is supposed that the degree of core degradation of unit 2 is less serious than in the other plants, and it was estimated that the operation of reactor core isolation cooling (RCIC) system at the initial stage of the accident minimized the core damage through decay heat removal. Although the operating conditions of the RCIC system are not known clearly, it can be important to analyze the accident scenario of unit 2. In this study, best case of the Fukushima unit 2 accident was presented considering the operating conditions of the RCIC system. The effects of operating condition on core degradation and fission product release rate to environment were also examined. In addition, importance of torus room flooding level in the accident analysis was discussed. MELCOR 1.8.6 was used in this research, and the geometries of plant and operating conditions of safety system were obtained from TEPCO through OECD/NEA BSAF Project.

Structural characterization and condition for measurement statistics preservation of a unital quantum operation

International Nuclear Information System (INIS)

Lee, Kai-Yan; Fung, Chi-Hang Fred; Chau, H F

2013-01-01

We investigate the necessary and sufficient condition for a convex cone of positive semidefinite operators to be fixed by a unital quantum operation ϕ acting on finite-dimensional quantum states. By reducing this problem to the problem of simultaneous diagonalization of the Kraus operators associated with ϕ, we can completely characterize the kinds of quantum states that are fixed by ϕ. Our work has several applications. It gives a simple proof of the structural characterization of a unital quantum operation that acts on finite-dimensional quantum states—a result not explicitly mentioned in earlier studies. It also provides a necessary and sufficient condition for determining what kind of measurement statistics is preserved by a unital quantum operation. Finally, our result clarifies and extends the work of Størmer by giving a proof of a reduction theorem on the unassisted and entanglement-assisted classical capacities, coherent information, and minimal output Renyi entropy of a unital channel acting on a finite-dimensional quantum state. (paper)

Limited field investigation report for the 100-KR-4 Operable Unit

International Nuclear Information System (INIS)

1994-07-01

This limited field investigation (LFI) was conducted to optimize the use of interim remedial measures (IRM) for expediting clean up while maintaining a technically sound and cost-effective program. The 100-KR-4 Operable Unit is one of four operable units associated with the 100 K Area. Operable units KR-1, KR-2 and KR-3 address contaminant sources while 100-KR-4 addresses contamination present in the underlying groundwater. The IRM decision process for groundwater operable units is based on three aspects: (1) Is the concentration greater than Hanford background? (2) Does the concentration present a medium or high human-health risk? (3) Does the concentration exceed an ecologically based applicable, relevant and appropriate requirements (ARAR) or present an environmental hazard quotient > I? The primary methods of investigation used during this LFI were the installation of monitoring wells and sampling of groundwater. The samples collected from the groundwater and soils were submitted for laboratory analysis. Boreholes were surveyed for radiological contamination using downhole geophysical techniques to further delineate the location and degree of contamination. All soil samples were screened to ascertain the presence of volatile organic compounds and radionuclides. Analytical data were subjected to validation; all first round and a minimum of 10% of subsequent round data were validated

Limited field investigation report for the 100-DR-1 Operable Unit

International Nuclear Information System (INIS)

1994-06-01

This limited field investigation (LFI) report summarizes the data collection and analysis activities conducted during the 100-DR-1 Source Operable Unite LFI and the associated qualitative risk assessment (QRA), and makes recommendations on the continued candidacy of high-priority sites for interim remedial measures (IRM). The results and recommendations presented in this report are generally independent of future land use scenarios. The 100-DR-1 Operable Unit is one of four operable units associated with the 100 D/DR Area at the Hanford Site. The 100-DR-1 Operable Unit encompasses approximately 1.5 km 2 (0.59 mi 2 ) and is located immediately adjacent to the Columbia River shoreline. In general, it contains waste facilities associated with the original plant facilities constructed to support D Reactor facilities, as well as cooling water retention basin systems for both D and DR Reactors. The 100-DR-1 LFI began the investigative phase of the remedial investigation for a select number of high-priority sites. The LFI was performed to provide additional data needed to support selection, design and implementation of IRM, if needed. The LFI included data compilation, nonintrusive investigations, intrusive investigations, summarization of 100 Area aggregate studies, and data evaluation

Integrated Ground Operations Demonstration Units Testing Plans and Status

Science.gov (United States)

Johnson, Robert G.; Notardonato, William U.; Currin, Kelly M.; Orozco-Smith, Evelyn M.

2012-01-01

Cryogenic propellant loading operations with their associated flight and ground systems are some of the most complex, critical activities in launch operations. Consequently, these systems and operations account for a sizeable portion of the life cycle costs of any launch program. NASA operations for handling cryogens in ground support equipment have not changed substantially in 50 years, despite advances in cryogenics, system health management and command and control technologies. This project was developed to mature, integrate and demonstrate advancement in the current state of the art in these areas using two distinct integrated ground operations demonstration units (GODU): GODU Integrated Refrigeration and Storage (IRAS) and GODU Autonomous Control

Operating experience with unit for sulfuric acid alkylation of isobutane by butylenes

Energy Technology Data Exchange (ETDEWEB)

Tagavov, I.T.; Sumanov, V.T.; Khadzhiev, S.N.

1988-09-01

The operation of units for the sulfuric acid alkylation of isobutanes by butylenes have been performed. The reaction was carried out in a KSG-3 horizontal sulfuric acid contractor. A butane-butylene fraction from catalytic cracking and an isobutane fraction from the central gas fractionating unit were used as a feedstock. The studies have shown that the unit will give a high-quality product under various conditions of operation. The specific consumption of sulfuric acid in processing different types of feed remains within acceptable limits.

2005 Annual Operations Report for INTEC Operable Unit 3-13, Group 1, Tank Farm Interim Action

International Nuclear Information System (INIS)

D. Shanklin

2006-01-01

This annual operations report describes the requirements followed and activities conducted to inspect, monitor, and maintain the items installed during performance of the Waste Area Group 3, Operable Unit 3-13, Group 1, Tank Farm Interim Action, at the Idaho Nuclear Technology and Engineering Center. This report describes inspection and monitoring activities for the surface-sealed areas within the tank farm, concrete-lined ditches and culverts in and around the tank farm, the lift station, and the lined evaporation pond. These activities are intended to assure that the interim action is functioning adequately to meet the objectives stated in the Operable Unit 3-13, Record of Decision for the Group 1, Tank Farm Interim Action, (DOE/ID-10660) and as amended by the agreement to resolve dispute, which was effective in February 2003

Limited field investigation report for the 100-HR-3 operable unit

International Nuclear Information System (INIS)

1994-09-01

This limited field investigation (LFI) was conducted to assess the applicability of interim remedial measures (IRM) for reducing human health and environmental risks within the 100-HR-3 Groundwater Operable Unit. The 100-HR-3 Operable Unit is comprised of three subareas; the 100 D Area, the 100 H Area and those portions of the 600 Area between the two reactor areas. The operable unit is one of seven operable units associated with the 100 D and H Areas. Operable units 100-DR-1, 100-DR-2, 100-DR-3, 100-HR-1, 100-HR-2 and 100-IU-4 address contaminant sources while 100-HR-3 addresses contamination present in the underlying groundwater. The primary method of field investigation used during this LFI was the installation and sampling of monitoring wells. Samples were collected from the groundwater and soils, and submitted for laboratory analysis. Boreholes were surveyed for radiological contamination using downhole geophysical techniques to further delineate the locations and levels of contaminants. All samples were screened to ascertain the presence of volatile organic compounds and radionuclides. Analytical data were subjected to validation; all round one, two and three and a minimum of 10% of round four data associated with the LFI were validated. A screening method was used to identify contaminants of potential concern (COPC). This screening method eliminated from further consideration, constituents that were below background. Constituents which are considered non-toxic to humans were eliminated from the human health evaluation. Data consistency and blank contamination were also evaluated in the screening process. These COPC were then evaluated further in the qualitative risk assessment (QRA). A human health QRA was performed using conservative (maximum equilibrated contaminant levels from the LFI) analyses

Limited field investigation report for the 100-HR-2 Operable Unit

International Nuclear Information System (INIS)

1994-09-01

This report summarizes the data collection and analysis activities conducted during the 100-HR-2 Operable Unit investigative phase and the associated qualitative risk assessment (QRA). The 100-HR-2 Operable Unit contains solid waste burial grounds, an ash pit, bum pits, electrical facilities, septic systems, and support facilities. All known and suspected areas of contamination were classified as solid waste burial grounds or low-priority waste sites based on the collective knowledge of the operable unit managers (representatives from the US Department of Energy [DOE], the US Environmental Protection Agency [EPA], and Washington Department of Ecology [Ecology]) during the preparation of the 100-HR-2 Operable Unit work plan (DOE/RL 1993f). Solid waste burial grounds were judged to pose sufficient risk(s), through one or more pathways, to require evaluation for an interim remedial measure (IRM) as per the Hanford Past-Practice Strategy (HPPS) (DOE/RL 1991) and negotiations with DOE, EPA, and Ecology. An IRM is intended to achieve remedies that are likely to lead to a final record of decision. Low-priority sites are those judged not to pose significant risk to require the streamlined evaluation. There were six low-priority waste sites and seven solid waste burial grounds identified. The investigative phase was conducted in accordance with the RCRA Facility Investigation/Corrective Measures Study Work Plan for the 100-HR-2 Operable Unit (DOE/RL 1993f). The QRA was performed in accordance with the Hanford Site Baseline Risk Assessment Methodology (DOE/RL 1993b) and the recommendations incorporate the strategies of the HPPS. The purpose of this report is to: (1) provide a summary of site investigative activities; (2) refine the conceptual exposure model (as needed); (3) identify chemical- and location-specific corrective action requirements; and (4) provide a human health and ecological QRA associated with solid waste burial grounds

Nuclear materials transportation workshops: USDOE outreach to local governments

International Nuclear Information System (INIS)

1987-01-01

To provide direct outreach to local governments, the Transportation Management Division of the United States Department of Energy asked the Urban Consortium and its Energy Task Force to assemble representatives for two workshops focusing on the transport of nuclear materials. The first session, for jurisdictions east of the Mississippi River, was held in New Orleans on May 5--6, 1988; the second was conducted on June 6--7, 1988 in Denver for jurisdictions to the west. Twenty local government professionals with management or operational responsibility for hazardous materials transportation within their jurisdictions were selected to attend each workshop. The discussions identified five major areas of concern to local government professionals; coordination; training; information resources; marking and placarding; and responder resources. Integrated federal, state, and local levels of government emerged as a priority coordination issue along with the need for expanded availability of training and training resources for first-reponders

Radioactive acid digestion test unit nonradioactive startup operations

International Nuclear Information System (INIS)

Allen, C.R.; Cowan, R.G.; Crippen, M.D.; Divine, J.R.

1978-05-01

The Radioactive Acid Digestion Test Unit (RADTU) will process 5 kg/hour of combustible solid waste and is designed to handle almost all solid combustible waste found in plutonium processing with plutonium contamination levels up to scrap. The RADTU is designed with special safety features to safely contain high masses of fissile materials and to safely handle unusual materials and reactive chemicals which may find their way into the waste. Nonradioactive operating experience to date has been very satisfactory. RADTU has been operated for extended runs on both a 24-hour per day basis as well as on a one shift per day basis. Some minor operating problems have been encountered as expected in a shakedown operation. In general, solutions to these have been readily found. 12 figures

Analysis of long-time operation of micro-cogeneration unit with fuel cell

Directory of Open Access Journals (Sweden)

Patsch Marek

2015-01-01

Full Text Available Micro-cogeneration is cogeneration with small performance, with maximal electric power up to 50 kWe. On the present, there are available small micro-cogeneration units with small electric performance, about 1 kWe, which are usable also in single family houses or flats. These micro-cogeneration units operate on principle of conventional combustion engine, Stirling engine, steam engine or fuel cell. Micro-cogeneration units with fuel cells are new progressive developing type of units for single family houses. Fuel cell is electrochemical device which by oxidation-reduction reaction turn directly chemical energy of fuel to electric power, secondary products are pure water and thermal energy. The aim of paper is measuring and evaluation of operation parameters of micro-cogeneration unit with fuel cell which uses natural gas as a fuel.

Multipurpose units: combining of technological operations of a soil cultivating and seeding

Directory of Open Access Journals (Sweden)

D. A. Petukhov

2015-01-01

Full Text Available The modern domestic market of technique for grain crops seeding differs variety of machines brands and types. The intensive type technologies combining technological operations of a soil cultivating and grain crops seeding in one pass are more widely used. The authors have established that one-operational units in new machine park have to be replaced multipurpose, universal and combined machines. Such approach will reduce number of machines in grain production from 20-30 to 5-6 name titles. Possibilities of multipurpose sowing units for simultaneous fertilizers application, soil cultivating and weeds destruction were analyzed. It was specified that nowadays there are several technologies types with two, four or six operations overlapping. Operational performance, technological and economical efficiency of the best multipurpose and also efficiency of technological operations overlapping at grain crops cultivating in the conditions of their real operation and at a trial establishment in the Kuban research institute of information and technical and economic studies of agro-industrial complex engineering and technical services were studied. Tit was defined that use of multipurpose sowing units and also studied efficiency of decreases operational costs by 48-71 percent, fuel consumption - by 41-76 percent and reduces labor input by 72-80 percent. Thus grain crops seeding is possible in optimal agrotime because of 4-6 technological operations overlapping in one pass.

Phase 1 remedial investigation report for 200-BP-1 operable unit. Volume 1

Energy Technology Data Exchange (ETDEWEB)

1993-09-01

The US Department of Energy (DOE) Hanford Site, in Washington State is organized into numerically designated operational areas including the 100, 200, 300, 400, 600, and 1100 Areas. The US Environmental Protection Agency (EPA), in November 1989 included the 200 Areas of the Hanford Site on the National Priority List (NPL) under the Comprehensive Environmental Response, Compensation and Liability Act of 1980 (CERCLA). Inclusion on the NPL initiated the remedial investigation (RD process for the 200-BP-1 operable unit. These efforts are being addressed through the Hanford Federal Facility Agreement and Consent Order (Ecology et al. 1989) which was negotiated and approved by the DOE, the EPA, and the State of Washington Department of Ecology (Ecology) in May 1989. This agreement, known as the Tri-Party Agreement, governs all CERCLA efforts at Hanford. In March of 1990, the Department of Energy, Richland Operations (DOE-RL) issued a Remedial Investigation/Feasibility Study (RI/FS) work plan (DOE-RL 1990a) for the 200-BP-1 operable unit. The work plan initiated the first phase of site characterization activities associated with the 200-BP-1 operable unit. The purpose of the 200-BP-1 operable unit RI is to gather and develop the necessary information to adequately understand the risks to human health and the environment posed by the site and to support the development and analysis of remedial alternatives during the FS. The RI analysis will, in turn, be used by Tri-Party Agreement signatories to make a risk-management-based selection of remedies for the releases of hazardous substances that have occurred from the 200-BP-1 operable unit.

Pressure Swing Adsorption in the Unit Operations Laboratory

Science.gov (United States)

Ganley, Jason

2018-01-01

This paper describes a student laboratory in the Unit Operations Laboratory at the Colorado School of Mines: air separation by pressure swing adsorption. The flexibility of the system enables students to study the production of enriched nitrogen or oxygen streams. Automatic data acquisition permits the study of cycle steps and performance.…

77 FR 29701 - Impact of Construction (Under a Combined License) of New Nuclear Power Plant Units on Operating...

Science.gov (United States)

2012-05-18

... New Nuclear Power Plant Units on Operating Units at Multi-Unit Sites AGENCY: Nuclear Regulatory... construct and operate new nuclear power plants (NPPs) on multi-unit sites to provide an evaluation of the... License) of New Nuclear Power Plants on Operating Units at Multi-Unit Sites (Package). ML112630039 Federal...

Remedial investigation/feasibility study work plan for the 100-KR-4 operable unit, Hanford Site, Richland, Washington

International Nuclear Information System (INIS)

1992-09-01

Four areas of the Hanford Site (the 100, 200, 300, and 1100 Areas) have been included on the US Environmental Protection Agency's (EPA's) National Priorities List (NPL) under the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA). This work plan and the attached supporting project plans establish the operable unit setting and the objectives, procedures, tasks, and schedule for conducting the CERCLA remedial investigation/feasibility study (RI/FS) for the 100-KR-4 operable unit. The 100-K Area consists of the 100-KR-4 groundwater operable unit and three source operable units. The 100-KR-4 operable unit includes all contamination found in the aquifer soils and water beneath the 100-K Area. Source operable units include facilities and unplanned release sites that are potential sources of contamination

Remedial investigation/feasibility study work plan for the 100-KR-4 operable unit, Hanford Site, Richland, Washington

Energy Technology Data Exchange (ETDEWEB)

1992-09-01

Four areas of the Hanford Site (the 100, 200, 300, and 1100 Areas) have been included on the US Environmental Protection Agency`s (EPA`s) National Priorities List (NPL) under the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA). This work plan and the attached supporting project plans establish the operable unit setting and the objectives, procedures, tasks, and schedule for conducting the CERCLA remedial investigation/feasibility study (RI/FS) for the 100-KR-4 operable unit. The 100-K Area consists of the 100-KR-4 groundwater operable unit and three source operable units. The 100-KR-4 operable unit includes all contamination found in the aquifer soils and water beneath the 100-K Area. Source operable units include facilities and unplanned release sites that are potential sources of contamination.

2006 Annual Operations Report for INTEC Operable Unit 3-13, Group 1, Tank Farm Interim Action

International Nuclear Information System (INIS)

D. E. Shanklin

2007-01-01

This annual operations report describes the requirements followed and activities conducted to inspect, monitor, and maintain the items installed during performance of the Waste Area Group 3, Operable Unit 3-13, Group 1, Tank Farm Interim Action, at the Idaho Nuclear Technology and Engineering Center. This report covers the time period from January 1 through December 31, 2006, and describes inspection and monitoring activities for the surface-sealed areas within the tank farm, concrete-lined ditches and culverts in and around the tank farm, the lift station, and the lined evaporation pond. These activities are intended to assure that the interim action is functioning adequately to meet the objectives stated in the Operable Unit 3-13, Record of Decision for the Group 1, Tank Farm Interim Action (DOE/ID-10660) as described in the Group 1 Remedial Design/Remedial Action Work Plan (DOE/ID-10772)

Tracking radioactive shipments using radio-navigation and satellite telecommunication systems

International Nuclear Information System (INIS)

Harmon, L.H.; Habib, E.J.; Hurley, J.D.; Carlson, R.D.

1988-01-01

The United States Department of Enegy (USDOE) Waste Transportation Management Division (WMTD) has commissioned the development of a transportation tracking management and communication system to monitor movement of radioactive material shipments throughout the United States. The system, TRANSCOM, is being developed to enhance DOE's management oversight and operational control over the transport of sensitive materials (e.g., spent fuel, highlevel waste, transuranic waste etc.) and to address state and local government concerns regarding public safety. These goals are accomplished through providing a near real time tracking and communication system complete with information database management to support emergency response capabilities

Effect of RCIC Operating Conditions on the Accident Scenario in Fukushima Unit 2

International Nuclear Information System (INIS)

Kim, Sung Il; Park, Jong Hwa; Ha, Kwang Soon

2015-01-01

This study was conducted by using MELCOR 1.8.6. Fukushima unit 2 accident was analyzed using MELCOR in this study, and best estimate scenario with considering RCIC operating conditions was presented. Researches on the boiling water reactor (BWR) plant with reactor core isolation cooling (RCIC) system have been conducted. Research on the RCIC operation in Fukushima unit 2 was also conducted by Sandia National Laboratory. MELCOR analysis of the Fukushima unit 2 accident was conducted in the report and energy balance in wetwell was described by considering RCIC operation. However, the effect of RCIC operation condition on the accident scenario has not been studied. The operating conditions of RCIC system affect the pressures in wetwell and drywell, and the high pressure can make leakage path of fission product from PCV to reactor building. Thus it can be directly related with the amount of fission product which released to environment. In this study, severe accident on Fukushima unit 2 was analyzed considering the operating condition of RCIC system, and best estimated scenario was presented. In addition, the effect of RCIC turbine efficiency on the accident progression was examined. Energy balance in suppression chamber was also considered with discussion on the effect of torus room flooding level. It was found that the operating condition of RCIC turbine not only affects the variation of drywell pressure but also the amount of released fission products to environment. It was also confirmed that the RCIC turbine efficiency in the accident would be less than normal operating condition

Brunswick Steam Electric Plant, Units 1 and 2. Annual operating report for 1976

International Nuclear Information System (INIS)

1977-01-01

Net electrical energy generated by Unit 1 was 30,399 MWH with the generator on line 334.5 hrs. Unit 2 generated 2,481,014 MWH with the generator on line 4,915.53 hrs. Information is presented concerning operations, shutdowns and power reductions, maintenance, power generation, modifications, changes to operational procedures, radiation exposures, and leak rate testing

Remedial investigation/feasibility study work plan for the 100-FR-3 operable unit, Hanford Site, Richland, Washington

International Nuclear Information System (INIS)

1992-09-01

Four areas of the Hanford Site (the 100, 200, 300, and 1100 Areas) have been included on the US Environmental Protection Agency's (EPA's) National Priorities List (NPL) under the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA). Figure 1-1 shows the location of these areas. Under the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement, Ecology et al. 1990a), signed by the Washington State Department of Ecology (Ecology), EPA, and the US Department of Energy (DOE), more than 1,000 inactive waste disposal and unplanned release sites on the Hanford Site have been grouped into a number of source and groundwater operable units. These operable units contain contamination in the form of hazardous waste, radioactive/hazardous mixed waste, and other CERCLA hazardous substances. This work plan and the attached supporting project plans establish the operable unit setting and the objectives, procedures, tasks, and schedule for conducting the CERCLA remedial investigation/feasibility study (RI/FS) for the 100-FR-3 operable unit. The 100-K Area consists of the 100-FR-3 groundwater operable unit and two source operable units. The 100-FR-3 operable unit includes all contamination found in the aquifer soils and water beneath the 100-F Area. Source operable units include facilities and unplanned release sites that are potential sources of contamination. A separate work plan has been initiated for the 100-FR-1 source operable unit (DOE-RL 1992a)

Remedial investigation/feasibility study work plan for the 100-FR-1 operable unit, Hanford Site, Richland, Washington

International Nuclear Information System (INIS)

1992-08-01

Four areas of the Hanford Site (the 100, 200,300, and 1100 Areas) have been included on the US Environmental Protection Agency's (EPA's) National Priorities List (NPL) under the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA). Under the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement, Ecology et al. 1990a), signed by the Washington State Department of Ecology (Ecology), EPA, and the US Department of Energy (DOE), more than 1,000 inactive waste disposal and unplanned release sites on the Hanford Site have been grouped into a number of source and groundwater operable units. These operable units contain contamination in the form of hazardous waste, radioactive/hazardous mixed waste, and other CERCLA hazardous substances. This work plan and the attached supporting project plans establish the objectives, procedures, tasks, and schedule for conducting the CERCLA remedial investigation/feasibility study (RI/FS) for the 100-FR-1 operable unit. The 100-FR-1 source operable unit is one of two source operable units in the 100-F Area. Source operable units include facilities and unplanned release sites that are potential sources of hazardous substance contamination. The groundwater affected or potentially affected by the entire 100-F Area is considered as a separate operable unit, the 100-FR-3 groundwater operable unit. A separate work plan has been initiated for the 100-FR-3 operable unit (DOE/RL 1992a)

Final record of decision for remedial actions at Operable Unit 4

International Nuclear Information System (INIS)

1994-12-01

This decision document presents the selected remedial action for Operable Unit 4 of the Fernald Site in Fernald, Ohio. This remedial action was selected in accordance with the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA), as amended by the Superfund Amendments and Reauthorization Act of 1986 (SARA), and to the extent practicable 40 Code of Federal Regulations (CFR) Part 300, the National Oil and Hazardous Substances Pollution Contingency Plan (NCP). For Operable Unit 4 at the FEMP, DOE has chosen to complete an integrated CERCLA/NEPA process. This decision was based on the longstanding interest on the part of local stakeholders to prepare an Environmental Impact Statement (EIS) on the restoration activities at the FEMP and on the recognition that the draft document was issued and public comments received. Therefore, this single document is intended to serve as DOE's Record of Decision (ROD) for Operable Unit 4 under both CERCLA and NEPA; however, it is not the intent of the DOE to make a statement on the legal applicability of NEPA to CERCLA actions

Qualitative risk assessment for the 100-HR-3 groundwater operable unit

Energy Technology Data Exchange (ETDEWEB)

Vukelich, S.E. [Golder Associates, Inc., Richland, WA (United States)

1994-09-22

This report provides the qualitative risk assessment for the 100-HR-3 operable unit on the Hanford Reservation. 100-HR-3 is a ground water unit. The purpose of the QRA at the 100-HR-3 operable unit is to focus on a predefined set of human and environmental exposure scenarios in order to provides sufficient information that will assist the Tri-Party signatories (Washington State Department of Ecology, EPA and US DOE) in making defensible decisions on the necessity of Interim Remedial Measures. Frequent- and occasional-use exposure scenarios are evaluated in the human health risk assessment to provide bounding estimates of risk. The ecological risk assessment consists of an evaluation of the risks to riparian and aquatic receptors which live in or near the Columbia River.

Qualitative risk assessment for the 100-HR-3 groundwater operable unit

International Nuclear Information System (INIS)

Vukelich, S.E.

1994-01-01

This report provides the qualitative risk assessment for the 100-HR-3 operable unit on the Hanford Reservation. 100-HR-3 is a ground water unit. The purpose of the QRA at the 100-HR-3 operable unit is to focus on a predefined set of human and environmental exposure scenarios in order to provides sufficient information that will assist the Tri-Party signatories (Washington State Department of Ecology, EPA and US DOE) in making defensible decisions on the necessity of Interim Remedial Measures. Frequent- and occasional-use exposure scenarios are evaluated in the human health risk assessment to provide bounding estimates of risk. The ecological risk assessment consists of an evaluation of the risks to riparian and aquatic receptors which live in or near the Columbia River

14 CFR 375.41 - Agricultural and industrial operations within the United States.

Science.gov (United States)

2010-01-01

... 14 Aeronautics and Space 4 2010-01-01 2010-01-01 false Agricultural and industrial operations... Agricultural and industrial operations within the United States. Foreign civil aircraft shall not be used for such commercial air operations as crop dusting, pest control, pipeline patrol, mapping, surveying...

Limited field investigation report for the 100-HR-2 Operable Unit

International Nuclear Information System (INIS)

1995-07-01

This report summarizes the data collection and analysis activities conducted during the 100-HR-2 Operable Unit investigative phase and the associated qualitative risk assessment. The 100-HR-2 Operable Unit contains solid waste burial grounds, an ash pit, burn pits, electrical facilities, septic systems, and support facilities. All known and suspected areas of contamination were classified as solid waste burial grounds or low-priority waste sites based on the collective knowledge of the operable unit managers (representatives from the US Department of Energy, the US Environmental Protection Agency, and Washington State Department of Ecology during the preparation of the 100-HR-2 Operable Unit Work Plan (DOE-RL 1993f). Solid waste burial grounds were judged to pose sufficient risk(s), through one or more pathways, to require evaluation for an interim remedial measure as per the Hanford Past-Practice Strategy (DOE-RL 1991) and negotiations with the Department of Energy, US Environmental Protection Agency, and Washington State Department of Ecology. An interim remedial measure is intended to achieve remedies that are likely to lead to a final record of decision. Low-priority sites are those judged not to pose significant risk to require the streamlined evaluation. There were six low-priority waste sites and seven solid waste burial grounds identified. The purpose of this report is to: (1) provide a summary of site investigative activities; (2) refine the conceptual exposure model (as needed); (3) identify chemical- and location-specific corrective action requirements; and 4) provide a human health and ecological QRA associated with solid waste burial grounds

Feasibility study report for Operable Unit 4: Volume 1

International Nuclear Information System (INIS)

1994-02-01

This report documents the Feasibility Study (FS) phase of the Fernald Environmental Management Project (FEMP) Operable Unit 4 Remedial Investigation/Feasibility Study (RI/FS) Program. The FEMP, formerly known as the Feed Materials Production Center (FMPC), is a US Department of Energy (DOE) facility that operated from 1952 to 1989. The facility's primarily function was to provide high purity uranium metal products to support United States defense programs. Production operations were suspended in 1989 to focus on environmental restoration and waste management activities at the facility. The RI/FS is being conducted pursuant to the terms of a Consent Agreement between DOE and the US Environmental Protection Agency (EPA) under Sections 120 and 106(a) of the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA), as amended. The Ohio Environmental Protection Agency (OEPA) is also participating in the RI/FS process at the FEMP through direct involvement in program review meetings and technical review of project documentation. The objective of the RI/FS process is to gather information to support an informed risk management decision regarding which remedy appears to be the most appropriate action for addressing the environmental concerns identified at the FEMP

Qualitative risk assessment for the 100-KR-4 groundwater operable unit

Energy Technology Data Exchange (ETDEWEB)

Biggerstaff, R.L.

1994-06-30

This report provides the qualitative risk assessment (QRA) for the 100-KR-4 groundwater operable unit at the US Department of Energy`s (DOE) Hanford Site in southeastern Washington State. The extent of the groundwater beneath the 100 K Area is defined in the Remedial Investigation/Feasibility Study Work Plan for the 100-KR-4 Operable Unit (DOE-RL 1992a). The QRA is an evaluation or risk using a limited amount of data and a predefined set of human and environmental exposure scenarios and is not intended to replace or be a substitute for a baseline risk assessment.

Qualitative risk assessment for the 100-KR-4 groundwater operable unit

International Nuclear Information System (INIS)

Biggerstaff, R.L.

1994-01-01

This report provides the qualitative risk assessment (QRA) for the 100-KR-4 groundwater operable unit at the US Department of Energy's (DOE) Hanford Site in southeastern Washington State. The extent of the groundwater beneath the 100 K Area is defined in the Remedial Investigation/Feasibility Study Work Plan for the 100-KR-4 Operable Unit (DOE-RL 1992a). The QRA is an evaluation or risk using a limited amount of data and a predefined set of human and environmental exposure scenarios and is not intended to replace or be a substitute for a baseline risk assessment

Remedial investigation/feasibility study work plan for the 100-BC-5 Operable Unit, Hanford Site, Richland, Washington

International Nuclear Information System (INIS)

1992-04-01

Four areas of the Hanford Site (the 100, 200, 300 and 1100 Areas) have been included on the US Environmental Protection Agency's (EPA's) National Priorities List (NPL) under the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA). Figure 1-1 shows the location of these areas. Under the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement, Ecology et al. 1990a), signed by the Washington State Department of Ecology (Ecology), EPA, and the US Department of Energy (DOE), more than 1,000 inactive waste disposal and unplanned release sites on the Hanford Site have been grouped into a number of source and groundwater operable units. These operable units contain contamination in the form of hazardous waste, radioactive/hazardous mixed waste and other CERCLA hazardous substances. Also included in the Tri-Party Agreement are 55 Resource Conservation and Recovery Act (RCRA) treatment, storage, or disposal (TSD) facilities that will be closed or permitted to operate in accordance with RCRA regulations, under the authority of Chapter 173-303 Washington Administrative Code (WAC). Some of the TSD facilities are included in the operable units. This work plant and the attached supporting project plans establish the operable unit setting and the objectives, procedures, tasks, and schedule for conducting the CERCLA remedial investigation/feasibility study (RI/FS) for the 100-BC-5 operable unit. The 100-B/C Area consists of the 100-BC-5 groundwater operable unit and four source operable units. The 100-BC-5 operable unit includes all contamination found in the aquifer soils and water beneath the 100-B/C Area. Source operable units include facilities and unplanned release sites that are potential sources of contamination

Training operators of VVER-1000 units in Eastern Europe

International Nuclear Information System (INIS)

Normand, X.; Nabet, E.; Hauesberger, P.

1996-01-01

The VVER 1000 is the most recent nuclear reactor designed in the former Soviet Union. Its design and operation principles are close to Western four-loop reactors in the 1000- to 1500-MW class; therefore, the Western simulation technology is usually directly applicable to the simulation of these units. Moreover, the current number of state-of-the-art training simulators in operation is very limited. A total of 19 units are in operation, while only 2 modern simulators are available (full-scope type) in Balakovo and Zaporozhe. Access to these simulators is practically limited to the respective plants' trainees, which means that the other units have to be satisfied with hands-on training. Facing this situation and taking into account the predicted lifetime of these plants (15 to 25 yr to go, maybe more), a lot of effort has been made in recent years to provide the plants with modern simulators. The major hurdles to this action were obviously financial and technical (availability of codes, computers, software tools). Today, one full-scope project (Kalinin) is almost complete, and three have been announced (Novovoronezh, Khmelnitsky, Kozloduy). Full-scope simulators are clearly the ultimate target of a concerned power plants. However, all users do realize the advantages of the complementary approach with compact simulators: 1. They can be available quickly for starting the training process. 2. They cover a training field that is not (or partly) addressed by full-scope simulators, i.e., the demonstration of physical phenomena in normal and accidental situations

Operative training in otolaryngology in the United Kingdom: a specialist registrar survey

NARCIS (Netherlands)

Georgalas, Christos; Hadjihannas, Edward; Ghufoor, Khalid; Pracy, Paul; Papesch, Michael

2005-01-01

OBJECTIVE: To assess the current status of operative training for otolaryngology specialist registrars in the United Kingdom. DESIGN: Web-based questionnaire survey. PARTICIPANTS: All otolaryngology specialist registrars in the United Kingdom. MAIN OUTCOME MEASURES: The overall satisfaction with

Level 1 shutdown and low power operation of Mochovce NPP, Unit 1, Slovakia

International Nuclear Information System (INIS)

Halada, P.; Cillik, I.; Stojka, T.; Kuzma, M.; Prochaska, J.; Vrtik, L.

2004-01-01

The paper presents general approach, used methods and form of documentation of the results that have been applied within the shutdown and low power PSA (SPSA) study for Mochovce NPP, Unit 1, Slovakia. The SPSA project was realized by VUJE Trnava Inc., Slovakia in 2001-2002 years. The Level 1 SPSA study for Mochovce NPP Unit 1 covers internal events as well as internal (fires, floods and heavy load drop) and external (aircraft crash, extreme meteorological conditions, seismic event and influence of surrounding industry) hazards. Mochovce NPP consists of two operating units equipped with VVER 440/V213 reactors safety upgraded before construction finishing and operation start. 87 safety measures based on VVER 440 operational experience and international mission insights were implemented to enhance its operational and nuclear safety. The SPSA relates to full power PSA (FPSA) as a continuation of the effort to create a harmonized level 1 PSA model for all operational modes of the plant with the goal to use it for further purposes as follows: Real Time Risk Monitor, Maintenance Optimization, Technical Specifications Optimization, Living PSA. (author)

Remedial investigation/feasibility study work plan for the 100-BC-5 operable unit, Hanford Site, Richland, Washington

International Nuclear Information System (INIS)

1992-07-01

Four areas of the Hanford Site (the 100, 200, 300, and 1100 Areas) have been included on the US Environmental Protection Agency's (EPA's) National Priorities List (NPL) under the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA). The Tri-Party Agreement requires that the cleanup programs at the Hanford Site integrate the requirements of CERCLA, RCRA, and Washington State's dangerous waste (the state's RCRA-equivalent) program. This work plan and the attached supporting project plans establish the operable unit setting and the objectives, procedures, tasks, and schedule for conducting the CERCLA remedial investigation/feasibility study (RI/FS) for the 100-BC-5 operable unit. The 100-B/C Area consists of the 100-BC-5 groundwater operable unit and four source operable units. The 100-BC-5 operable unit includes all contamination found in the aquifer soils and water beneath the 100-B/C Area. Source operable units include facilities and unplanned release sites that are potential sources of contamination

WTP Waste Feed Qualification: Glass Fabrication Unit Operation Testing Report

Energy Technology Data Exchange (ETDEWEB)

Stone, M. E. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL). Hanford Missions Programs; Newell, J. D. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL). Process Technology Programs; Johnson, F. C. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL). Engineering Process Development; Edwards, T. B. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL). Engineering Process Development

2016-07-14

The waste feed qualification program is being developed to protect the Hanford Tank Waste Treatment and Immobilization Plant (WTP) design, safety basis, and technical basis by assuring waste acceptance requirements are met for each staged waste feed campaign prior to transfer from the Tank Operations Contractor to the feed receipt vessels inside the Pretreatment Facility. The Waste Feed Qualification Program Plan describes the three components of waste feed qualification: 1. Demonstrate compliance with the waste acceptance criteria 2. Determine waste processability 3. Test unit operations at laboratory scale. The glass fabrication unit operation is the final step in the process demonstration portion of the waste feed qualification process. This unit operation generally consists of combining each of the waste feed streams (high-level waste (HLW) and low-activity waste (LAW)) with Glass Forming Chemicals (GFCs), fabricating glass coupons, performing chemical composition analysis before and after glass fabrication, measuring hydrogen generation rate either before or after glass former addition, measuring rheological properties before and after glass former addition, and visual observation of the resulting glass coupons. Critical aspects of this unit operation are mixing and sampling of the waste and melter feeds to ensure representative samples are obtained as well as ensuring the fabrication process for the glass coupon is adequate. Testing was performed using a range of simulants (LAW and HLW simulants), and these simulants were mixed with high and low bounding amounts of GFCs to evaluate the mixing, sampling, and glass preparation steps in shielded cells using laboratory techniques. The tests were performed with off-the-shelf equipment at the Savannah River National Laboratory (SRNL) that is similar to equipment used in the SRNL work during qualification of waste feed for the Defense Waste Processing Facility (DWPF) and other waste treatment facilities at the

40 CFR 60.105a - Monitoring of emissions and operations for fluid catalytic cracking units (FCCU) and fluid coking...

Science.gov (United States)

2010-07-01

..., Catalytic Reforming Units, and Sulfur Recovery Units. (iii) The owner or operator shall install, operate... for fluid catalytic cracking units (FCCU) and fluid coking units (FCU). 60.105a Section 60.105a... and operations for fluid catalytic cracking units (FCCU) and fluid coking units (FCU). (a) FCCU and...

Remedial investigation/feasibility study work plan for the 100-BC-2 operable unit, Hanford Site, Richland, Washington

International Nuclear Information System (INIS)

1993-05-01

This work plan and attached supporting project plans establish the operable unit setting and the objectives, procedures, tasks, and schedule for conducting the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA) remedial investigation/feasibility study (RI/FS) for the 100-BC-2 operable unit in the 100 Area of the Hanford Site. The 100 Area is one of four areas at the Hanford Site that are on the US Environmental Protection Agency's (EPA) National Priorities List under CERCLA. The 100-BC-2 operable unit is one of two source operable units in the 100-B/C Area (Figure ES-1). Source operable units are those that contain facilities and unplanned release sites that are potential sources of hazardous substance contamination. The 100-BC-2 source operable unit contains waste sites that were formerly in the 100-BC-2, 100-BC-3, and 100-BC-4 operable units. Because of their size and geographic location, the waste sites from these two operable units were added to 100-BC-2. This allows for a more efficient and effective investigation of the remaining 100-B/C Reactor area waste sites. The investigative approach to waste sites associated with the 100-BC-2 operable unit are listed in Table ES-1. The waste sites fall into three general categories: high priority liquid waste disposal sites, low priority liquid waste disposal sites, and solid waste burial grounds. Several sites have been identified as candidates for conducting an IRM. Two sites have been identified as warranting additional limited field sampling. The two sites are the 116-C-2A pluto crib, and the 116-C-2C sand filter

Adaptation of Professional Skills in the Unit Operations Laboratory

Science.gov (United States)

Rende, Deniz; Rende, Sevinc; Baysal, Nihat

2012-01-01

We introduce the design of three consecutive unit operations laboratory (UOL) courses that retain the academic rigor of the course while incorporating skills essential for professional careers, such as ability to propose ideas, develop practical solutions, participate in teamwork, meet deadlines, establish communication between technical support…

Initial closed operation of the CELSS Test Facility Engineering Development Unit

Science.gov (United States)

Kliss, M.; Blackwell, C.; Zografos, A.; Drews, M.; MacElroy, R.; McKenna, R.; Heyenga, A. G.

2003-01-01

As part of the NASA Advanced Life Support Flight Program, a Controlled Ecological Life Support System (CELSS) Test Facility Engineering Development Unit has been constructed and is undergoing initial operational testing at NASA Ames Research Center. The Engineering Development Unit (EDU) is a tightly closed, stringently controlled, ground-based testbed which provides a broad range of environmental conditions under which a variety of CELSS higher plant crops can be grown. Although the EDU was developed primarily to provide near-term engineering data and a realistic determination of the subsystem and system requirements necessary for the fabrication of a comparable flight unit, the EDU has also provided a means to evaluate plant crop productivity and physiology under controlled conditions. This paper describes the initial closed operational testing of the EDU, with emphasis on the hardware performance capabilities. Measured performance data during a 28-day closed operation period are compared with the specified functional requirements, and an example of inferring crop growth parameters from the test data is presented. Plans for future science and technology testing are also discussed. Published by Elsevier Science Ltd on behalf of COSPAR.

100-HR-1 Operable Unit focused feasibility study report. Draft A

International Nuclear Information System (INIS)

1994-09-01

The standard Comprehensive Environmental Response, Compensation, and Liability Act of 1980 Feasibility Study (FS) includes development and screening of alternatives (phases 1 and 2) and the detailed analysis of alternatives (phase 3). This focused feasibility study (FFS) constitutes the phase 3 portion of the FS process. The FFS process is conducted in two stages, a Process Document (DOE-RL 1994a) and an operable unit-specific FFS document, such as this one. The FFS process is performed by implementing a ''plug-in'' style approach as defined in great detail in the Process Document. The objective of this operable unit-specific FFS is to provide decision makers with sufficient information to allow appropriate and timely selection of interim remedial measures (IRM) for sites associated with the 100-HR-1 Operable Unit. The IRM candidate waste sites are determined in the limited field investigation. Site profiles are developed for each of these waste sites. The site profiles are used in the application of the plug-in approach. The waste site either plugs into the analysis of the alternatives for the group, or deviations from the developed group alternatives are described and documented

Operational behaviour of WWER nuclear power units after Chernobyl accident

International Nuclear Information System (INIS)

Milivojevic, S.; Spasojevic, D.

2000-01-01

The indicators of effectiveness of WWER operation, in 1987-1998 were analyzed. For three groups of nuclear units (WWER, NPP Kozloduy, NPP Paks), the trends of Indicators flow were established. The comparative analysis of forced outage rate, and load factor of WWERs and nuclear units all in the world was carried out; it gives the general picture of accident influence on the states and the relations of these indicators in considered period (author)

H. B. Robinson Plant, Unit 2. Annual operating report for 1976

International Nuclear Information System (INIS)

1977-01-01

The unit achieved a good performance record through the year, experiencing only short duration shutdowns or power reductions. Information is presented concerning operations, maintenance, shutdowns, and occupational radiation exposures. In November there was a scheduled refueling lasting 40 days. After a start-up physics test program, the unit achieved 100 percent power on December 22, 1976

Physical decommissioning of the Shippingport Atomic Power Station

International Nuclear Information System (INIS)

Crimi, F.P.

1988-01-01

The Shippingport Atomic Power Station consists of the nuclear steam supply system and associated radioactive waste processing systems, which are owned by the United States Department of Energy (USDOE), and the turbine-generator and balance of plant which is owned by the Duquesne Light Company. The station is located at Shippingport, Pennsylvania on seven acres of land leased by USDOE from the Duquesne Light Company. The Shippingport Station Decommissioning Project (SSDP) is being managed for the USDOE by the General Electric Company and its integated subcontractor, Morrison Knudsen-Ferguson (MK-F) Company. The objectives of the Shippingport Station Decommissioning Project (SSDP) are to: Demonstrate the safe and cost effective dismantlement of a large scale nuclear power plant; Provide useful data for future decommissioning projects

Superfund Record of Decision (EPA Region 7): Weldon Spring Quarry/Plant/Pits (USDOE), Weldon Spring, MO. (Second remedial action), September 1990

International Nuclear Information System (INIS)

1990-01-01

The 226-acre Weldon Spring Quarry/Plant/Pits (USDOE) site is a former ordnance works and chemical plant near the city of Weldon Spring in St. Charles County, Missouri. The site is divided into two noncontiguous areas: a 217-acre chemical plant area, comprised of various buildings, ponds and four raffinate pits, and a 9-acre quarry, which forms a valley wall at the edge of the Missouri River floodplain. Since the early 1940s, the site has been used by various government agencies for chemical and ordnance processing with chemical and radioactive waste disposal in the quarry. From 1941 to 1946, the site was an Army ordnance works used for the production of trinitrotoluene (TNT) and dinitrotoluene (DNT) explosives. The selected interim remedial action for the site includes excavating an estimated 95,000 cubic yards of chemically and radioactively contaminated bulk wastes from the quarry and temporarily storing the wastes onsite in the chemical plant area; and implementing site access restrictions. The estimated total cost for the remedial action is $11,000,000

40 CFR 62.15145 - What are the operating practice requirements for my municipal waste combustion unit?

Science.gov (United States)

2010-07-01

... requirements for my municipal waste combustion unit? 62.15145 Section 62.15145 Protection of Environment... Combustion Units Constructed on or Before August 30, 1999 Good Combustion Practices: Operating Requirements § 62.15145 What are the operating practice requirements for my municipal waste combustion unit? (a) You...

Feasibility study report for Operable Unit 4: Volume 2

International Nuclear Information System (INIS)

1994-02-01

This report documents the Feasibility Study (FS) phase of the Fernald Environmental Management Project (FEMP) Operable Unit 4 Remedial Investigation/Feasibility Study (RI/FS) Program. The FEMP, formerly known as the Feed Materials Production Center (FMPC), is a US Department of Energy (DOE) facility that operated from 1952 to 1989. The facility's primarily function was to provide high purity uranium metal products to support United States defense programs. Production operations were suspended in 1989 to focus on environmental restoration and waste management activities at the facility. The RI/FS is being conducted pursuant to the terms of a Consent Agreement between DOE and the US Environmental Protection Agency (EPA) under Sections 120 and 106(a) of the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA), as amended. The Ohio Environmental Protection Agency (OEPA) is also participating in the RI/FS process at the FEMP through direct involvement in program review meetings and technical review of project documentation. The objective of the RI/FS process is to gather information to support an informed risk management decision regarding which remedy appears to be the most appropriate action for addressing the environmental concerns identified at the FEMP. This volume contains appendices A--E

Pilot-scale treatability test plan for the 200-UP-1 groundwater Operable Unit

International Nuclear Information System (INIS)

Wittreich, C.D.

1994-05-01

This document presents the treatability test plan for pilot-scale pump and treat testing at the 200-UP-1 Operable Unit. This treatability test plan has been prepared in response to an agreement between the US Department of Energy, the US Environmental Protection Agency, and the Washington State Department of Ecology, as documented in Hanford Federal Facility Agreement and Consent Order (Ecology et al. 1989a) Change Control Form M-13-93-03 (Ecology et al. 1994). The agreement also requires that, following completion of the activities described in this test plan, a 200-UP-1 Operable Unit interim remedial measure (IRM) proposed plan be developed for use in preparing an interim action record of decision (ROD). The IRM Proposed Plan will be supported by the results of the testing described in this treatability test plan, as well as by other 200-UP-1 Operable Unit activities (e.g., limited field investigation, development of a qualitative risk assessment). Once issued, the interim action ROD will specify the interim action for groundwater contamination at the 200-UP-1 Operable Unit. The approach discussed in this treatability test plan is to conduct a pilot-scale pump and treat test for the contaminant plume associated with the 200-UP-1 Operable Unit. Primary contaminants of concern are uranium and technetium-99; the secondary contaminant of concern is nitrate. The pilot-scale treatability testing presented in this test plan has as its primary purpose to assess the performance of aboveground treatment systems with respect to the ability to remove the primary contaminants in groundwater withdrawn from the contaminant plume

An Appraisal Of The Operation And Management Of Unit Trust ...

African Journals Online (AJOL)

An Appraisal Of The Operation And Management Of Unit Trust Schemes In Nigeria. ... Open Access DOWNLOAD FULL TEXT ... instead of being invested in shares or in money market instruments as a result of widespread financial illiteracy.

Lessons learned from the 1994 Northridge Earthquake

International Nuclear Information System (INIS)

Eli, M.W.; Sommer, S.C.

1995-01-01

Southern California has a history of major earthquakes and also has one of the largest metropolitan areas in the United States. The 1994 Northridge Earthquake challenged the industrial facilities and lifetime infrastructure in the northern Los Angeles (LA) area. Lawrence Livermore National Laboratory (LLNL) sent a team of engineers to conduct an earthquake damage investigation in the Northridge area, on a project funded jointly by the United States Nuclear Regulatory Commission (USNRC) and the United States Department of Energy (USDOE). Many of the structures, systems, and components (SSCs) and lifelines that suffered damage are similar to those found in nuclear power plants and in USDOE facilities. Lessons learned from these experiences can have some applicability at commercial nuclear power plants

An Analysis of United States Marine Corps Enlisted Entry-Level Training Using Supply Chain and Operations Management

Science.gov (United States)

2010-12-01

An Analysis of United States Marine Corps Enlisted Entry-Level Training Using Supply Chain and Operations Management ______________________________________ By...Report 4. TITLE AND SUBTITLE: An Analysis of United States Marine Corps Enlisted Entry-Level Training Using Supply Chain and Operations Management 6...Level Training; United States Marine Corps; Operations Management ; Supply Chain Management; Process Analysis 16. PRICE CODE 17. SECURITY

Pilot-scale treatability test plan for the 200-BP-5 operable unit

International Nuclear Information System (INIS)

1994-08-01

This document presents the treatability test plan for pilot-scale pump and treat testing at the 200-BP-5 Operable Unit. This treatability test plan has been prepared in response to an agreement between the U.S. Department of Energy (DOE), the U.S. Environmental Protection Agency (EPA), and the State of Washington Department of Ecology (Ecology), as documented in Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement, Ecology et al. 1989a) Change Control Form M-13-93-03 (Ecology et al. 1994) and a recent 200 NPL Agreement Change Control Form (Appendix A). The agreement also requires that, following completion of the activities described in this test plan, a 200-BP-5 Operable Unit Interim Remedial Measure (IRM) Proposed Plan be developed for use in preparing an Interim Action Record of Decision (ROD). The IRM Proposed Plan will be supported by the results of this treatability test plan, as well as by other 200-BP-5 Operable Unit activities (e.g., development of a qualitative risk assessment). Once issued, the Interim Action ROD will specify the interim action(s) for groundwater contamination at the 200-BP-5 Operable Unit. The treatability test approach is to conduct a pilot-scale pump and treat test for each of the two contaminant plumes associated with the 200-BP-5 Operable Unit. Primary contaminants of concern are 99 Tc and 60 Co for underwater affected by past discharges to the 216-BY Cribs, and 90 Sr, 239/240 Pu, and Cs for groundwater affected by past discharges to the 216-B-5 Reverse Well. The purpose of the pilot-scale treatability testing presented in this testplan is to provide the data basis for preparing an IRM Proposed Plan. To achieve this objective, treatability testing must: Assess the performance of groundwater pumping with respect to the ability to extract a significant amount of the primary contaminant mass present in the two contaminant plumes

Control technique for enhancing the stable operation of distributed generation units within a microgrid

International Nuclear Information System (INIS)

Mehrasa, Majid; Pouresmaeil, Edris; Mehrjerdi, Hasan; Jørgensen, Bo Nørregaard; Catalão, João P.S.

2015-01-01

Highlights: • A control technique for enhancing the stable operation of distributed generation units is proposed. • Passivity-based control technique is considered to analyze the dynamic and steady-state behaviors. • The compensation of instantaneous variations in the reference current components is considered. • Simulation results confirm the performance of the control scheme within the microgrid. - Abstract: This paper describes a control technique for enhancing the stable operation of distributed generation (DG) units based on renewable energy sources, during islanding and grid-connected modes. The Passivity-based control technique is considered to analyze the dynamic and steady-state behaviors of DG units during integration and power sharing with loads and/or power grid, which is an appropriate tool to analyze and define a stable operating condition for DG units in microgrid technology. The compensation of instantaneous variations in the reference current components of DG units in ac-side, and dc-link voltage variations in dc-side of interfaced converters, are considered properly in the control loop of DG units, which is the main contribution and novelty of this control technique over other control strategies. By using the proposed control technique, DG units can provide the continuous injection of active power from DG sources to the local loads and/or utility grid. Moreover, by setting appropriate reference current components in the control loop of DG units, reactive power and harmonic current components of loads can be supplied during the islanding and grid-connected modes with a fast dynamic response. Simulation results confirm the performance of the control scheme within the microgrid during dynamic and steady-state operating conditions

Soil washing physical separations test procedure - 300-FF-1 operable unit

Energy Technology Data Exchange (ETDEWEB)

Belden, R.D.

1993-10-08

This procedure provides the operations approach, a field sampling plan, and laboratory procedures for a soil washing test to be conducted by Alternative Remedial Technologies, Inc. (ART) in the 300-FF-1 area at the Hanford site. The {open_quotes}Quality Assurance Project Plan for the Soil Washing Physical Separations Test, 300-FF-1 Operable Unit,{close_quotes} Hanford, Washington, Alternative Remedial Technologies, Inc., February 1994 (QAPP) is provided in a separate document that presents the procedural and organizational guidelines for this test. This document describes specifications, responsibilities, and general procedures to be followed to conduct physical separation soil treatability tests in the North Process Pond of the 300-FF-1 Operable Unit (OU) at the Hanford Site. These procedures are based on the {open_quotes}300-FF-1 Physical Separations CERCLA Treatability Test Plan, DOE/RL 92-2l,{close_quotes} (DOE-RL 1993).

Soil washing physical separations test procedure - 300-FF-1 operable unit

International Nuclear Information System (INIS)

Belden, R.D.

1993-01-01

This procedure provides the operations approach, a field sampling plan, and laboratory procedures for a soil washing test to be conducted by Alternative Remedial Technologies, Inc. (ART) in the 300-FF-1 area at the Hanford site. The open-quotes Quality Assurance Project Plan for the Soil Washing Physical Separations Test, 300-FF-1 Operable Unit,close quotes Hanford, Washington, Alternative Remedial Technologies, Inc., February 1994 (QAPP) is provided in a separate document that presents the procedural and organizational guidelines for this test. This document describes specifications, responsibilities, and general procedures to be followed to conduct physical separation soil treatability tests in the North Process Pond of the 300-FF-1 Operable Unit (OU) at the Hanford Site. These procedures are based on the open-quotes 300-FF-1 Physical Separations CERCLA Treatability Test Plan, DOE/RL 92-2l,close quotes (DOE-RL 1993)

Operating experience with nuclear power stations in Member States in 2002

International Nuclear Information System (INIS)

2003-11-01

This report is the thirty-fourth in the Agency's series of annual reports on operating experience with nuclear power stations in Member States. The report is a direct output from the Agency's Power Reactor Information System (PRIS), whose database contains all operating experience data published in the Agency's operating experience annual reports since 1971 and basic information on power reactors, including design data. It presents operating experience data for all worldwide nuclear power plants after starting commercial operation. The PRIS databank is available free of charge to IAEA Member States through its two services: PRIS-PC and MicroPRIS. The PRIS-PC allows direct access to the database via telephone lines or through the Internet. The MicroPRIS contains a subset of the PRIS database and is a personal computer version of PRIS data available on diskette in a form readily accessible by standard, commercially available personal computer packages. PRIS is also available in the Internet at http://www.iaea.org/programmes/a2. Load, operation and availability factors are used as the basic performance factors. Energy unavailability factors, separate for planned and unplanned unavailability, due either to causes in the plant or causes external to the plant, are used as a measure of energy lost through a unit not being available. However, some ambiguity remains in the operator reports of the unavailability data, resulting in inconsistencies in these factors. It is recognized that there is an inherent difficulty in reporting unavailability in energy with relation to a maximum capacity which may change several times during the year. In addition, there are different practices in reporting planned and unplanned unavailability among Member States. The unavailability factors in this report should therefore be used with caution. It should be noted that, for load, operation and unavailability factors, there might be differences between the data of this report and those

RCRA facility investigation/corrective measures study work plan for the 100-HR-1 operable unit, Hanford Site, Richland, Washington

International Nuclear Information System (INIS)

1992-09-01

Four areas of the Hanford Site (the 100, 200, 300, and 1100 Areas) have been included on the US. Environmental Protection Agency's (EPA's) National Priorities List (NPL) under the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA). Under the Hanford Federal Facility Agreement and Consent Order, signed by the Washington State Department of Ecology (Ecology), EPA, and the US Department of Energy (DOE), more than 1,000 inactive waste disposal and unplanned release sites on the Hanford Site have been grouped into a number of source and groundwater operable units. These operable units contain contamination in the form of hazardous waste, radioactive/hazardous mixed waste, and other CERCLA hazardous substances. This work plan and the attached supporting project plans establish the operable unit setting and the objectives, procedures, tasks, and schedule for conducting the RCRA facility investigation/corrective measures study (RFI/CMS) for the 100-HR-1 source operable unit. Source operable units include facilities and unplanned release sites that are potential sources of contamination. The 100-HR-3 operable unit underlies the D/DR and H Areas, the 600 Area between them, and the six source operable units these areas contain. The 100-HR-3 operable unit includes all contamination found in the aquifer soils and water within its boundary. Separate work plans have been initiated for the 100-HR-3 groundwater operable unit (DOE-RL 1992a) and the 100-DR-1 (DOE-RL 1992b) source operable units

Habitat Demonstration Unit Medical Operations Workstation Upgrades

Science.gov (United States)

Trageser, Katherine H.

2011-01-01

This paper provides an overview of the design and fabrication associated with upgrades for the Medical Operations Workstation in the Habitat Demonstration Unit. The work spanned a ten week period. The upgrades will be used during the 2011 Desert Research and Technology Studies (Desert RATS) field campaign. Upgrades include a deployable privacy curtain system, a deployable tray table, an easily accessible biological waste container, reorganization and labeling of the medical supplies, and installation of a retractable camera. All of the items were completed within the ten week period.

On Point: The United States Army in Operation Iraqi Freedom

Science.gov (United States)

2004-01-01

to retain operational context. Moreover, times noted in the text have been adjusted from Greenwich Mean Time (“ Zulu ”) to local Kuwait time (+ 3...TF 1-64 AR unit history is composed of short narratives for each subordinate unit. Most cite times in zulu . 34. Ibid. 35. Ibid. Numbers of enemy...places in the world. Inside the city cemetery is the Tomb of Ali, son-in-law and cousin to Mohammed and founder of the Shiite sect. Coalition leaders

Experimental determinations of the turbine condenser operation at Cernavoda NPP Unit 1

International Nuclear Information System (INIS)

Romascu, Gabriel; Dragusin, Dumitru; Rogociu, Ioan; Macodean, Luminita; Marciulescu, George

1999-01-01

The condenser system represents one of the most important BOP (balance of plant) systems of the CANDU 700 MW Unit at Cernavoda NPP. The paper presents theoretical calculation elements, mathematical model for simulation of condenser operation and the results obtained by model implementation as compared to operation data. The model could be adapted to other turbine and operation regime types. (authors)

Survey method for radiological surveys of 300 FF-1 Operable Unit soil and materials

International Nuclear Information System (INIS)

Greif, A.A.

1997-06-01

This technical basis document is to be used to survey soils at the 300-FF-1 Operable Unit during remediation of the site. Its purpose is to provide a basis for the survey methods to be employed by the Radiological Control Technician to determine if excavated areas require continued remediation in accordance with the Record of Decision for the operable unit

The role of heat pipes in intensified unit operations

International Nuclear Information System (INIS)

Reay, David; Harvey, Adam

2013-01-01

Heat pipes are heat transfer devices that rely, most commonly, on the evaporation and condensation of a working fluid contained within them, with passive pumping of the condensate back to the evaporator. They are sometimes referred to as ‘thermal superconductors’ because of their exceptionally high effective thermal conductivity (substantially higher than any metal). This, together with several other characteristics make them attractive to a range of intensified unit operations, particularly reactors. The majority of modern computers deploy heat pipes for cooling of the CPU. The application areas of heat pipes come within a number of broad groups, each of which describes a property of the heat pipe. The ones particularly relevant to chemical reactors are: i. Separation of heat source and sink. ii. Temperature flattening, or isothermalisation. iii. Temperature control. Chemical reactors, as a heat pipe application area, highlight the benefits of the heat pipe based on isothermalisation/temperature flattening device and on being a highly effective heat transfer unit. Temperature control, done passively, is also of relevance. Heat pipe technology offers a number of potential benefits to reactor performance and operation. The aim of increased yield of high purity, high added value chemicals means less waste and higher profitability. Other intensified unit operations, such as those employing sorption processes, can also profit from heat pipe technology. This paper describes several variants of heat pipe and the opportunities for their use in intensified plant, and will give some current examples. -- Highlights: ► Heat pipes – thermal superconductors – can lead to improved chemical reactor performance. ► Isothermalisation within a reactor vessel is an ideal application. ► The variable conductance heat pipe can control reaction temperatures within close limits. ► Heat pipes can be beneficial in intensified reactors

Remedial investigation/feasibility study work plan for the 100-KR-1 operable unit, Hanford Site, Richland, Washington

International Nuclear Information System (INIS)

1992-07-01

Four areas of the Hanford Site (the 100, 200, 300, and 1100 Areas) have been included on the US Environmental Protection Agency's (EPA's) National Priorities List (NPL) under the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA). Figure 1-1 shows the location of these areas. Under the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement, Ecology et al. 1990a), signed by the Washington State Department of Ecology (Ecology), EPA, and the US Department of Energy (DOE), more than 1,000 inactive waste disposal and unplanned release sites on the Hanford Site have been grouped into a number of source and groundwater operable units. These operable units contain contamination in the form of hazardous waste, radioactive/hazardous mixed waste, and other CERCLA hazardous substances. Also included in the Tri-Party Agreement are 55 Resource Conservation and Recovery Act (RCRA) treatment, storage, or disposal (TSD) facilities that will be closed or permitted to operate in accordance with RCRA regulations, under the authority of Chapter 173-303 Washington Administrative Code (WAC). Some of the TSD facilities are included in the operable units. This work plan and the attached supporting project plans establish the objectives, procedures, tasks, and schedule for conducting the CERCLA remedial investigation/feasibility study (RI/FS) for the 100-KR-1 operable unit. The 100-KR-1 source operable unit is one of three source operable units in the 100-K Area. Source operable units include facilities and unplanned release sites that are potential sources of hazardous substance contamination

PREMATH: a Precious-Material Holdup Estimator for unit operations and chemical processes

International Nuclear Information System (INIS)

Krichinsky, A.M.; Bruns, D.D.

1982-01-01

A computer program, PREMATH (Precious Material Holdup Estimator), has been developed to permit inventory estimation in vessels involved in unit operations and chemical processes. This program has been implemented in an operating nuclear fuel processing plant. PREMATH's purpose is to provide steady-state composition estimates for material residing in process vessels until representative samples can be obtained and chemical analyses can be performed. Since these compositions are used for inventory estimation, the results are determined for and cataloged in container-oriented files. The estimated compositions represent material collected in applicable vessels - including consideration for material previously acknowledged in these vessels. The program utilizes process measurements and simple material balance models to estimate material holdups and distribution within unit operations. During simulated run testing, PREMATH-estimated inventories typically produced material balances within 7% of the associated measured material balances for uranium and within 16% of the associated, measured material balances for thorium (a less valuable material than uranium) during steady-state process operation

NUMATH: a nuclear-material-holdup estimator for unit operations and chemical processes

International Nuclear Information System (INIS)

Krichinsky, A.M.

1981-01-01

A computer program, NUMATH (Nuclear Material Holdup Estimator), has been developed to permit inventory estimation in vessels involved in unit operations and chemical processes. This program has been implemented in an operating nuclear fuel processing plant. NUMATH's purpose is to provide steady-state composition estimates for material residing in process vessels until representative samples can be obtained and chemical analyses can be performed. Since these compositions are used for inventory estimation, the results are determined for and cataloged in container-oriented files. The estimated compositions represent material collected in applicable vessels-including consideration for material previously acknowledged in these vessels. The program utilizes process measurements and simple material balance models to estimate material holdups and distribution within unit operations. During simulated run testing, NUMATH-estimated inventories typically produced material balances within 7% of the associated measured material balances for uranium and within 16% of the associated, measured material balance for thorium during steady-state process operation

Treatability test plan for the 200-ZP-1 operable unit

International Nuclear Information System (INIS)

1994-07-01

This document presents the treatability test plan for pilot-scale pump and treat testing at the 200-ZP-1 Operable Unit. The approach discussed in this treatability test plan is to conduct a pilot-scale pump and treat test for the contaminant plume associated with the 200-ZP-1 Operable Unit. The primary contaminants of concern are carbon tetrachloride, chloroform, and trichloroethylene (TCE). The pilot-scale treatability testing has as its primary purpose to assess the performance of aboveground treatment systems with respect to the ability to remove the primary contaminants present in groundwater withdrawn from the contaminant plume. The overall scope of this test plan includes: description of the pump and treat system to be tested, as well as the test performance objectives and data quality objectives (DQOs) that will be used to evaluate the effectiveness of the pilot-scale treatment system; discussion of the treatment technology to be tested and supporting development activities, including process flow and conceptual design descriptions and equipment, fabrication, utility, and system startup needs; description of pilot-scale treatment system performance, operating procedures, and operational controls, as well as anticipated monitoring activities, analytes, parameters, analytical procedures, and quality assurance protocols; summaries of other related treatability testing elements, including personnel and environmental health and safety controls, process and secondary waste management and disposition, schedule, and program organization

Securing the Northern Maritime Border Through Maritime Domain Awareness

Science.gov (United States)

2010-09-01

and purpose of the agreement” (United States Department of State [USDOS], 2003). According to this pro memoria document, armament consists of M-60, .50...of Justice. United States Department of State. (2003). Pro Memoria of the United States Department of State. Washington, DC. Retrieved August 16

RCRA facility investigation/corrective measures study work plan for the 100-HR-3 operable unit, Hanford Site, Richland, Washington

International Nuclear Information System (INIS)

1992-09-01

Four areas of the Hanford Site (the 100, 200, 300, and 1100 Areas) have been included on the US Environmental Protection Agency's (EPA's) National Priorities List (NPL) under the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA). Under the Hanford Federal Facility Agreement and Consent Order, signed by the Washington State Department of Ecology (Ecology), EPA, and the US Department of Energy (DOE), more than 1000 inactive waste disposal and unplanned release sites on the Hanford Site have been grouped into a number of source and groundwater operable units. These operable units contain contamination in the form of hazardous waste, radioactive/hazardous mixed waste, and other CERCLA hazardous substances. Also included in the Tri-Party Agreement are 55 Resource Conservation and Recovery Act (RCRA) treatment, storage, or disposal (TSD) facilities that will be closed or permitted to operate in accordance with RCRA regulations, under the authority of Chapter 173-303 Washington Administrative Code (WAC). Some of the TSD facilities are included in the operable units. This work plan and the attached supporting project plans establish the operable unit setting and the objectives, procedures, tasks, and schedule for conducting the RCRA facility investigation/corrective measures study (RFI/CMS) for the 100-HR-3 operable unit. The 100-HR-3 operable unit underlies the D/DR and H Areas, the 600 Area between them, and the six source operable units these areas contain. The 100-HR-3 operable unit includes all contamination found in the aquifer soils and water within its boundary. Source operable units include facilities and unplanned release sites that are potential sources of contamination. Separate work plans have been initiated for the 100-DR-1 (DOE-RL 1992a) and 100-HR-1 (DOE-RL 1992b) source operable units

Point Beach Nuclear Plant, Units 1 and 2. Semiannual operating report No. 10, January--June 1975

International Nuclear Information System (INIS)

1975-01-01

Unit 1 operated at an average capacity factor of 65.2 percent with a net efficiency of 31.41 percent. Unit 2 operted at an average capacity factor of 88.6 lpercent with a net efficiency of 32.28 percent. Unit 1 was essentially base loaded while Unit 2 operated on load follow. Information is presented concerning power generation, shutdowns, corrective maintenance, chemistry and radiochemistry, occupational radiation exposure, release of radioactive materials, abnormal occurrences, and environmental monitoring. (FS)

Smart house-based optimal operation of thermal unit commitment for a smart grid considering transmission constraints

Science.gov (United States)

Howlader, Harun Or Rashid; Matayoshi, Hidehito; Noorzad, Ahmad Samim; Muarapaz, Cirio Celestino; Senjyu, Tomonobu

2018-05-01

This paper presents a smart house-based power system for thermal unit commitment programme. The proposed power system consists of smart houses, renewable energy plants and conventional thermal units. The transmission constraints are considered for the proposed system. The generated power of the large capacity renewable energy plant leads to the violated transmission constraints in the thermal unit commitment programme, therefore, the transmission constraint should be considered. This paper focuses on the optimal operation of the thermal units incorporated with controllable loads such as Electrical Vehicle and Heat Pump water heater of the smart houses. The proposed method is compared with the power flow in thermal units operation without controllable loads and the optimal operation without the transmission constraints. Simulation results show the validation of the proposed method.

Heat recovery unit operation of HVAC system in IMEF

International Nuclear Information System (INIS)

Paek, S. R.; Oh, Y. W.; Song, E. S.; Park, D. K.; Joo, Y. S.; Hong, K. P.

2003-01-01

HVAC system including a supply and exhaust air system in IMEF(Irradiated Materials Examination Facility) is an essential facility for preventing a leakage of radioactive materials and for a preservation of a working environment. It costs a lot to operate the HVAC system in IMEF because our ventilation type is once-through system, and an air flow is maintained from low level contamination area to high level and maintained high turns of ventilation air under certain conditions. As HRU(Heat Recovery Unit) at HVAC system based on PIEF(Post Irradiation Examination Facility) operation experiences is designed and adopted, it prevents from a heating coil freezing destruction in winter and makes much energy saving etc.. Heat pipe type HRU is adopted in IMEF, and a construction and operation result of HRU is examined

Denver Radium Site -- Operable Unit I closeout report for the US Environmental Protection Agency

International Nuclear Information System (INIS)

1992-08-01

The Denver Radium Site consists of properties in the Denver, Colorado, area having radioactive contamination left from radium processing in the early 1900s. The properties are divided into 11 gaps or operable units to facilitate remedial action of the Site. Operable Unit I is an 8-acre block bounded by Quivas Street to the east, Shoshone Street to the west, West 12th Avenue to the south, and West 13th Avenue to the north. The primary focus of interest concerning investigations of radiological contamination was a radium, vanadium, and uranium processing facility at 1201 Quivas Street owned by the Pittsburgh Radium Company (PRC) from 1925 until 1926. The Radium Ores Company, which was associated with PRC, operated the facility until 1927. A Remedial investigation (RI) of Operable Unit I was prepared by Jacobs Engineering Group and CH 2 M Hill on behalf of EPA in April 1986. The draft Feasibility Study (FS), prepared by Jacobs Engineering Group and CH 2 M Hill, was issued in July 1987 (the final FS is the Community Relations Responsiveness Summary with an errata to the draft, issued September 1987). The RI focused on radium uranium processing residues discarded in the early 1900s. These residues contained uranium, radium, and thorium. EPA s Community Relations Plan involved the community in the decision-making process relating to the remedy to be implemented at Operable Unit X, and promoted communications among interested parties throughout the course of the project. The remedial action alternative preferred by EPA for Operable Unit I was Off-Site Permanent Disposal. Because a permanent disposal facility was not available at the time the Record of Decision was issued in September 1987, EPA selected the On-Site Temporary Containment (capping) with the Off-Site Permanent Disposal alternative

40 CFR 60.2989 - Does this subpart directly affect incineration unit owners and operators in my State?

Science.gov (United States)

2010-07-01

... incineration unit owners and operators in my State? 60.2989 Section 60.2989 Protection of Environment... SOURCES Emission Guidelines and Compliance Times for Other Solid Waste Incineration Units That Commenced... incineration unit owners and operators in my State? (a) No, this subpart does not directly affect incineration...

78 FR 14361 - U.S. Steel Tubular Products, Inc., Mckeesport Tubular Operations Division, Subsidiary of United...

Science.gov (United States)

2013-03-05

... Products, Inc., Mckeesport Tubular Operations Division, Subsidiary of United States Steel Corporation, Mckeesport, PA; Notice of Initiation of Investigation To Terminate Certification of Eligibility Pursuant to... Tubular Products, McKeesport Tubular Operations Division, Subsidiary of United States Steel Corporation...

Operation experience of the advanced fuel assemblies at Unit 1 of Volgodonsk NPP within four fuel cycles

International Nuclear Information System (INIS)

Vasilchenko, I.; Kobelev, S.; Kushmanov, S.

2006-01-01

The first commissioning of Volgodonsk NPP Unit 1 with standard reactor WWER-1000 (project V-320) was in 2001. The reactor core, starting from the first fuel charge, was arranged completely with Advanced Fuel Assemblies (AFAs). In this way, it is possible to obtain the experience in startup and operation of the core, completely arranged with AFAs, and also to get a possibility of performing the comprehensive check for justification of newly commissioned units and justification of design solutions accepted in the design of reactor core for Taiwan NPP, Bushehr NPP and Kudankulam NPP. The first fuel charge of the Volgodonsk NPP Unit 1 is a reference and unified for Tiawan NPP (V-428), Bushehr NPP (V-446), Kudankulam NPP(V-412) with small differences caused by design features of RP V-320. The first core charge of Unit 1 of Volgodonsk NPP was arranged of 163 AFAs, comprising 61 CPS ARs and 42 BAR bundles. The subsequent fuel charges were arranged of AFAs with gadolinium oxide integrated into fuel instead of BAR. By 2005 the results of operation of the core at Unit 1 of Volgodonsk NPP during four fuel cycles showed that AFA is sufficiently reliable and serviceable. The activity of the primary coolant of the Volgodonsk NPP is at stable low level. During the whole time of the core operation of the Volgodonsk NPP Unit 1 no leaky AFAs were revealed. The modifications of the internals, made during pre-operational work, are reasonable and effective to provide for fuel mechanical stability in the course of operation. The modifications, made in AFA structure during operation of the Volgodonsk NPP Unit 1, are aimed at improving the service and operational reliability of its components. Correctness of the solutions taken is confirmed by AFAs operation experience both at the Volgodonsk NPP, and at other operating Russian NPPs

SCOPING SUMMARY FOR THE P-AREA OPERABLE UNIT

International Nuclear Information System (INIS)

Kupar, J; Sadika Baladi, S; Mark Amidon, M

2007-01-01

This scoping summary supports development of the combined Remedial Investigation (RI)/Baseline Risk Assessment (BRA)/Feasibility Study (FS) for the P-Area Operable Unit (PAOU), or Combined document, which will be submitted on or before 09/28/2007. The objective of this Feasibility Study scoping summary meeting is to agree on the likely response actions to be evaluated and developed as alternatives in the combined document and agree on the uncertainties identified and whether they have been adequately managed

SCOPING SUMMARY FOR THE P-AREA OPERABLE UNIT

Energy Technology Data Exchange (ETDEWEB)

Kupar, J; Sadika Baladi, S; Mark Amidon, M

2007-05-22

This scoping summary supports development of the combined Remedial Investigation (RI)/Baseline Risk Assessment (BRA)/Feasibility Study (FS) for the P-Area Operable Unit (PAOU), or Combined document, which will be submitted on or before 09/28/2007. The objective of this Feasibility Study scoping summary meeting is to agree on the likely response actions to be evaluated and developed as alternatives in the combined document and agree on the uncertainties identified and whether they have been adequately managed.

40 CFR 60.1200 - What are the operating practice requirements for my municipal waste combustion unit?

Science.gov (United States)

2010-07-01

... requirements for my municipal waste combustion unit? 60.1200 Section 60.1200 Protection of Environment... SOURCES Standards of Performance for Small Municipal Waste Combustion Units for Which Construction is... Good Combustion Practices: Operating Requirements § 60.1200 What are the operating practice...

Reservoir release patterns for hydropower operations at the Aspinall Unit on the Gunnison River, Colorado

International Nuclear Information System (INIS)

Yin, S.C.L.; Sedlacek, J.

1995-05-01

This report presents the development of reservoir release patterns for the Aspinall Unit, which includes Blue Mesa, Morrow Point, and Crystal Reservoirs on the Gunnison River in Colorado. Release patterns were assessed for two hydropower operational scenarios--seasonally adjusted steady flows and seasonally adjusted high fluctuating flows--and three representative hydrologic years--moderate (1987), dry (1989), and wet (1983). The release patterns for the operational scenarios were developed with the aid of monthly, daily, and hourly reservoir operational models, which simulate the linked operation of the three Aspinall Unit reservoirs. Also presented are reservoir fluctuations and downstream water surface elevations corresponding to the reservoir release patterns. Both of the hydropower operational scenarios evaluated are based on the ecological research flows proposed by the US Fish and Wildlife Service for the Aspinall Unit. The first operational scenario allows only seasonally adjusted steady flows (no hourly fluctuations at any dam within one day), whereas the second scenario permits high fluctuating flows from Blue Mesa and Morrow Point Reservoirs during certain times of the year. Crystal Reservoir would release a steady flow within each day under both operational scenarios

NRC plan for cleanup operations at Three Mile Island Unit 2

International Nuclear Information System (INIS)

Lo, R.; Snyder, B.J.

1980-07-01

The NRC plan defines the functional role of the NRC in cleanup operations at Three Mile Island Unit 2 to assure that agency regulatory responsibilities and objectives will be fulfilled. The plan outlines NRC functions in TMI-2 cleanup operations in the following areas: (1) the functional relationship of NRC to other government agencies, the public, and the licensee to coordinate activities, (2) the functional roles of these organizations in cleanup operations, (3) the NRC review and decision-making procedure for the licensee's proposed cleanup operation, (4) the NRC/licensee estimated schedule of major actions, and (5) NRC's functional role in overseeing implementation of approved licensee activities

Interim remedial measures proposed plan for the 200-ZP-1 Operable Unit, Hanford Site, Washington

International Nuclear Information System (INIS)

Parker, D.L.

1993-12-01

The purpose of this interim remedial measures (IRM) proposed plan is to present and solicit public comments on the IRM planned for the 200-ZP-1 Operable Unit at the Hanford Site in Washington state. The 200-ZP-1 is one of two operable units that envelop the groundwater beneath the 200 West Area of the Hanford Site

Development of Regulatory Audit Programs for Wolsong Unit 1 Continued Operation

Energy Technology Data Exchange (ETDEWEB)

Kim, Hong Key; Nho, Seung Hwan; Song, Myung Ho [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

2012-05-15

Wolsong Unit 1 (PHWR type) design life expires on November 20, 2010. In relation to it, KHNP submitted its application to get approval of the MEST on December 30, 2009 and KINS is under review to confirm the appropriateness of continued operation. For the comprehensive review of Wolsong Unit 1 continued operation, KINS has developed the review guidelines for PHWR type reactor including a total of 39 aging management program (AMP) items and 7 time limited aging analysis (TLAA) items. Evaluations or calculations to verify the integrity of nuclear components are required for plant specific AMP and TLAA items as well as the ones specified in the guidelines. In this paper, audit calculation programs developed for KINS staff use in reviewing applicant's submitted evaluation results are presented

Indian Point Station, Units 1, 2, and 3. Annual operating report for 1976

International Nuclear Information System (INIS)

1977-01-01

Unit 1 remained in a shutdown condition pending a decision by the Company on the installation of an ECCS as required by NRC. Net electrical power generated by Unit 2 was 2,267,654 MWH with the unit on line 3,056.45 hrs. Unit 3 generated 1,872,947 MWH and was on line 2,286.01 hrs. Information is presented concerning operations, reportable events, corrective maintenance, fuel performance, radioactivity releases, shutdowns, primary coolant chemistry, and occupational radiation exposures

Quad-Cities Station, Units 1 and 2. Semiannual operating report, January--June 1975

International Nuclear Information System (INIS)

1975-01-01

Unit 1 generated 2,024,125 net electrical MWH and the generator was on line 3162.6 hours. Unit 2 generated 746,184 net electrical MWH and was on line 1475.3 hrs. Data is included concerning operations, power generation, shutdowns, maintenance, changes, and tests. (FS)

Advanced Transport Operating System (ATOPS) control display unit software description

Science.gov (United States)

Slominski, Christopher J.; Parks, Mark A.; Debure, Kelly R.; Heaphy, William J.

1992-01-01

The software created for the Control Display Units (CDUs), used for the Advanced Transport Operating Systems (ATOPS) project, on the Transport Systems Research Vehicle (TSRV) is described. Module descriptions are presented in a standardized format which contains module purpose, calling sequence, a detailed description, and global references. The global reference section includes subroutines, functions, and common variables referenced by a particular module. The CDUs, one for the pilot and one for the copilot, are used for flight management purposes. Operations performed with the CDU affects the aircraft's guidance, navigation, and display software.

Proposed plan for remedial action at the quarry residuals operable unit of the Weldon Spring Site

International Nuclear Information System (INIS)

1998-03-01

This proposed plan addresses the management of contamination present in various components of the quarry residuals operable unit (QROU) of the Weldon Spring site, which is located in St. Charles County, Missouri. The QROU consists of (1) residual waste at the quarry proper; (2) the Femme Osage Slough, Little Femme Osage Creek, and Femme Osage Creek; and (3) quarry groundwater located primarily north of the slough. Potential impacts to the St. Charles County well field downgradient of the quarry area are also being addressed as part of the evaluations for this operable unit. Remedial activities for the QROU will be conducted by the US Department of Energy (DOE) in accordance with the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA), as amended. As part of the remedial investigation/feasibility study (RI/FS) process required for the QROU under CERCLA, three major evaluation documents have been prepared to support cleanup decisions for this operable unit. decisions for this operable unit

How Can the United States Army Improve Human Intelligence in Peace Operations?

National Research Council Canada - National Science Library

Wright, David

2003-01-01

.... These secondary collectors, such as the Military Police, Psychological Operations, Civil Affairs and Line Units conduct liaison with international and local police forces, host-government official...

Steam generator tube integrity requirements and operating experience in the United States

International Nuclear Information System (INIS)

Karwoski, K.J.

2009-01-01

Steam generator tube integrity is important to the safe operation of pressurized-water reactors. For ensuring tube integrity, the U.S. Nuclear Regulatory Commission uses a regulatory framework that is largely performance based. This performance-based framework is supplemented with some prescriptive requirements. The framework recognizes that there are three combinations of tube materials and heat treatments currently used in the United States and that the operating experience depends, in part, on the type of material used. This paper summarizes the regulatory framework for ensuring steam generator tube integrity, it highlights the current status of steam generators, and it highlights some of the steam generator issues and challenges that exist in the United States. (author)

An operating nuclear utility's experience with the ALARA design of a new nuclear unit

International Nuclear Information System (INIS)

Rodgers, R.C.

1985-01-01

This talk presents a review of how operating experience at Northeast Utilities has been factored into the design of a new nuclear unit and the development and management of the radiation protection program. Their operational experience has indicated that there are two facets to keeping radiation exposures ALARA. The first is the proper ALARA design of the unit. The other facet is the design of a comprehensive radiation protection program. The author discusses these facets in some detail

Operator support system for power unit control in abnormal modes of operation

International Nuclear Information System (INIS)

Kurka, J.

1993-01-01

I and C system technology, partly Soviet and partly Czechoslovakian, used on the NPP Dukovany units represents the control technology standard of late 70-ties and it becomes the weak part of the whole system. The modernization of the system, therefore, is necessary and it is already in preparation. The specification of both the scope and the depth of upgrading/replacement is being carried out within the framework of the PHARE program. The second phase of the program aimed at the final specifications of requirements on new I and C system is in progress. The output will serve as detailed specification for bid invitation for control system supplier. Parallely, the preparation of specification for WWER-440 full-scope plant simulator for operator training is in progress as well. In the case of two units with WWER-1000 MW reactors, the completion of construction of which was even threaten for a certain period of time, essential changes have taken place in the design of both the I and C systems and the reactor core. 7 figs

Application of total care time and payment per unit time model for physician reimbursement for common general surgery operations.

Science.gov (United States)

Chatterjee, Abhishek; Holubar, Stefan D; Figy, Sean; Chen, Lilian; Montagne, Shirley A; Rosen, Joseph M; Desimone, Joseph P

2012-06-01

The relative value unit system relies on subjective measures of physician input in the care of patients. A payment per unit time model incorporates surgeon reimbursement to the total care time spent in the operating room, postoperative in-house, and clinic time to define payment per unit time. We aimed to compare common general surgery operations by using the total care time and payment per unit time method in order to demonstrate a more objective measurement for physician reimbursement. Average total physician payment per case was obtained for 5 outpatient operations and 4 inpatient operations in general surgery. Total care time was defined as the sum of operative time, 30 minutes per hospital day, and 30 minutes per office visit for each operation. Payment per unit time was calculated by dividing the physician reimbursement per case by the total care time. Total care time, physician payment per case, and payment per unit time for each type of operation demonstrated that an average payment per time spent for inpatient operations was $455.73 and slightly more at $467.51 for outpatient operations. Partial colectomy with primary anastomosis had the longest total care time (8.98 hours) and the least payment per unit time ($188.52). Laparoscopic gastric bypass had the highest payment per time ($707.30). The total care time and payment per unit time method can be used as an adjunct to compare reimbursement among different operations on an institutional level as well as on a national level. Although many operations have similar payment trends based on time spent by the surgeon, payment differences using this methodology are seen and may be in need of further review. Copyright © 2012 American College of Surgeons. Published by Elsevier Inc. All rights reserved.

Explicit isospectral flows for the AKNS operator on the unit interval

International Nuclear Information System (INIS)

Amour, L

2009-01-01

We consider the AKNS operator on the unit interval. The boundary conditions are self-adjoint separated boundary conditions. For fixed boundary conditions, we make the formulae for flows induced by general tangent vector fields on isospectral sets explicit

Pilgrim Nuclear Power Station, Unit 1. Annual operating report for 1976

International Nuclear Information System (INIS)

Net electrical power generated was 2,415,511 MWH with the generator on line 5,333.6 hrs. Information is presented concerning operations, procedure changes, tests, experiments, maintenance, unit shutdowns and power reductions, and radiation doses to personnel

Salem Nuclear Generating Station, Unit 1. Annual operating report for 1976

International Nuclear Information System (INIS)

1977-01-01

Initial reactor criticality was achieved 12/11/76 and power generation began 12/25/76. Information is presented concerning operation, maintenance, procedure and specification changes, power generation, unit shutdowns and forced power reductions, testing, and personnel radiation exposures

Operational aerial snow surveying in the United States

Energy Technology Data Exchange (ETDEWEB)

Peck, E L; Carroll, T R; Vandemark, S C

1980-03-01

An airborne gamma radiation detector and data acquisition system has been designed for rapid measurement of the snow cover water equivalent over large open areas. Research and field tests conducted prior to the implementation of an operational snow measurement system in the United States are reviewed. Extensive research test flights were conducted over large river basins of the north-central plains and in the high mountain valleys of the inter-mountain West. Problems encountered during development include: (1) error in the gross gamma flux produced by atmospheric radon gas daughters; (2) spatial and temporal variability in soil moisture; and (3) errors in gamma radiation count rate introduced by aircraft and cosmic background radiation. Network design of operational flight line and ground observation data used in a river forecasting system are discussed. 22 references, 4 figures, 2 tables.

Operating experience gained during the copper oxide plugging incident in Koeberg unit 1 generator stator

International Nuclear Information System (INIS)

Mellor, S.P.; Matthee, F.W.

2002-01-01

In June 1999 Koeberg's unit 1 started to experience adverse operating conditions which were later ascribed to blockages in the hollow conductors of the generator stator. These blockages were attributed to copper oxide plugs which developed progressively during the following year and culminated in reduced power operation. Many attempts were made to address the plugging by implementing various off-line and on-line cleaning processes. Subsequent to a successful on-line cleaning operation, the unit was returned to full power and the chemistry regime for the stator cooling water system was changed to allow for operation at an elevated pH. This paper discusses Koeberg's experience with copper oxide blockages, describes the initial indications of the problem and the impact on the operating parameters. The remainder of the paper focuses on the actions taken to address the deteriorating situation and the different cleaning methods implemented to remove the copper oxide deposits. The paper concludes with the current status of the unit 1 generator stator and the lessons learned during the resolution of this problem. (authors)

Operating experience gained during the copper oxide plugging incident in Koeberg unit 1 generator stator

Energy Technology Data Exchange (ETDEWEB)

Mellor, S.P.; Matthee, F.W. [ESKOM, Koeberg Nuclear Power Station (South Africa)

2002-07-01

In June 1999 Koeberg's unit 1 started to experience adverse operating conditions which were later ascribed to blockages in the hollow conductors of the generator stator. These blockages were attributed to copper oxide plugs which developed progressively during the following year and culminated in reduced power operation. Many attempts were made to address the plugging by implementing various off-line and on-line cleaning processes. Subsequent to a successful on-line cleaning operation, the unit was returned to full power and the chemistry regime for the stator cooling water system was changed to allow for operation at an elevated pH. This paper discusses Koeberg's experience with copper oxide blockages, describes the initial indications of the problem and the impact on the operating parameters. The remainder of the paper focuses on the actions taken to address the deteriorating situation and the different cleaning methods implemented to remove the copper oxide deposits. The paper concludes with the current status of the unit 1 generator stator and the lessons learned during the resolution of this problem. (authors)

RCRA facility investigation report for the 200-PO-1 operable unit. Revision 1

International Nuclear Information System (INIS)

1997-05-01

This Resource Conservation and Recovery Act (RCRA) Facility Investigation (RFI) report is prepared in support of the RFI/corrective measures study process for the 200-PO-1 Groundwater Operable Unit in the 200 East Area of the Hanford Site. This report summarizes existing information on this operable unit presented in the 200 East and PUREX Aggregate Area Management Study Reports, contaminant specific studies, available modeling data, and groundwater monitoring data summary reports. Existing contaminant data are screened against current regulatory limits to determine contaminants of potential concern (COPC). Each identified COPC is evaluated using well-specific and plume trend analyses

United States Department of Energy projects related to reactor pressure vessel annealing optimization

International Nuclear Information System (INIS)

Rosinski, S.T.; Nakos, J.T.

1993-01-01

Light water reactor pressure vessel (RPV) material properties reduced by long-term exposure to neutron irradiation can be recovered through a thermal annealing treatment. This technique to extend RPV life, discussed in this report, provides a complementary approach to analytical methodologies to evaluate RPV integrity. RPV annealing has been successfully demonstrated in the former Soviet Union and on a limited basis by the US (military applications only). The process of demonstrating the technical feasibility of annealing commercial US RPVs is being pursued through a cooperative effort between the nuclear industry and the US Department of Energy (USDOE) Plant Lifetime Improvement (PLIM) Program. Presently, two projects are under way through the USDOE PLIM Program to demonstrate the technical feasibility of annealing commercial US RPVS, (1) annealing re-embrittlement data base development and (2) heat transfer boundary condition experiments

Commercial operation and outage experience of ABWR at Kashiwazaki-Kariwa units Nos. 6 and 7

International Nuclear Information System (INIS)

Anahara, N.; Yamada, M.; Kataoka, H.

2000-01-01

Kashiwazaki-Kariwa Nuclear Power Station Units Nos. 6 and 7, the world's first ABWRs (Advanced Boiling Water Reactor), started commercial operation on November 7, 1996 and July 2, 1997, respectively, and continued their commercial operation with a high capacity factor, low occupational radiation exposure and radioactive waste. Units 6 and 7 were in their 3rd cycle operation until 25th April 1999 and 1st November 1999, respectively. Thermal efficiency was 35.4-35.8% (design thermal efficiency: 34.5%) during these period, demonstrating better performance than that of BWR-5 (design thermal efficiency: 33.4%). Nos. 6 and 7 have experienced 2 annual outages. The first outage of unit No. 6 started on November 20, 1997 and was completed within 61 days (including 6 New Year holidays), and the second outage started on March 13, 1999 and was completed within 44 days. The first annual outage of unit No. 7 started on May 27, 1998, earlier than it would normally have been, to avoid an annual outage during the summer, and was completed within 55 days, and the second outage started on September 18th, 1999 and was completed within 45 days, All annual outages were carried out within a very short time period without any severe malfunctions, including newly designed ABWR systems and equipment. As the first outage in Japan, 55 days is a very short period, despite the fact that the Nos. 6 and 7 are the first ABWRs in the world and the largest capacity units in Japan. The total occupational radiation exposure of No. 6 was 300 man-mSv (1st outage) and 331 man-mSv (2nd outage). That of Unit 7 was 153 man-mSv (1st outage) Those of unit No. 6 were at the same level as those of unit No. 3, which is the latest design 1100MW(e) BWR-5. That of unit No. 7 was the lowest ever at Kashiwazaki-Kariwa nuclear power station. The drums of radioactive waste discharged during the annual outage numbered 54 (1st outage) for No. 6 and 62 (1st outage) for No. 7, which was less than the design target of 100

100-BC-1 Operable Unit focused feasibility study

International Nuclear Information System (INIS)

Day, R.E.

1994-01-01

The standard Comprehensive Environmental Response, Compensation, and Liability Act feasibility study includes development and screening of alternatives (Phases 1 and 2) and the detailed analysis of alternatives (Phase 3). This focused feasibility study constitutes the Phase 3 portion of the feasibility study process for the remedial alternatives initially developed and screened in the 100 Area Feasibility Study Phases 1 and 2 (DOE-RL 1993a). The focused feasibility study process is conducted in two stages, a Process Document (DOE-RL 1994a) and an operable unit-specific focused feasibility study document, such as this one. The focused feasibility study process is performed by implementing a ''plug-in'' style approach; as defined in greater detail in the Process Document, which is a companion to this document. The objective of this focused feasibility study is to provide decision makers with sufficient information to allow appropriate and timely selection of interim remedial measures for candidate waste sites associated with the 100-BC-1 Operable Unit which is located in the north-central part of the Hanford Site. The interim remedial measure candidate waste sites are determined in the Limited Field Investigation (DOE-RL 1993b). Site profiles are developed for each of these waste sites. The site profiles are used in the application of the plug-in approach. The waste site either plugs into the analysis of the alternatives for the group, or deviations from the developed group alternatives are described and documented

Report on the research through the U.S.DOE. 'The international search and consequence management workshop (ISCM-WS)'

International Nuclear Information System (INIS)

Kawakami, Takeshi; Tasaki, Takashi

2011-12-01

The International Search and Consequence Management Workshop (ISCM-WS) that was organized by the U.S. Department of Energy (DOE) took place from May 17th to May 20th, 2010. The aim of this Workshop was to build and enhance the global capacity to prevent and respond to nuclear and radiological emergencies, and it directly supports the aims of global initiative to combat nuclear terrorism. The U.S.DOE brought together 92 officials from 26 countries and 3 officials from IAEA in this workshop. DOE introduced two matters in the USA, first was response against nuclear and radiological terrorisms and second was technology, systems, activity for consequence management. This Review Report summarized the observation of the ISCM-WS including activity of DOE/NNSA's Search Response Team and activity of consequence management. Important knowledge from the ISCM-WS is as follows: Development and Equipment of remote radiation measurement system for searching Improvised Nuclear devises, Radiological Dispersal Device, etc. Using GPS data for mapping and checking of radiation measurement, Using GIS system for supporting planning and mapping of radiation measurement. Follow up system for checking first responder's radiation measurement data by radiological specialist in the radiological institute at distance place. Deployment system and logistics system for radiation monitoring team and radiation management team including national agency's team who are deployed on the spot. Aerial Measuring System and mobile laboratory for environmental samples analysis. Information sharing system for consequence management. (author)

RCRA facility investigation/corrective measures study work plan for the 200-UP-2 Operable Unit, Hanford Site, Richland, Washington

International Nuclear Information System (INIS)

1993-06-01

The 200-UP-2 Operable Unit is one of two source operable units at the U Plant Aggregate Area at the Hanford Site. Source operable units include waste management units and unplanned release sites that are potential sources of radioactive and/or hazardous substance contamination. This work plan, while maintaining the title RFI/CMS, presents the background and direction for conducting a limited field investigation in the 200-UP-2 Operable Unit, which is the first part of the process leading to final remedy selection. This report discusses the background, prior recommendations, goals, organization, and quality assurance for the 200-UP-2 Operable Unit Work Plan. The discussion begins with a summary of the regulatory framework and the role of the work plan. The specific recommendations leading into the work plan are then addressed. Next, the goals and organization of the report are discussed. Finally, the quality assurance and supporting documentation are presented

Remedial investigation for the 200-BP-1 operable unit, Hanford Site, Richland, Washington

International Nuclear Information System (INIS)

Buckmaster, M.A.

1991-01-01

The Hanford Site, Richland, Washington, contains over 1500 identified waste sites that will be characterized and remediated over the next 30 years. In support of the ''Hanford Federal Facility Agreement and Consent Order,'' the US Department of Energy has initiated a remedial investigation/feasibility study (RI/FS) at the 200-BP-1 operable unit. The 200-BP-1 RI is the first Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) investigation on the Hanford Site that involves drilling into highly radioactive and chemically contaminated soils. The initial phase of the site characterization is oriented toward determining the nature and extent of any contamination present in the vicinity of the 200-BP-1 operable unit. The major focus of the Phase I RI is the drilling and sampling of 10 inactive waste disposal units which received low level radioactive liquid waste

Risk-based decision analysis for groundwater operable units

International Nuclear Information System (INIS)

Chiaramonte, G.R.

1995-01-01

This document proposes a streamlined approach and methodology for performing risk assessment in support of interim remedial measure (IRM) decisions involving the remediation of contaminated groundwater on the Hanford Site. This methodology, referred to as ''risk-based decision analysis,'' also supports the specification of target cleanup volumes and provides a basis for design and operation of the groundwater remedies. The risk-based decision analysis can be completed within a short time frame and concisely documented. The risk-based decision analysis is more versatile than the qualitative risk assessment (QRA), because it not only supports the need for IRMs, but also provides criteria for defining the success of the IRMs and provides the risk-basis for decisions on final remedies. For these reasons, it is proposed that, for groundwater operable units, the risk-based decision analysis should replace the more elaborate, costly, and time-consuming QRA

Operation time extension for power units of the first generation NPP and the liability for potential damage

International Nuclear Information System (INIS)

Kovalevich, O.M.

2000-01-01

The problem on the operation time extension for the six operating NPP first generation power units is discussed. However it is not advisable to improve the safety of these power units up to the acceptable level, therefore there arises the contradiction between the operation time extension of these power units and potential damage for the population. The possibility of having the increased civilian-legal responsibility for potential harm and losses in case of an accident is proposed to be considered as a compensating measure. The measures for realization of this civilian-legal responsibility are described [ru

Browns Ferry Nuclear Power Station, Units 1, 2, and 3. Annual operating report: January--December 1976

International Nuclear Information System (INIS)

1977-01-01

Units 1 and 2 were down for the first half of the year caused by the fire of March 1975. Net electrical power generated by Unit 1 this year was 1,301,183 MWH with the generator on line 2,175.25 hrs. Unit 2 generated 1,567,170 MWH with the generator on line 2,548.73 hrs. Unit 3 began full power operation on November 20th and generated 1,416,891 MWH with the generator on line 2,058.20 hrs. Information is presented concerning operations, fuel performance, surveillance testing, containment leak testing, changes, power generation, shutdown and forced reductions, coolant chemistry, occupational radiation exposures, and maintenance

Operating of mobile machine units system using the model of multicomponent complex movement

OpenAIRE

A. Lebedev; R. Kaidalov; N. Artiomov; M. Shulyak; M. Podrigalo; D. Abramov; D. Klets

2015-01-01

To solve the problems of mobile machine units system operating it is proposed using complex multi-component (composite) movement physical models. Implementation of the proposed method is possible by creating of automatic operating systems of fuel supply to the engines using linear accelerometers. Some examples to illustrate the proposed method are offered.

Operable Unit 3-13, Group 3, Other Surface Soils (Phase II) Field Sampling Plan

Energy Technology Data Exchange (ETDEWEB)

G. L. Schwendiman

2006-07-27

This Field Sampling Plan describes the Operable Unit 3-13, Group 3, Other Surface Soils, Phase II remediation field sampling activities to be performed at the Idaho Nuclear Technology and Engineering Center located within the Idaho National Laboratory Site. Sampling activities described in this plan support characterization sampling of new sites, real-time soil spectroscopy during excavation, and confirmation sampling that verifies that the remedial action objectives and remediation goals presented in the Final Record of Decision for Idaho Nuclear Technology and Engineering Center, Operable Unit 3-13 have been met.

Estimation of the optimal operating conditions for a radiation chemical neutralization unit

International Nuclear Information System (INIS)

Putilov, A.V.; Kamenetskaya, S.A.; Pshezhetskii, S.Ya.; Kazakov, M.S.; Kudryavtsev, S.L.; Petrukhin, N.V.; Misharin, B.A.; Koneev, V.Z.

1985-01-01

An estimate is made of the effect of the hydrodynamic conditions on the efficiency of foam units for the radiation chemical neutralization of impurities, taking into account the penetrating power of accelerated electrons having various energies. Expressions are obtained for calculating the efficiency of such units with sectionized operation of the chamber and taking account of the effect of incomplete mixing of the products of radiolysis through the height of the foam layer

Groundwater Monitoring Plan for the Reactor Technology Complex Operable Unit 2-13

International Nuclear Information System (INIS)

Richard P. Wells

2007-01-01

This Groundwater Monitoring Plan describes the objectives, activities, and assessments that will be performed to support the on-going groundwater monitoring requirements at the Reactor Technology Complex, formerly the Test Reactor Area (TRA). The requirements for groundwater monitoring were stipulated in the Final Record of Decision for Test Reactor Area, Operable Unit 2-13, signed in December 1997. The monitoring requirements were modified by the First Five-Year Review Report for the Test Reactor Area, Operable Unit 2-13, at the Idaho National Engineering and Environmental Laboratory to focus on those contaminants of concern that warrant continued surveillance, including chromium, tritium, strontium-90, and cobalt-60. Based upon recommendations provided in the Annual Groundwater Monitoring Status Report for 2006, the groundwater monitoring frequency was reduced to annually from twice a year

OPERATING OF MOBILE MACHINE UNITS SYSTEM USING THE MODEL OF MULTICOMPONENT COMPLEX MOVEMENT

Directory of Open Access Journals (Sweden)

A. Lebedev

2015-07-01

Full Text Available To solve the problems of mobile machine units system operating it is proposed using complex multi-component (composite movement physical models. Implementation of the proposed method is possible by creating of automatic operating systems of fuel supply to the engines using linear accelerometers. Some examples to illustrate the proposed method are offered.

RCRA facility investigation/corrective measures study work plan for the 100-DR-1 operable unit, Hanford Site, Richland, Washington

International Nuclear Information System (INIS)

1992-09-01

Four areas of the Hanford Site (the 100, 200, 300, and 1100 Areas) have been included on the US Environmental Protection Agency's (EPA's) National Priorities List (NPL) under the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA). Under the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement, Ecology et. al. 1990a), signed by the Washington State Department of Ecology (Ecology), EPA, and the US Department of Energy (DOE), more than 1,000 inactive waste disposal and unplanned release sites on the Hanford Site have been grouped into a number of source and groundwater operable units. These operable units contain contamination in the form of hazardous waste, radioactive/hazardous mixed waste, and other CERCLA hazardous substances. Also included in the Tri-Party Agreement are 55 Resource Conservation and Recovery Act (RCRA) treatment, storage, or disposal (TSD) facilities that will be closed or permitted to operate in accordance with RCRA regulations. Some of the TSD facilities are included in the operable units. This work plan and the attached supporting project plans establish the operable unit setting and the objectives, procedures, tasks, and schedule for conducting the RCRA facility investigation/corrective measures study (RFI/CMS) for the 100-DR-1 source operable unit Source operable units include facilities and unplanned release sites that are potential sources of contamination

Feasibility Study for Operable Unit 7-13/14

International Nuclear Information System (INIS)

K. Jean Holdren Thomas E. Bechtold Brian D. Preussner

2007-01-01

The Subsurface Disposal Area is a radioactive waste landfill located within the Radioactive Waste Management Complex at the Idaho National Laboratory Site in southeastern Idaho. This Feasibility Study for Operable Unit 7-13/14 analyzes options for mitigating risks to human health and the environment associated with the landfill. Analysis is conducted in accordance with the Comprehensive Environmental Response, Compensation, and Liability Act, using nine evaluation criteria to develop detailed and comparative analysis of five assembled alternatives. Assembled alternatives are composed of discrete modules. Ultimately, decision-makers will select, recombine, and sum various modules into an optimized preferred alternative and final remedial decision

Feasibility Study for Operable Unit 7-13/14

Energy Technology Data Exchange (ETDEWEB)

K. Jean Holdren

2007-05-29

The Subsurface Disposal Area is a radioactive waste landfill located within the Radioactive Waste Management Complex at the Idaho National Laboratory Site in southeastern Idaho. This Feasibility Study for Operable Unit 7-13/14 analyzes options for mitigating risks to human health and the environment associated with the landfill. Analysis is conducted in accordance with the Comprehensive Environmental Response, Compensation, and Liability Act, using nine evaluation criteria to develop detailed and comparative analysis of five assembled alternatives. Assembled alternatives are composed of discrete modules. Ultimately, decision-makers will select, recombine, and sum various modules into an optimized preferred alternative and final remedial decision.

Aquatic studies at the 100-HR-3 and 100-NR-1 operable units

International Nuclear Information System (INIS)

Cushing, C.E.

1993-04-01

Pacific Northwest Laboratory initiated a program to characterize selected aquatic biological populations to determine (1) existing levels of inorganic chemical and radionuclide contamination, and (2) the populations' suitability as indicators of chemical releases during cleanup activities at the US Department of Energy's Hanford Site. Following work plans for the ground-water operable units, lower trophic levels in the aquatic habitat (periphyton and caddisfly larvae) were evaluated for contaminants at the 100-HR-3 Operable Unit and 100-NR-1 Operable Unit. The results were evaluated to determine the need for further sampling. If the results showed no significant contamination compared to upriver levels, sampling would be discontinued. The periphyton community appears to be suitable for determining contamination levels. Baseline concentrations for stable chromium were established and will be useful for comparing samples collected when contaminant release is expected. Concentrations of 60 Co, 90 Sr, and 137 Cs in periphyton were essentially below detectable limits, which will also make this community useful in detecting potential releases of radionuclides during cleanup activities. Levels for both stable chromium and radionuclides were essentially below detection limits for caddisfly larvae. Thus, these organisms may be used to monitor suspected contaminant releases from cleanup activities; if concentrations exceed detection limits, they may be related to these activities. Two candidate threatened and endangered species of molluscs occur in the Hanford Reach of the Columbia River. These are the shortface lanx (Fisherola nuttalli), which is a Washington State candidate species, and the Columbia pebblesnail (Fluminicola columbiana), which is both a state and federal candidate species. Specimens of the shortface lanx were observed in the vicinity of N Springs (100-NR-1 Operable Unit); they likely occur throughout this area

Unit operation in food manufacturing and processing. Shokuhin seizo/kako ni okeru tan'i sosa

Energy Technology Data Exchange (ETDEWEB)

Matsuno, R. (Kyoto Univ., Kyoto (Japan). Faculty of Aguriculture)

1993-09-05

Processed foods must be produced in mass, cheap and safe and should be suitable for the delicate taste of human being. Food tastes are effected by an outlook on human attitude, and the surrounding environment. And these factors are reflected to unit operation in food manufacturing and processing and it is clarified that there are many technical difficulties. The characteristics of unit operation for food manufacturing and processing are that the food materials are a multicomponent system, moreover, a very small amount of aroma components, taste components, vitamin, physiologically activation materials and so on are more important than the main components, and also inapplicable of the model centering to the most quantitative component. The purpose of unit operation in food manufacturing and processing is to produce the properties of matter matching to human sense, and therefore there are many problems left unsolved. The development of analytical technology also has an influence on manufacturing and processing technology. Consequently, food manufacturing and processing technology must be based on general science. It is necessary to develop unit operation with an understanding of mutual effect between food and human body.

Day-Ahead Coordination of Vehicle-to-Grid Operation and Wind Power in Security Constraints Unit Commitment (SCUC)

OpenAIRE

Mohammad Javad Abdollahi; Majid Moazzami

2015-01-01

In this paper security constraints unit commitment (SCUC) in the presence of wind power resources and electrical vehicles to grid is presented. SCUC operation prepare an optimal time table for generation unit commitment in order to maximize security, minimize operation cost and satisfy the constraints of networks and units in a period of time, as one of the most important research interest in power systems. Today, the relationship between power network and energy storage systems is interested...

Calvert Cliffs Nuclear Power Plant, Units 1 and 2. Annual operating report: January--December 1976

International Nuclear Information System (INIS)

1977-01-01

Unit 1 successfully completed its first core cycle with unit availability of 95.2 percent. Saltwater leakage into the condenser continues to be a problem. Unit 2 achieved initial criticality November 30 and was initially paralleled to the Baltimore system on December 7. Information is presented concerning operations, specifications, maintenance, shutdowns and power reduction, and personnel exposures

Survey Method for Radiological Surveys of 300-FF-1 Operable Unit Soils and Material

International Nuclear Information System (INIS)

Brehm, D.M.

1998-06-01

This technical basis is to be used to survey soils at the 300-FF-1 Operable Unit during remediation of the site. Its purpose is to provide a basis for the survey methods to be employed by radiological control technician (RCTs) to guide the excavation effort in accordance with the 300-FF-1 waste site Record of Decision (ROD). The ROD for the 300-FF-1 Operable Unit requires selective excavation, removal, and disposal of contaminated soil above 350 pCi/g total uranium activity. Soil above this level will be disposed of as radioactive waste. The remaining soil will remain onsite

INEL Operable Unit 7-13 containment and stabilization configuration option

International Nuclear Information System (INIS)

Raivo, B.D.; Richardson, J.G.; Nickelson, D.F.

1993-05-01

A containment and stabilization configuration option has been developed for the Idaho National Engineering Laboratory's Subsurface Disposal Area Operable Unit 7-13, the transuranic (TRU)-contaminated waste pits and trenches. The configuration option is presented as an end-to-end system block diagram. Functional subelements are separately discussed, and technical background information, assumptions, input, high-level subelement requirements, and output are presented for each option

Oconee Nuclear Station, Units 1, 2, and 3. Semiannual operating report, January--June 1975

International Nuclear Information System (INIS)

1975-01-01

Information is presented concerning operations, performance characteristics, changes, tests, inspections, containment leak tests, maintenance, primary coolant chemistry, station staff changes, reservoir investigations, plume mapping, and operational environmental radioactivity monitoring data for oconee Units 1, 2, and 3. The non-radiological environmental surveillance program is also described. (FS)

Design and operational parameters of transportable supercritical water oxidation waste destruction unit

International Nuclear Information System (INIS)

McFarland, R.D.; Brewer, G.R.; Rofer, C.K.

1991-12-01

Supercritical water oxidation (SCWO) is the destruction of hazardous waste by oxidation in the presence of water at temperatures and pressures above its critical point. A 1 gal/h SCWO waste destruction unit (WDU) has been designed, built, and operated at Los Alamos National Laboratory. This unit is transportable and is intended to demonstrate the SCWO technology on wastes at Department of Energy sites. This report describes the design of the WDU and the preliminary testing phase leading to demonstration

The quality of operative notes at a general surgery unit.

Science.gov (United States)

Rogers, A; Bunting, M; Atherstone, A

2008-09-01

With the increasingly litigious nature of medical practice, accurate documentation is critical. This is particularly true for operative procedures, and medical councils have identified this and published guidelines to aid surgeons. However, these remain a frequently cited weakness in their defence in medico-legal cases. This study assessed the accuracy of operative notes in a general surgery unit in order to improve our practice. An audit of 100 consecutive operative notes was performed, and notes were assessed using the Royal College of Surgeons guidelines. The quality of note-taking of trainees was compared with that of consultant surgeons. A series of operation note pro formas was designed in response to the findings. Of the notes, 66% were completed by trainees. The vast majority of notes had no diagram to demonstrate the surgical findings or illustrate the actions. Specialist surgeons were more likely to describe the actions accurately, but less likely to describe wound closure methods or dressings used. They were also less likely to complete adequate postoperative orders. This study identifies key areas of weakness in our operative note-keeping. Pro formas should be introduced and made available for commonly performed procedures, and diagrams should be used wherever possible.

Enhanced teaching and student learning through a simulator-based course in chemical unit operations design

Science.gov (United States)

Ghasem, Nayef

2016-07-01

This paper illustrates a teaching technique used in computer applications in chemical engineering employed for designing various unit operation processes, where the students learn about unit operations by designing them. The aim of the course is not to teach design, but rather to teach the fundamentals and the function of unit operation processes through simulators. A case study presenting the teaching method was evaluated using student surveys and faculty assessments, which were designed to measure the quality and effectiveness of the teaching method. The results of the questionnaire conclusively demonstrate that this method is an extremely efficient way of teaching a simulator-based course. In addition to that, this teaching method can easily be generalised and used in other courses. A student's final mark is determined by a combination of in-class assessments conducted based on cooperative and peer learning, progress tests and a final exam. Results revealed that peer learning can improve the overall quality of student learning and enhance student understanding.

Emergency operating instruction improvements at San Onofre Nuclear Generating Station Units 2 and 3

International Nuclear Information System (INIS)

Trillo, M.W.; Smith, B.H.

1989-01-01

In late 1987, San Onofre nuclear generating station (SONGS) began an extensive upgrade of the units 2 and 3 emergency operating instructions (EOIs). The original intent of this program was to incorporate revised generic guidance and to correct problems that were identified by operators. While this program was in progress, the US Nuclear Regulatory Commission (NRC) conducted a series of audits of emergency operating procedure (EOP) development and maintenance programs as 16 commercial nuclear facilities in the United States. These audits included four stations with Combustion Engineering-designed nuclear steam supply systems. (One of these audits included a review of preupgrade SONGS units 2 and 3 EOIs.) Significant industrywide comments resulted from these audits. The NRC has stated its intent to continue the review and audit of EOIs and the associated maintenance programs at all US commercial nuclear facilities. The units 2 and 3 EOI upgrade program developed procedural improvements and procedural program maintenance improvements that address many of the existing audit comments that have been received by the industry. Other resulting improvements may be useful in minimizing NRC comments in future such audits. Specific improvements are discussed. The upgrade program resulted in benefits that were not originally anticipated. The results of this program can be of significant use by other utilities in addressing the industrywide concerns that have been raised in recent NRC audits of EOP development and maintenance programs

NRC plan for cleanup operations at Three Mile Island Unit 2

International Nuclear Information System (INIS)

Lo, R.; Snyder, B.

1982-02-01

This NRC Plan, which defines NRC's functional role in cleanup operations at Three Mile Island Unit 2 and outlines NRC's regulatory responsibilities in fulfilling this role, is the first revision to the initial plan issued in July 1980 (NUREG-0698). Since 1980, a number of policy developments have occurred which will have an impact on the course of cleanup operations. This revision reflects these developments in the area of NRC's review and approval process with regard to cleanup operations as well as NRC's interface with the Department of Energy's involvement in the cleanup and waste disposal. This revision is also intended to update the cleanup schedule by presenting the cleanup progress that has taken place and NRC's role in ongoing and future cleanup activities

Article separation apparatus and method for unit operations

Science.gov (United States)

Pardini, Allan F.; Gervais, Kevin L.; Mathews, Royce A.; Hockey, Ronald L.

2010-06-22

An apparatus and method are disclosed for separating articles from a group of articles. The apparatus includes a container for containing one or more articles coupled to a suitable fluidizer for suspending articles within the container and transporting articles to an induction tube. A portal in the induction tube introduces articles singly into the induction tube. A vacuum pulls articles through the induction tube separating the articles from the group of articles in the container. The apparatus and method can be combined with one or more unit operations or modules, e.g., for inspecting articles, assessing quality of articles, or ascertaining material properties and/or parameters of articles, including layers thereof.

Interim action record of decision remedial alternative selection: TNX area groundwater operable unit

International Nuclear Information System (INIS)

Palmer, E.R.

1994-10-01

This document presents the selected interim remedial action for the TNX Area Groundwater Operable Unit at the Savannah River Site (SRS), which was developed in accordance with CERCLA of 1980, as amended by the Superfund Amendments and Reauthorization Act (SARA) of 1986, and to the extent practicable, the National Oil and Hazardous Substances Pollution contingency Plan (NCP). This decision is based on the Administrative Record File for this specific CERCLA unit

The Applied Meteorology Unit: Nineteen Years Successfully Transitioning Research Into Operations for America's Space Program

Science.gov (United States)

Madura, John T.; Bauman, William H., III; Merceret, Francis J.; Roeder, William P.; Brody, Frank C.; Hagemeyer, Bartlett C.

2011-01-01

The Applied Meteorology Unit (AMU) provides technology development and transition services to improve operational weather support to America's space program . The AMU was founded in 1991 and operates under a triagency Memorandum of Understanding (MOU) between the National Aeronautics and Space Administration (NASA), the United States Air Force (USAF) and the National Weather Service (NWS) (Ernst and Merceret, 1995). It is colocated with the 45th Weather Squadron (45WS) at Cape Canaveral Air Force Station (CCAFS) and funded by the Space Shuttle Program . Its primary customers are the 45WS, the Spaceflight Meteorology Group (SMG) operated for NASA by the NWS at the Johnson Space Center (JSC) in Houston, TX, and the NWS forecast office in Melbourne, FL (MLB). The gap between research and operations is well known. All too frequently, the process of transitioning research to operations fails for various reasons. The mission of the AMU is in essence to bridge this gap for America's space program.

Day-Ahead Coordination of Vehicle-to-Grid Operation and Wind Power in Security Constraints Unit Commitment (SCUC

Directory of Open Access Journals (Sweden)

Mohammad Javad Abdollahi

2015-08-01

Full Text Available In this paper security constraints unit commitment (SCUC in the presence of wind power resources and electrical vehicles to grid is presented. SCUC operation prepare an optimal time table for generation unit commitment in order to maximize security, minimize operation cost and satisfy the constraints of networks and units in a period of time, as one of the most important research interest in power systems. Today, the relationship between power network and energy storage systems is interested for many researchers and network operators. Using Electrical Vehicles (PEVs and wind power for energy production is one of the newest proposed methods for replacing fossil fuels.One of the effective strategies for analyzing of the effects of Vehicle 2 Grid (V2G and wind power in optimal operation of generation is running of SCUC for power systems that are equipped with V2G and wind power resources. In this paper, game theory method is employed for deterministic solution of day-ahead unit commitment with considering security constraints in the simultaneous presence of V2G and wind power units. This problem for two scenarios of grid-controlled mode and consumer-controlled mode in three different days with light, medium and heavy load profiles is analyzed. Simulation results show the effectiveness of the presence of V2G and wind power for decreasing of generation cost and improving operation indices of power systems.

Limited field investigation report for the 100-NR-1 Operable Unit

International Nuclear Information System (INIS)

1995-03-01

This limited field investigation (LFI) report summarizes the data collection and analysis activities conducted during the 100-NR-1 Source Operable Unit LFI and the associated qualitative risk assessment (QRA), and makes recommendations on the continued candidacy of high-priority sites for interim remedial measures (IRM). The results and recommendations presented in this report are generally independent of future land-use scenarios. This report is unique in that it is based on Hanford-specific agreements discussed in the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) (Ecology et al. 1992), the Hanford Site Risk Assessment Methodology (DOE-RL 1994a), the Remedial Investigation Feasibility Study Work Plan for the 100-NR-1 Operable Unit (DOE-RL 1992a), and the Hanford Past-Practice Strategy (HPPS) (DOE-RL 1991), and must be viewed in this context. The HPPS emphasizes initiating and completing waste site cleanup through interim actions. The strategy includes paths for interim decision-making and a final remedy-selection process for the operable unit. A LFI report is required, in accordance with the HPPS, when waste sites are to be considered for IRM and existing data are insufficient to formulate a conceptual model or perform a QRA. The purpose of the report is to identify those sites that are recommended to remain as candidates for IRM, provide a preliminary summary of site characterization studies, refine the conceptual model as needed, identify potential contaminant- and location-specific applicable or relevant and appropriate requirements (ARAR), and provide a qualitative assessment of the risks associated with the sites. This assessment includes consideration of whether contaminant concentrations pose a risk to human health or the environment that warrants action through IRM

A Moveable Feast--A Progressive Approach to the Unit Operations Laboratory

Science.gov (United States)

Conner, Wm. Curtis, Jr.; Hammond, Karl D.; Laurence, Robert L.

2011-01-01

The authors describe an alternative format for the senior laboratory in which students are allowed--indeed, expected--to communicate with previous groups and build on their results. The effect is a unit operations laboratory in which students are empowered to propose the experiments they wish to do and in which the cumulative experience of the…

Use of Special Operations Forces in United Nations Missions: a Method to Resolve Complexity

Science.gov (United States)

2015-05-21

physical stamina and psychological stability, followed by a rigorous training program are the imperatives to create SOF soldiers.42 Mark Bowden in...recommendation is that the United Nations should establish a Special Operations planning cell within the UN Department of Peacekeeping Operations. As of...now, the cell is nonexistent. This cell should be able to facilitate the integration of SOF into the overall peace operations concept. Finally, the

Qualitative risk assessment for the 100-FR-1 source operable unit

International Nuclear Information System (INIS)

Corporation, I.T.

1994-08-01

This report provides the Qualitative risk assessment (QRA) for the waste sites associated with the 100-FR-1 Operable Unit. The QRA is an evaluation of risk for a predefined set of human and ecological exposure scenarios. It is not intended to replace or be a substitute for a baseline risk assessment. The QRA is streamlined to consider only two human health scenarios (frequent-and occasional-use) with four exposure pathways (soil ingestion, fugitive dust inhalation, inhalation of volatile organics, and external radiation exposure) and a limited ecological evaluation. The use of these scenarios and pathways was agreed to by the 100 Area Tri-Party unit managers

Engineering evaluation/conceptual plan for the 200-UP-1 groundwater operable unit interim remedial measure

International Nuclear Information System (INIS)

Myers, D.A.; Swanson, L.C.; Weeks, R.S.; Giacinto, J.; Gustafson, F.W.; Ford, B.H.; Wittreich, C.; Parnell, S.; Green, J.

1995-04-01

This report presents an engineering evaluation and conceptual plan for an interim remedial measure (ERM) to address a uranium and technetium-99 groundwater plume and an associated nitrate contamination plume in the 200-UP-1 Groundwater Operable Unit located in the 200 West Area of the Hanford Site. This report provides information regarding the need and potentially achievable objectives and goals for an IRM and evaluates alternatives to contain elevated concentrations of uranium, technetium-99, nitrate, and carbon tetrachloride and to obtain information necessary to develop final remedial actions for the operable unit

Cost and Operational Effectiveness Analysis of Aiternative Force Structures for Fulfillment of the United States Marine Corps Operational Support Airlift and Search and Rescue Missions

National Research Council Canada - National Science Library

Chase, Eric

2000-01-01

This thesis provides a preliminary cost and operational effectiveness analysis of alternative force structures for the United States Marine Corps operational support airlift and search and rescue missions...

Waste Area Group 10, Operable Unit 10-08, Remedial Investigation/Feasibility Study Annual Status Report for Fiscal Year 2006

Energy Technology Data Exchange (ETDEWEB)

R. P. Wells

2007-05-09

This report provides a status of the progress made in Fiscal Year 2006 on tasks identified in the Waste Area Group 10, Operable Unit 10-08, Remedial Investigation/Feasibility Study Work Plan. Major accomplishments include: (1) groundwater sampling and review of the groundwater monitoring data, (2) installation of a Sitewide groundwater-level monitoring network, (3) update of the Groundwater Monitoring and Field Sampling Plan of Operable Unit 10-08, (4) re-evaluation of the risk at Site TSF-08, (5) progress on the Operable Unit 10-08 Sitewide Groundwater Model.

Geophysical Investigation of the 618-10 and 618-11 Burial Grounds, 300-FF-2 Operable Unit

International Nuclear Information System (INIS)

Bergstrom, K.A.; Bolin, D.J.; Mitchell, T.H.

1997-09-01

This document summarizes the results of geophysical investigations conducted at two radioactive solid waste burial grounds, 618-10 and 618-11. The burial grounds are located approximately 4.5 miles and 7 miles north of the 300 Area, respectively. These sites are within the 300-FF-2 Operable Unit, where geophysical techniques are being used to characterize the distribution of solid waste in the subsurface as part of the Limited Field Investigations for this operable unit

Compex system for teaching and training operators for TPP and NPP power units

International Nuclear Information System (INIS)

Tsiptsyura, R.D.

1985-01-01

Requirements, taken as a principle for constructing the system for operator teaching and training (OTT), have been formulated on the basis of investigation of operators' work at TPP and NPP power units. Functional structure and a structural block-diagram for OTT are built. As a criterion, which determines the structure of any trainers, being a part of OTT a requirement has been chosen satisfying the correspondence beetween habits developed with the help of trainers and habits of real operators' work. Results of analysis permit to confirm that refusal or under statement of the role of any stage of operator training leads to reduction of quality of his training

5-year operation experience with the 1.8 K refrigeration units of the LHC cryogenic system

CERN Document Server

Ferlin, G; Claudet, S; Pezzetti, M

2015-01-01

Since 2009, the Large Hadron Collider (LHC) is in operation at CERN. The LHC superconducting magnets distributed over eight sectors of 3.3-km long are cooled at 1.9 K in pressurized superfluid helium. The nominal operating temperature of 1.9 K is produced by eight 1.8-K refrigeration units based on centrifugal cold compressors (3 or 4 stages depending to the vendor) combined with warm volumetric screw compressors with sub-atmospheric suction. After about 5 years of continuous operation, we will present the results concerning the availability for the final user of these refrigeration units and the impact of the design choice on the recovery time after a system trip. We will also present the individual results for each rotating machinery in terms of failure origin and of Mean Time between Failure (MTBF), as well as the consolidations and upgrades applied to these refrigeration units.

5-year operation experience with the 1.8 K refrigeration units of the LHC cryogenic system

Science.gov (United States)

Ferlin, G.; Tavian, L.; Claudet, S.; Pezzetti, M.

2015-12-01

Since 2009, the Large Hadron Collider (LHC) is in operation at CERN. The LHC superconducting magnets distributed over eight sectors of 3.3-km long are cooled at 1.9 K in pressurized superfluid helium. The nominal operating temperature of 1.9 K is produced by eight 1.8-K refrigeration units based on centrifugal cold compressors (3 or 4 stages depending to the vendor) combined with warm volumetric screw compressors with sub-atmospheric suction. After about 5 years of continuous operation, we will present the results concerning the availability for the final user of these refrigeration units and the impact of the design choice on the recovery time after a system trip. We will also present the individual results for each rotating machinery in terms of failure origin and of Mean Time between Failure (MTBF), as well as the consolidations and upgrades applied to these refrigeration units.

Wood Storks of the Birdsville Colony and swamps of the Savannah River Site: General overview of research findings, 1983--1990

International Nuclear Information System (INIS)

Coulter, M.C.

1993-02-01

The population of Wood Storks (Mycteria americana) that breeds in the United States has decreased from an estimated 20,000 breeding pairs in 1930 to just under 5,000 pairs in 1980. Since 1980, the number has remained relatively stable, fluctuating between 3,500 and 5,500 breeding pairs. The decline prompted the US Fish and Wildlife Service (USFWS) to list the United States population of Wood Storks as endangered in 1984. When the US Department of Energy (USDOE) decided to restart L-Reactor on the Savannah River Site (SRS), there was concern that when the reactor was restarted, cooling water flowing into the Steel Creek Delta would raise the water level and the area would become too deep for foraging storks. The potential loss of this area to storks was important because storks had been observed foraging in the Steel Creek Delta. The USDOE began consultation with the USFWS in April, 1984, and the USDOE subsequently agreed to develop and maintain alternative foraging habitat to replace the potential loss. In order to design and manage the alternate foraging ponds as effectively as possible, it was necessary to understand aspects of the biology of the storks, the characteristics of their foraging sites and the patterns of their use of the SRSS. Results are described

Results of toxicity tests and chemical analyses conducted on sediments collected from the TNX Outfall Delta Operable Unit, July 1999

International Nuclear Information System (INIS)

Specht, W.L.

2000-01-01

In order to provide unit specific toxicity data that will be used to address critical uncertainty in the ecological risk assessment (ERA) for the TNX Outfall Delta Operable Unit (TNXOD OU), sediments were collected from eight locations in the Inner Swamp portion of the operable unit and two unit specific background locations. These samples were analyzed for total mercury, total uranium, and sediment toxicity

Main problems experienced on diesel generators of French 900 MWe operating units

Energy Technology Data Exchange (ETDEWEB)

Dredemis, Geoffroy; Jude, Francois [Commissariat a l' Energie Atomique, centre d' Etudes Nucleaires de Fontenay-aux-Roses, Institut de Protection et Surete Nucleaire, Departement d' Analyse de Surete, B.P. No. 6, 92260 Fontenay-aux-Roses (France)

1986-02-15

Each unit of all the French nuclear power plant is equipped with two diesel emergency generator sets., For the totality of standards PWRs of 900 MWe, they are identical. We present in this communication the most significative failures met with diesel engines on operating units, such as rupture of fuel injection pipes, breaking of the connecting rods, and cylinder lubrication failures. All these incidents, which affected the emergency power sources of concerned units, had generic characteristics. In view of their potential consequences, it was proceeded in each case to an immediate control of the components concerned of all PWR 900 MWe diesel engines. At the same time, studies were started as to what modifications would permit to solve rapidly each one of the problems met with. (authors)

Computer Drawing Method for Operating Characteristic Curve of PV Power Plant Array Unit

Science.gov (United States)

Tan, Jianbin

2018-02-01

According to the engineering design of large-scale grid-connected photovoltaic power stations and the research and development of many simulation and analysis systems, it is necessary to draw a good computer graphics of the operating characteristic curves of photovoltaic array elements and to propose a good segmentation non-linear interpolation algorithm. In the calculation method, Component performance parameters as the main design basis, the computer can get 5 PV module performances. At the same time, combined with the PV array series and parallel connection, the computer drawing of the performance curve of the PV array unit can be realized. At the same time, the specific data onto the module of PV development software can be calculated, and the good operation of PV array unit can be improved on practical application.

Annual Summary Report, February to December 1998, for the 100-HR-3 and 100-KR-4 Pump-and-Treat Operations and Operable Units

International Nuclear Information System (INIS)

Boutin, R. J.

1999-01-01

This annual summary report discusses the interim remedial actions at the 100-HR-3 and 100-KR-4 Operable Units (OUs) for February 1,1998, through December 31, 1998. This is the second annual summary report that has been submitted for these OUs; the first report was released in April 1998 (DOE-RL 1998). Ongoing annual summaries and performance evaluations of each of the pump-and-treat systems are required by the Remedial Design Report and Remedial Action Work Plan for the 100-HR-3 and 100-KR-4 Groundwater Operable Units' Interim Action (RDR/RAWP) (DOE-RL 1996)

Remedial Design/Remedial Action Work Plan for Operable Units 6-05 and 10-04, Phase III

Energy Technology Data Exchange (ETDEWEB)

R. P. Wells

2006-09-19

The remedial design/remedial action for Operable Unit 6-05 (Waste Area Group 6) and Operable Unit 10-04 (Waste Area Group 10) - collectively called Operable Unit 10-04 has been divided into four phases. Phase I consists of developing and implementing institutional controls at Operable Unit 10-04 sites and developing and implementing Idaho National Laboratory-wide plans for both institutional controls and ecological monitoring. Phase II will remediate sites contaminated with trinitrotoluene and Royal Demolition Explosive. Phase III will remediate lead contamination at a gun range, and Phase IV will remediate hazards from unexploded ordnance. This Phase III remedial Design/Remedial Action Work Plan addresses the remediation of lead-contaminated soils found at the Security Training Facility (STF)-02 Gun Range located at the Idaho National Laboratory. Remediation of the STF-02 Gun Range will include excavating contaminated soils; physically separating copper and lead for recycling; returning separated soils below the remediation goal to the site; stabilizing contaminated soils, as required, and disposing of the separated soils that exceed the remediation goal; encapsulating and disposing of creosote-contaminated railroad ties and power poles; removing and disposing of the wooden building and asphalt pads found at the STF-02 Gun Range; sampling and analyzing soil to determine the excavation requirements; and when the remediation goals have been met, backfilling and contouring excavated areas and revegetating the affected area.

Changing priorities of codes and standards: An A/E's perspective for operating units and new generation

International Nuclear Information System (INIS)

Meyers, B.L.; Jackson, R.W.; Morowski, B.D.

1994-01-01

As the nuclear power industry has shifted emphasis from the construction of new plants to the reliability and maintenance of operating units, the industry's commitment to safety has been well guarded and maintained. Many other important indicators of nuclear industry performance are also positive. Unfortunately, by some projections, as many as 25 operating nuclear units could prematurely shutdown because of increasing O ampersand M and total operating costs. The immediate impact of higher generating costs on the nuclear industry is evident. However, when viewed over the longer-term, high generating costs will also affect license renewals, progress in the development of advanced light water reactor designs and prospects for a return to the building of new plants. Today's challenge is to leverage the expertise and contribution of the nuclear industry partner organizations to steadily improve the work processes and methods necessary to reduce operating costs, to achieve higher levels in the performance of operating units, and to maintain high standards of technical excellence and safety. From the experience and perspective of an A/E and partner in the nuclear industry, this paper will discuss the changing priorities of codes and standards as they relate to opportunities for the communication of lessons learned and improving the responsiveness to industry needs

Safety evaluation report related to the operation of Limerick Generating Station, Units 1 and 2 (Docket Nos. 50-352 and 50-353)

International Nuclear Information System (INIS)

1989-06-01

In August 1983 the staff of the Nuclear Regulatory Commission issued its Safety Evaluation Report (NUREG-0991) regarding the application of the Philadelphia Electric Company (the licensee) for licenses to operate the Limerick Generating Station, Units 1 and 2, located on site in Montgomery and Chester Counties, Pennsylvania. Supplement 1 to NUREG-0991 was issued in December 1983. Supplements 2 and 3 were issued in October 1984. License NPF-27 for the low-power operation of Limerick Unit 1 was issued on October 26, 1984. Supplement 4 was issued in May, 1985, Supplement 5 was issued in July 1985, and Supplement 6 was issued in August 1985. These supplements addressed further issues that required resolution before Unit 1 proceeded beyond the 5-percent power level. The full-power operating license for Limerick Unit 1 (NPF-39) was issued August 8, 1985, and the unit has completed two cycles of operation. Supplement 7 was issued April 1989 to address some of the few significant design differences between Units 1 and 2, the resolution of issues that remained open when the Unit 1 full-power license was issued and an assessment of some of the issues that required resolution before issuance of an operating license for Unit 2. This supplement addresses the remaining issues that required resolution before issuance of and operating license for Unit 2

Operational benchmark for VVER-1000, unit 6, Kozloduy NPP

International Nuclear Information System (INIS)

Apostolov, T.; Petrov, B.

1999-01-01

Benchmark calculations have been carried out using the 3D nodal code TRAPEZ. Global neutron-physics characteristics of the VVER-1000 core, Kozloduy NPP Unit 6, have been determined taking into account the real loading patterns and operational history of the first three cycles. The code TRLOAD has been used to perform the fuel reloading between any two cycles. The reactor and components descriptions as well as material compositions are given. The results presented include the critical boric acid concentration, the radial power distribution, the axial power distribution for the maximum overload assembly, and the burnup distribution at three different moments during each cycle. Calculated values have been compared with measured data. It is shown that the results obtained by the TRAPEZ code are in good agreement with the experimental data. The information presented could serve as a test case for validation of code packages designed for analyzing the steady-state operation of VVERs. (author)

200-BP-11 operable unit and 216-B-3 main pond work/closure plan, Hanford Site, Richland, Washington. Volume 1: Field investigation and sampling strategy

International Nuclear Information System (INIS)

1994-09-01

This document coordinates a Resource Conservation and Recovery Act (RCRA) past-practice work plan for the 200-BP-11 Operable Unit and a RCRA closure/postclosure plan for the 216-B-3 Main Pond and 216-B-3-3 Ditch [treatment, storage, and/or disposal (TSD) unit]. Both RCRA TSD and past-practice waste management units are contained within the 200-BP-11 Operable Unit. The 200-BP-11 Operable Unit is a source operable unit located on the east side of the B Plant Source Aggregate Area in the 200 East Area of the Hanford Site. The operable unit lies just east of the 200 East Area perimeter fence and encompass approximately 476 hectares (1,175 acres). Source operable units include waste management units that are potential sources of radioactive and/or hazardous substance contamination. Source waste management units are categorized in the Hanford Federal Facility Agreement and Consent Order as either RCRA TSD, RCRA past-practice, or Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) past-practice. As listed below and in the Tri-Party Agreement, the 200-BP-11 Operable Unit contains five RCRA past-practice and five RCRA TSD waste management units. Additionally, for RCRA TSD permitting purposes, the RCRA TSD waste management units are subdivided into two RCRA TSD units

Approach and plan for cleanup actions in the 100-FR-2 operable unit of the Hanford Site, Revision 0

International Nuclear Information System (INIS)

1995-06-01

A new administrative approach is being used to reach a cleanup decision for the 100-FR-2 Operable Unit. The unit, located at the 100-F Area, contains solid waste sites and is one of the remaining operable units scheduled for characterization and cleanup in the 100 Area. This Focus Package (1) describes the new approach and activities needed to reach a decision on cleanup actions for the 100-FR-2 Operable Unit and (2) invites public participation into the planning process. The previous approach included the production of a Work Plan, a Limited Field Investigation Report, a Qualitative Risk Assessment, a Focused Feasibility Study, and a Proposed Plan, all culminating in an interim action Record of Decision. Information gathered to date on other operable units allows the analgous site approach to be used on the 100-FR-2 Operable Unit, and therefore, a reduction in documentation preparation. The U.S. Environmental Protection Agency, Washington State Department of Ecology, and the U.S. Department of Energy (Tri-Party Agreement) believe that the new approach will save time and funding. In the new approach, the Work Plan has been condensed into this 12 page Focus Package. The Focus Package includes a summary of 100-F Area information, a list of waste sites in the 100-FR-2 Operable Unit, a summary of proposed work, and a schedule. The new approach will also combine the Limited Field Investigation and Qualitative Risk Assessment reports into the Focused Feasibility Study. The Focused Feasibility Study will analyze methods and costs to clean up waste sites. Consolidating the documents should reduce the time to complete the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) process by 16 months, compared to the previous approach

Coordinating bifurcated remediation of soil and groundwater at sites containing multiple operable units

International Nuclear Information System (INIS)

Laney, D.F.

1996-01-01

On larger and/or more complex sites, remediation of soil and groundwater is sometimes bifurcated. This presents some unique advantages with respect to expedited cleanup of one medium, however, it requires skillful planning and significant forethought to ensure that initial remediation efforts do not preclude some long-term options, and/or unduly influence the subsequent selection of a technology for the other operable units and/or media. this paper examines how the decision to bifurcate should be approached, the various methods of bifurcation, the advantages and disadvantages of bifurcation, and the best methods to build flexibility into the design of initial remediation systems so as to allow for consideration of a fuller range of options for remediation of other operable units and/or media at a later time. Pollutants of concern include: metals; petroleum hydrocarbons; and chlorinated solvents

Dresden Nuclear Power Station, Units 1, 2, and 3. Annual operating report: January thru December 1976

International Nuclear Information System (INIS)

1977-01-01

Net electrical energy generated by Unit 1 was 953,015.5 MWH with the generator on line 7,399.37 hrs. Unit 2 generated 4,371,553.689 MWH with the generator on line 6,664.58 hrs while Unit 3 generated 4,034,251 MWH with the generator on line 7,234.86 hrs. Information is presented concerning operations, maintenance, and shutdowns

Retrofitting and operation solid radwaste system Dresden Station, Units 2 and 3

International Nuclear Information System (INIS)

Testa, J.; Homer, J.C.

1982-01-01

Units 2 and 3 at Dresden Station are twin 794 MW (net) BWR units that became operational in 1970 and 1971. The waste streams are typical of BWR stations, namely, bead resin and filter sludge (powdered resins and diatomaceous earth), evaporator concentrate containing approximately 25% dissolved solids and dry active waste. The original solid radwaste system utilized cement for solidification in open top 55 gallon drums. Remote handling was provided by means of a monorail with moving platforms supporting the drums. A relatively light-weight compactor was used to compact DAW into 55 gallon drums. Difficulties were experienced with this system

Ambiguity in Units and the Referents: Two Cases in Rational Number Operations

Science.gov (United States)

Rathouz, Margaret

2010-01-01

I explore the impact of ambiguous referral to the unit on understanding of decimal and fraction operations during episodes in two different mathematics courses for pre-service teachers (PSTs). In one classroom, the instructor introduces a rectangular area diagram to help the PSTs visualize decimal multiplication. A transcript from this classroom…

Description of work for 100-DR-2 Operable Unit Vadose Drilling/test pits

International Nuclear Information System (INIS)

Naiknimbalkar, N.

1993-01-01

This report describes the scope of work for the boreholes/test pits of the 100-DR-2 Operable Unit. Sampling and field activities include: Soil screening; geologic sampling; soil sampling (physical property); analytical sampling and depths; and geophysical logging

Start-up and commercial operation of the Laguna Verde power plants, unit 1

International Nuclear Information System (INIS)

Torres R, J.F.

1991-01-01

The main features of the unit 1 of the Laguna Verde Power Plant is presented as well as the phases of the start-up process. The process includes various steps and tests up to start the commercial operation. (author)

Environmental assessment report: Nuclear Test Technology Complex. [Construction and operation of proposed facility

Energy Technology Data Exchange (ETDEWEB)

Tonnessen, K.; Tewes, H.A.

1982-08-01

The US Department of Energy (USDOE) is planning to construct and operate a structure, designated the Nuclear Test Technology Complex (NTTC), on a site located west of and adjacent to the Lawrence Livermore National Laboratory. The NTTC is designed to house 350 nuclear test program personnel, and will accommodate the needs of the entire staff of the continuing Nuclear Test Program (NTP). The project has three phases: land acquisition, facility construction and facility operation. The purpose of this environmental assessment report is to describe the activities associated with the three phases of the NTTC project and to evaluate potential environmental disruptions. The project site is located in a rural area of southeastern Alameda County, California, where the primary land use is agriculture; however, the County has zoned the area for industrial development. The environmental impacts of the project include surface disturbance, high noise levels, possible increases in site erosion, and decreased air quality. These impacts will occur primarily during the construction phase of the NTTC project and can be mitigated in part by measures proposed in this report.

Categorization of safety related motor operated valve safety significance for Ulchin Unit 3

International Nuclear Information System (INIS)

Kang, D. I.; Kim, K. Y.

2002-03-01

We performed a categorization of safety related Motor Operated Valve (MOV) safety significance for Ulchin Unit 3. The safety evaluation of MOV of domestic nuclear power plants affects the generic data used for the quantification of MOV common cause failure ( CCF) events in Ulchin Units 3 PSA. Therefore, in this study, we re-estimated the MGL(Multiple Greek Letter) parameter used for the evaluation of MOV CCF probabilities in Ulchin Units 3 Probabilistic Safety Assessment (PSA) and performed a classification of the MOV safety significance. The re-estimation results of the MGL parameter show that its value is decreased by 30% compared with the current value in Ulchin Unit 3 PSA. The categorization results of MOV safety significance using the changed value of MGL parameter shows that the number of HSSCs(High Safety Significant Components) is decreased by 54.5% compared with those using the current value of it in Ulchin Units 3 PSA

Water level measurements for modeling hydraulic properties in the 300-FF-5 and 100 Aggregate Area Operable units

International Nuclear Information System (INIS)

Campbell, M.D.; McMahon, W.J.; Simpson, K.R.

1993-04-01

Pressure transducers connected to dataloggers were used to measure ground water and Columbia River water elevations simultaneously and hourly at 35 locations in the 300-FF-5 Operable Unit and 16 locations in the 100 Aggregate Area Operable Unit on the Hanford Site. Water temperatures were also measured at 12 of these locations. This report details the findings of these studies

40 CFR 60.1690 - What are the operating practice requirements for my municipal waste combustion unit?

Science.gov (United States)

2010-07-01

... requirements for my municipal waste combustion unit? 60.1690 Section 60.1690 Protection of Environment... SOURCES Emission Guidelines and Compliance Times for Small Municipal Waste Combustion Units Constructed on or Before August 30, 1999 Model Rule-Good Combustion Practices: Operating Requirements § 60.1690 What...

Cooling unit for a superconducting power cable. Two years successful operation

Energy Technology Data Exchange (ETDEWEB)

Herzog, Friedhelm [Messer Group GmbH, Krefeld (Germany); Kutz, Thomas [Messer Industriegase GmbH, Bad Soden (Germany); Stemmle, Mark [Nexans Deutschland GmbH, Hannover (Germany); Kugel, Torsten [Westnetz GmbH, Essen (Germany)

2016-07-01

High temperature super conductors (HTS) can efficiently be cooled with liquid nitrogen down to a temperature of 64 K (-209 C). Lower temperatures are not practical, because nitrogen becomes solid at 63 K (-210 C). To achieve this temperature level the coolant has to be vaporized below atmospheric pressure. Messer has developed a cooling unit with an adequate vacuum subcooler, a liquid nitrogen circulation system, and a storage vessel for cooling an HTS power cable. The cooling unit was delivered in 2013 for the German AmpaCity project of RWE Deutschland AG, Nexans and Karlsruhe Institute of Technology. Within this project RWE and Nexans installed the worldwide longest superconducting power cable in the city of Essen, Germany. The cable is in operation since March 10th, 2014.

Nursing Leaders' Satisfaction with Information Systems in the Day-to-Day Operations Management in Hospital Units.

Science.gov (United States)

Peltonen, Laura-Maria; Junttila, Kristiina; Salanterä, Sanna

2018-01-01

Information usage in the day-to-day operations management of hospital units is complex due to numerous information systems in use. The aim of this study was to describe and compare nurse leaders' satisfaction with information systems used in the day-to-day operations management in hospital units. The design was a cross-sectional survey with five questions rated from one (disagree) to five (fully agree). The response rate was 65 % (n = 453). Respondents reported fair satisfaction with how information systems support decision-making (median 4, IQR 3-4) and improve ease of access to information (median 4, IQR 3-4). However, respondents were less satisfied with how systems improve speed of access to information (median 3, IQR 3-4). Nor did respondents think that systems were developed for them (median 3, IQR 2-4). Respondents further reported needing numerous systems daily to support decision-making (median 4, IQR 3-5). A clear need for one system, which would gather important information for display was stated (median 5, IQR 4-5). Work experience, gender and time when overseeing the unit were associated with some aspects related to satisfaction. In conclusion, information system improvements are needed to better support the day-to-day operations management in hospital units.

Study of the thermal behavior of a latent heat cold storage unit operating under frosting conditions

International Nuclear Information System (INIS)

Simard, A.P.; Lacroix, M.

2003-01-01

A study is performed of the thermal behavior of a latent heat cold storage unit operating under frosting conditions. This unit is employed to maintain the temperature inside the refrigerated compartment of a truck below 265 K. The system consists of parallel plates filled with a phase change material (PCM) that absorbs heat from the flow of warm moist air. A mathematical model for the system is first presented and, next, validated with numerical and experimental data. It is then exploited to assess the effects of design parameters and operating conditions on the performance of the system. The recommended thickness and distance separating the PCM plates are found to be 50x10 -3 and 30x10 -3 m, respectively. The results indicate that the performance of the unit is enhanced by turbulent air flow in spite of the increased pressure loss and accentuated frost growth. The unit also performs well even when the surrounding relative humidity is 100%

Baseline groundwater model update for p-area groundwater operable unit, NBN

Energy Technology Data Exchange (ETDEWEB)

Ross, J. [Savannah River Site (SRS), Aiken, SC (United States); Amidon, M. [Savannah River Site (SRS), Aiken, SC (United States)

2015-09-01

This report documents the development of a numerical groundwater flow and transport model of the hydrogeologic system of the P-Area Reactor Groundwater Operable Unit at the Savannah River Site (SRS) (Figure 1-1). The P-Area model provides a tool to aid in understanding the hydrologic and geochemical processes that control the development and migration of the current tritium, tetrachloroethene (PCE), and trichloroethene (TCE) plumes in this region.

Unreviewed Disposal Question Evaluation: Waste Disposal In Engineered Trench #3

Energy Technology Data Exchange (ETDEWEB)

Hamm, L. L.; Smith, F. G. III; Flach, G. P.; Hiergesell, R. A.; Butcher, B. T.

2013-07-29

Because Engineered Trench #3 (ET#3) will be placed in the location previously designated for Slit Trench #12 (ST#12), Solid Waste Management (SWM) requested that the Savannah River National Laboratory (SRNL) determine if the ST#12 limits could be employed as surrogate disposal limits for ET#3 operations. SRNL documented in this Unreviewed Disposal Question Evaluation (UDQE) that the use of ST#12 limits as surrogates for the new ET#3 disposal unit will provide reasonable assurance that Department of Energy (DOE) 435.1 performance objectives and measures (USDOE, 1999) will be protected. Therefore new ET#3 inventory limits as determined by a Special Analysis (SA) are not required.

Superfund record of decision (EPA Region 4): Savannah River Site (USDOE), F-Area Retention Basin (281-3F), Aiken, SC, September 4, 1998

International Nuclear Information System (INIS)

1999-05-01

The F-Area Retention Basin (FRB) Operable Unit (OU) includes the retention basin (basin soils), the former process sewer line (pipeline sediment, and pipeline associated soils), and the groundwater associated with the unit. This decision document presents the selected remedial alternatives for the FRB OU located at the SRS south of Aiken, South Carolina

Female Participation in Formed Police Units: A Report on the Integration of Women in Formed Police Units of Peacekeeping Operations

Science.gov (United States)

2012-09-01

of Peacekeeping Operations in accor- dance with the principles of United Nations (UN) Res- olution 1325. To address this topic the study (1) briefly...that the eligibility criteria was revised to include women who played support roles to the combatants, as cooks, por- ters, sex slaves or spies

Qualitative risk assessment for the 100-NR-2 Operable Unit. Revision 1

International Nuclear Information System (INIS)

1995-03-01

This qualitative risk assessment provides information about the 100- NR-2 Groundwater Operable Unit of the Hanford reservation. Topics discussed in this report are: data evaluation; human health risk assessment overview; ecological evaluations; summary of uncertainty; results of both the ecological and human health evaluations; toxicity assessment; risk characterization; and a summary of contaminants of potential concern

Surry Power Station, Units 1 and 2. Semiannual operating report, July--December 1974

International Nuclear Information System (INIS)

1974-01-01

Net electric power generated by Surry Unit 1 was 6,930,353 MWH with the generator on line for 10,417.7 hours. Net electric power generated by Unit 2 was 5,699,299 MWH with the generator on line for 8,384.2 hours. Information is presented concerning operation, radioactive effluent releases, solid radioactive wastes, fuel shipments, occurrences in which temperature limitations on the condenser cooling water discharge were exceeded, changes in station organization, occupational personnel radiation exposure, nonradiological monitoring including thermal, physical, and biological programs, and the radiological environmental monitoring program. (U.S.)

Turkey Point Plant, Units 3 and 4. Semiannual operating report No. 7, July--December 1975

International Nuclear Information System (INIS)

1976-01-01

Unit 3 generated 1,968,074 MWh(e) net electric power and the generator was on line 2,802.9 hrs. Unit 4 generated 2,560,476 MWh(e) and was on line 3,944.8 hrs. Information is presented concerning operations, power generation, shutdowns, maintenance, changes, tests, experiments, radioactive effluent releases, radiological environmental monitoring, and occupational personnel radiation monitoring

Scale-up of a mixer-settler extractor using a unit operations approach

International Nuclear Information System (INIS)

Lindholm, D.C.; Bautista, R.G.

1976-01-01

The results of scale-up studies on a continuous, multistage horizontal mixer-settler extractor are presented. The chemical and mechanical system involves the separation of lanthanum from a mixture of rare earth chlorides using di(2-ethylhexyl) phosphoric acid as the solvent and dilute HCl as a scrub solution in a bench scale extractor. Each stage has a hold-up of 2.6 l. A single stage unit is utilized for scale-up studies. Results are obtained on four sizes of geometrically similar units, the largest being six times the volume of the original bench size. A unit operations technique is chosen so that mixing and settling can be examined independently. Variables examined include type of continuous phase, flow rate of inlet streams, and power input to the mixer. Inlet flow-rate ratios are kept constant for all tests. Two potential methods of unbaffled pump-mixer scale-up are explored; the maintenance of constant impeller tip speed and constant power input. For the settler, the previously successful method of basing design on constant flow-rate per unit cross-sectional area is used

Dresden Nuclear Power Station, Units 1, 2, and 3. Semiannual report on operating and maintenance, July--December 1974

International Nuclear Information System (INIS)

1975-01-01

Unit 1 generated 388,882 MWH(e) and was on line 3111.2 hours, Unit 2 generated 1,204,106 MWH(e) and was on line 2013.4 hours, and Unit 3 generated 2,250,810 MWH(e) and was on line 3836 hours. Information is presented concerning operations, shutdowns, maintenance, changes, tests, and experiments for the three units. (U.S.)

Operation of the radioactive acid digestion test unit

International Nuclear Information System (INIS)

Blasewitz, A.G.; Allen, C.R.; Lerch, R.E.; Ely, P.C.; Richardson, G.L.

1980-01-01

The Radioactive Acid Digestion Test Unit (RADTU) has been constructed at Hanford to demonstrate the application of the Acid Digestion Process for treating combustible transuranic wastes and scrap materials. The RADTU with its original tray digestion vessel has recently completed a six-month campaign processing potentially contaminated nonglovebox wastes from a Hanford plutonium facility. During this campaign, it processed 2100 kg of largely cellulosic wastes at an average sustained processing rate of 3 kg/h as limited by the water boiloff rate from the acid feeds. The on-line operating efficiency was nearly 50% on a twelve hour/day, five day/week basis. Following this campaign, a new annular high rate digester has been installed for testing. In preliminary tests with simulated wastes, the new digester demonstrated a sustained capacity of 10 kg/h with greatly improved intimacy of contact between the digestion acid and the waste. The new design also doubles the heat transfer surface, which with reduced heat loss area, is expected to provide at least three times the water boiloff rate of the previous tray digester design. Following shakedown testing with simulated and low-level wastes, the new unit will be used to process combustible plutonium scrap and waste from Hanford plutonium facilities for the purposes of volume reduction, plutonium recovery, and stabilization of the final waste form

Engineering evaluation/conceptual plan for the 200-UP-1 Groundwater Operable Unit interim remedial measure. Revision 2

International Nuclear Information System (INIS)

1996-03-01

This report presents an engineering evaluation and conceptual plan for an interim remedial measure (IRM) to address a uranium and technetium-99 groundwater plume in the 200-UP-1 Groundwater Operable Unit located in the 200 West Area of the Hanford Site. This report provides information regarding the need for an IRM and its potentially achievable objectives and goals. The report also evaluates alternatives to contain elevated concentrations of uranium and technetium-99 and to obtain information necessary to develop final remedial actions for the operable unit

Hydrologic resources management program and underground test area operable unit fy 1997

Energy Technology Data Exchange (ETDEWEB)

Smith, D. F., LLNL

1998-05-01

This report present the results of FY 1997 technical studies conducted by the Lawrence Livermore National Laboratory (LLNL) as part of the Hydrology and Radionuclide Migration Program (HRMP) and Underground Test Area Operable Unit (UGTA). The HRMP is sponsored by the US Department of Energy to assess the environmental (radiochemical and hydrologic) consequences of underground nuclear weapons testing at the Nevada Test Site.

Development of a processor embedded timing unit for the synchronized operation in KSTAR

Energy Technology Data Exchange (ETDEWEB)

Lee, Woongryol, E-mail: wrlee@nfri.re.kr; Lee, Taegu; Hong, Jaesic

2016-11-15

Highlights: • Timing board for the synchronized tokamak operation. • Processor embedded distributed control system. • Single clock source and multiple trigger signal for the plasma diagnostics. • Delay compensation among the distributed timing boards. - Abstract: The Local Timing Unit (LTU) in KSTAR provides a single clock source and multiple trigger signals with flexible configuration. Over the past seven years, the LTU had a mechanical redesign and several firmware updates for the purpose of provision of a robust operation and precision timing signal. Now we have developed a third version of a local timing unit which has a standalone operation capability. The LTU is built in a cabinet mountable 1U PIZZA box and provides twelve signal output ports, a packet mirroring interface, and an LCD interface panel. The core functions of the LTU are implemented in a Field Programmable Gate Array (FPGA) which has an internal hardcore processor. The internal processor allows the use of Linux Operating System (OS) and the Experimental Physics and Industrial Control System (EPICS). All user level application functions are controllable through the EPICS, however the time critical internal functions are performed by the FPGA logic blocks same as the previous version. The new LTU provides pluggable output module so that we can easily extend the signal output port. The easy installation and effective replacement reduce the efforts of maintenance. This paper describes design, development, and commissioning results of the new KSTAR LTU.

Development of a processor embedded timing unit for the synchronized operation in KSTAR

International Nuclear Information System (INIS)

Lee, Woongryol; Lee, Taegu; Hong, Jaesic

2016-01-01

Highlights: • Timing board for the synchronized tokamak operation. • Processor embedded distributed control system. • Single clock source and multiple trigger signal for the plasma diagnostics. • Delay compensation among the distributed timing boards. - Abstract: The Local Timing Unit (LTU) in KSTAR provides a single clock source and multiple trigger signals with flexible configuration. Over the past seven years, the LTU had a mechanical redesign and several firmware updates for the purpose of provision of a robust operation and precision timing signal. Now we have developed a third version of a local timing unit which has a standalone operation capability. The LTU is built in a cabinet mountable 1U PIZZA box and provides twelve signal output ports, a packet mirroring interface, and an LCD interface panel. The core functions of the LTU are implemented in a Field Programmable Gate Array (FPGA) which has an internal hardcore processor. The internal processor allows the use of Linux Operating System (OS) and the Experimental Physics and Industrial Control System (EPICS). All user level application functions are controllable through the EPICS, however the time critical internal functions are performed by the FPGA logic blocks same as the previous version. The new LTU provides pluggable output module so that we can easily extend the signal output port. The easy installation and effective replacement reduce the efforts of maintenance. This paper describes design, development, and commissioning results of the new KSTAR LTU.

Selection of Forklift Unit for Warehouse Operation by Applying Multi-Criteria Analysis

Directory of Open Access Journals (Sweden)

Predrag Atanasković

2013-07-01

Full Text Available This paper presents research related to the choice of the criteria that can be used to perform an optimal selection of the forklift unit for warehouse operation. The analysis has been done with the aim of exploring the requirements and defining relevant criteria that are important when investment decision is made for forklift procurement, and based on the conducted research by applying multi-criteria analysis, to determine the appropriate parameters and their relative weights that form the input data and database for selection of the optimal handling unit. This paper presents an example of choosing the optimal forklift based on the selected criteria for the purpose of making the relevant investment decision.

Conceptual site models for groundwater contamination at 100-BC-5, 100-KR-4, 100-HR-3, and 100-FR-3 operable units

International Nuclear Information System (INIS)

Peterson, R.E.; Raidl, R.F.; Denslow, C.W.

1996-09-01

This document presents technical information on groundwater contamination in the 100-BC-5, 100-KR-4, 100-HR-3, and 100-FR-3 Operable Units on the Hanford Site in Richland, Washington. These operable units are defined for groundwater that underlies the retired plutonium production reactors and their associated support facilities. This technical information supports conceptual site models (CSM) for each operable unit. The goal in maintaining a CSM is to ensure that a reasonable understanding of contamination issues in each groundwater operable unit is available for selecting a final remediation alternative and for developing a record of decision. CSMs are developed for hazardous waste sites to help evaluate potential risks to human health and the environment from exposure to contamination

Donald C. Cook Nuclear Power Plant, Unit 1. Annual operating report for 1976

International Nuclear Information System (INIS)

1977-01-01

The unit was paralleled to the grid 83.1 percent of the time and 7,073,200 MWH gross was generated. There were six scheduled outages and 14 forced outages/load reductions. Information is presented concerning operations, shutdowns, power reductions, inservice maintenance, personnel radiation exposures, fuel history, and facility changes

Proposed plan for the 100-IU-1, 100-IU-3, 100-IU-4, AND 100-IU-5 Operable Units

International Nuclear Information System (INIS)

1995-06-01

This proposed plan identifies the preferred alternative for the Riverland Rad Yard, the Wahluke Slope, the Sodium Dichromate Baffel Landfill, and the, White Bluffs Pickling Acid Cribs, located at the Hanford Site. These areas are known respectively as the 100-IU-1, 100-IU-3, 100-IU-4, and 100-IU-5 Operable Units. Between 1992 and 1994, each of the four operable units was the subject of an expedited response action that addressed removal of site contaminants in soil. Waste sites in the 100-IU-2 (White Bluffs Townsite) and 100-IU-6 (Hanford Townsite) Operable Units will be addressed in future proposed plans. A proposed plan is intended to be a fact sheet for public review that summarizes the information relied upon to recommend the preferred alternative. As presented in this proposed plan, no further action is the preferred alternative for the final resolution of the 100-IU-1, 100-IU-3, 100-IU-4, and 100-IU-5 Operable Units. The preferred alternative is recommended because all suspect hazardous substances above cleanup levels have been removed from the waste sites, and the sites are unlikely to pose any significant risk to human health or the environment

Proposed plan for interim remedial measures at the 100-HR-1 Operable Unit, Hanford Site, Richland, Washington. Draft A

International Nuclear Information System (INIS)

1994-09-01

This proposed plan introduces the interim remedial measures for addressing contaminated soil at the 100-HR-1 Operable Unit, located at the Hanford Site. In addition, this plan includes a summary of other alternatives analyzed and considered for the 100-HR-1 Operable Unit. The EPA, DOE, and Washington State Dept. of Ecology believe that a combination of removal, treatment, and disposal technologies, where appropriate, would significantly reduce the potential threats to human health and the environment at the 100-HR-1 Operable Unit high-priority waste sites. The remedial actions described in this proposed plan are designed to minimize human health and ecological risks and ensure that additional contaminants originating from these waste sites are not transported to the groundwater. The 100-HR-1 Operable Unit contains the retention basin for the H reactor cooling system, process effluent trenches, the Pluto crib which received an estimated 260 gallons of radioactive liquid waste, process effluent pipelines, and solid waste sites used for the burial of decontaminated and decommissioned equipment from other facilities. Potential health threats would be from the isotopes of cesium, cobalt, europium, plutonium, and strontium, and from chromium, arsenic, lead, and chysene

Development of in situ product removal strategies in biocatalysis applying scaled-down unit operations.

Science.gov (United States)

Heintz, Søren; Börner, Tim; Ringborg, Rolf H; Rehn, Gustav; Grey, Carl; Nordblad, Mathias; Krühne, Ulrich; Gernaey, Krist V; Adlercreutz, Patrick; Woodley, John M

2017-03-01

An experimental platform based on scaled-down unit operations combined in a plug-and-play manner enables easy and highly flexible testing of advanced biocatalytic process options such as in situ product removal (ISPR) process strategies. In such a platform, it is possible to compartmentalize different process steps while operating it as a combined system, giving the possibility to test and characterize the performance of novel process concepts and biocatalysts with minimal influence of inhibitory products. Here the capabilities of performing process development by applying scaled-down unit operations are highlighted through a case study investigating the asymmetric synthesis of 1-methyl-3-phenylpropylamine (MPPA) using ω-transaminase, an enzyme in the sub-family of amino transferases (ATAs). An on-line HPLC system was applied to avoid manual sample handling and to semi-automatically characterize ω-transaminases in a scaled-down packed-bed reactor (PBR) module, showing MPPA as a strong inhibitor. To overcome the inhibition, a two-step liquid-liquid extraction (LLE) ISPR concept was tested using scaled-down unit operations combined in a plug-and-play manner. Through the tested ISPR concept, it was possible to continuously feed the main substrate benzylacetone (BA) and extract the main product MPPA throughout the reaction, thereby overcoming the challenges of low substrate solubility and product inhibition. The tested ISPR concept achieved a product concentration of 26.5 g MPPA  · L -1 , a purity up to 70% g MPPA  · g tot -1 and a recovery in the range of 80% mol · mol -1 of MPPA in 20 h, with the possibility to increase the concentration, purity, and recovery further. Biotechnol. Bioeng. 2017;114: 600-609. © 2016 Wiley Periodicals, Inc. © 2016 Wiley Periodicals, Inc.

Data compilation task report for the source investigation of the 300-FF-1 operable unit phase 1 remedial investigation

International Nuclear Information System (INIS)

Young, J.S.; Fruland, R.M.; Fruchter, J.S.

1990-02-01

This report provides additional information on facility and waste characteristics for the 300-FF-1 operable unit. The additional information gathered and reported includes meetings and on-site visits with current and past personnel having knowledge of operations in the operable unit, a more precise determination of the location of the Process Sewer lines and Retired Radioactive Liquid Waste Sewer, a better understanding of the phosphoric acid spill at the 340 Complex, and a search for engineering plans and environmental reports related to the operable unit. As a result of this data-gathering effort, recommendations for further investigation include characterization of the 307 Trenches to determine the origin of an underlying uranium plume in the groundwater, more extensive sampling of near-surface and dike sediments in the North and South Process Ponds to better define the extent of horizontal contamination, and detection of possible leaks in the abandoned Radioactive Waste Sewer by either electromagnetic induction or remote television camera inspection techniques. 16 refs., 4 figs., 5 tabs

Peach Bottom Atomic Power Station, Units 2 and 3. Annual operating report: January--December 1976

International Nuclear Information System (INIS)

1977-01-01

Unit 2 experienced 11 forced outages, 5 power reductions, and one major refueling outage which lasted about 3 months during which time the feedwater spargers were replaced. Net electrical power generated was 5,569,633 MWH with the generator on line 5,998 hrs. Unit 3 experienced 17 forced outages, 11 power reductions and 2 major outages. The first refueling outage began 12/24/77. Net electrical power generated was 6,049,644 MWH with the unit on line 6,829 hrs. Information is presented concerning operations, personnel exposures, radioactive releases, maintenance, and irradiated fuel examination

Superfund record of decision (EPA Region 4): Marzone Inc. /Chevron Chemical Company Superfund Site, Operable Unit 1, Tifton, GA, September 1994

Energy Technology Data Exchange (ETDEWEB)

1994-09-30

This decision document (Record of Decision) presents the selected remedial action for the Marzone, Inc./Chevron Chemical Company Site in Tift County, Georgia. EPA has organized the work at this Site into two phases or operable units (OUs). Operable Unit No. 1 involves contamination on the 1.68-acre former Marzone pesticide blending area, part of the Slack Property, and railroad drainage ditch past the southwest corner of the horse pasture, and contaminated groundwater related to the Site. This first operable unit is broken down into two separate remedies; one for groundwater and the other for soil.

Pilot-scale treatability test plan for the 100-HR-3 operable unit

International Nuclear Information System (INIS)

1994-08-01

This document presents the treatability test plan for pilot-scale pump-and-treat testing at the 100-HR-3 Operable Unit. The test will be conducted in fulfillment of interim Milestone M-15-06E to begin pilot-scale pump-and-treat operations by August 1994. The scope of the test was determined based on the results of lab/bench-scale tests (WHC 1993a) conducted in fulfillment of Milestone M-15-06B. These milestones were established per agreement between the U.S. Department of Energy (DOE), the Washington State Department of Ecology and the U.S. Environmental Protection Agency (EPA), and documented on Hanford Federal of Ecology Facility Agreement and Consent Order Change Control Form M-15-93-02. This test plan discusses a pilot-scale pump-and-treat test for the chromium plume associated with the D Reactor portion of the 100-HR-3 Operable Unit. Data will be collected during the pilot test to assess the effectiveness, operating parameters, and resource needs of the ion exchange (IX) pump-and-treat system. The test will provide information to assess the ability to remove contaminants by extracting groundwater from wells and treating extracted groundwater using IX. Bench-scale tests were conducted previously in which chromium VI was identified as the primary contaminant of concern in the 100-D reactor plume. The DOWEX 21K trademark resin was recommended for pilot-scale testing of an IX pump-and-treat system. The bench-scale test demonstrated that the system could remove chromium VI from groundwater to concentrations less than 50 ppb. The test also identified process parameters to monitor during pilot-scale testing. Water will be re-injected into the plume using wells outside the zone of influence and upgradient of the extraction well

The Vertebrate Brain, Evidence of Its Modular Organization and Operating System: Insights into the Brain's Basic Units of Structure, Function, and Operation and How They Influence Neuronal Signaling and Behavior

Science.gov (United States)

Baslow, Morris H.

2011-01-01

The human brain is a complex organ made up of neurons and several other cell types, and whose role is processing information for use in eliciting behaviors. However, the composition of its repeating cellular units for both structure and function are unresolved. Based on recent descriptions of the brain's physiological “operating system”, a function of the tri-cellular metabolism of N-acetylaspartate (NAA) and N-acetylaspartylglutamate (NAAG) for supply of energy, and on the nature of “neuronal words and languages” for intercellular communication, insights into the brain's modular structural and functional units have been gained. In this article, it is proposed that the basic structural unit in brain is defined by its physiological operating system, and that it consists of a single neuron, and one or more astrocytes, oligodendrocytes, and vascular system endothelial cells. It is also proposed that the basic functional unit in the brain is defined by how neurons communicate, and consists of two neurons and their interconnecting dendritic–synaptic–dendritic field. Since a functional unit is composed of two neurons, it requires two structural units to form a functional unit. Thus, the brain can be envisioned as being made up of the three-dimensional stacking and intertwining of myriad structural units which results not only in its gross structure, but also in producing a uniform distribution of binary functional units. Since the physiological NAA–NAAG operating system for supply of energy is repeated in every structural unit, it is positioned to control global brain function. PMID:21720525

The Vertebrate Brain, Evidence of Its Modular Organization and Operating System: Insights into the Brain's Basic Units of Structure, Function, and Operation and How They Influence Neuronal Signaling and Behavior.

Science.gov (United States)

Baslow, Morris H

2011-01-01

The human brain is a complex organ made up of neurons and several other cell types, and whose role is processing information for use in eliciting behaviors. However, the composition of its repeating cellular units for both structure and function are unresolved. Based on recent descriptions of the brain's physiological "operating system", a function of the tri-cellular metabolism of N-acetylaspartate (NAA) and N-acetylaspartylglutamate (NAAG) for supply of energy, and on the nature of "neuronal words and languages" for intercellular communication, insights into the brain's modular structural and functional units have been gained. In this article, it is proposed that the basic structural unit in brain is defined by its physiological operating system, and that it consists of a single neuron, and one or more astrocytes, oligodendrocytes, and vascular system endothelial cells. It is also proposed that the basic functional unit in the brain is defined by how neurons communicate, and consists of two neurons and their interconnecting dendritic-synaptic-dendritic field. Since a functional unit is composed of two neurons, it requires two structural units to form a functional unit. Thus, the brain can be envisioned as being made up of the three-dimensional stacking and intertwining of myriad structural units which results not only in its gross structure, but also in producing a uniform distribution of binary functional units. Since the physiological NAA-NAAG operating system for supply of energy is repeated in every structural unit, it is positioned to control global brain function.

Numerical Analysis of Loss of Residual Heal Removal System (RHRS) during Mid-Loop Operation for Hanul NPP Units 1 and 2

Energy Technology Data Exchange (ETDEWEB)

Kim, Sook Kwan; Park, Seong Gyu; Han, Sang Koo [ACT Co., Daejeon (Korea, Republic of)

2016-10-15

As a part of supporting LPSD (Low Power and Shutdown) PSA (Probabilistic Safety Assessment) of Hanul NPP units 1 and 2, numerical analysis for a loss of RHRS (Residual Heat Removal system) during midloop operation was performed using RELAP5/MOD3.3 code. The one of main purpose of thermal hydraulic analysis for PSA work is to estimate times allowable for operation actions in each accident. A loss of RHRS during mid-loop operation may cause more significant results than during RCS full condition due to reduced RCS inventory. In order to perform this kind of analysis, it is particularly important to establish a steady state of mid-loop operational initial condition. Mid-loop operation corresponds to POS(Plant Operational State) 5 and 11 in the category of LPSD PSA at Hanul NPP units 1 and 2. RELAP5/MOD3.3 code was used to predict behaviors of RCS and fuels for the case of loss of RHRS during mid-loop operation at Hanul NPP units 1 and 2. The initial state of mid-loop operational condition was established by proper control of charging and letdown flow. Considering existing similar analysis results for this kind of accident, it can be concluded that RELAP5 code well predicts reasonably the behavior of RCS for loss of RHRS during mid-loop operation in Hanul NPP units 1 and 2. Thus the method developed in the analysis can be applied reasonably to support LPSD PSA.

78 FR 32278 - Vogtle Electric Generating Station, Units 3 and 4; Southern Nuclear Operating Company; Change to...

Science.gov (United States)

2013-05-29

... Generating Station, Units 3 and 4; Southern Nuclear Operating Company; Change to Information in Tier 1, Table... Nuclear Operating Company, Inc., and Georgia Power Company, Oglethorpe Power Corporation, Municipal... Table 3.3-1, ``Definition of Wall Thicknesses for Nuclear Island Buildings, Turbine Buildings, and Annex...

The advanced neutron source safety approach and plans

International Nuclear Information System (INIS)

Harrington, R.M.

1989-01-01

The Advanced Neutron Source (ANS) is a user facility for all areas of neutron research proposed for construction at the Oak Ridge National Laboratory. The neutron source is planned to be a 350-MW research reactor. The reactor, currently in conceptual design, will belong to the United States Department of Energy (USDOE). The safety approach and planned elements of the safety program for the ANS are described. The safety approach is to incorporate USDOE requirements [which, by reference, include appropriate requirements from the United States Nuclear Regulatory Commission (USNRC) and other national and state regulatory agencies] into the design, and to utilize probabilistic risk assessment (PRA) techniques during design to achieve extremely low probability of severe core damage. The PRA has already begun and will continue throughout the design and construction of the reactor. Computer analyses will be conducted for a complete spectrum of accidental events, from anticipated events to very infrequent occurrences. 8 refs., 2 tabs

The Advanced Neutron Source safety approach and plans

International Nuclear Information System (INIS)

Harrington, R.M.

1990-01-01

The Advanced Neutron Source (ANS) is a user facility proposed for construction at the Oak Ridge National Laboratory for all areas of neutron research. The neutron source is planned to be a 350-MW research reactor. The reactor, currently in conceptual design, will belong to the United States Department of Energy (USDOE). The safety approach and planned elements of the safety program for the ANS are described. The safety approach is to incorporate USDOE requirements (which, by reference, include appropriate requirements from the United States Nuclear Regulatory Commission (USNRC) and other national and state regulatory agencies) into the design, and to utilize probabilistic risk assessment (PRA) techniques during design to achieve extremely low probability of severe core damage. The PRA has already begun and will continue throughout the design and construction of the reactor. Computer analyses will be conducted for a complete spectrum of accidental events, from anticipated events to very infrequent occurrences

Field measurement of the piping system vibration of Ko-Ri unit 4 during the load-following operation

International Nuclear Information System (INIS)

Chung, Tae-Young; Hong, Sung-Yull; Kim, Bum-Nyun.

1989-01-01

During the load-following operation of nuclear power plants, flow rate, temperature, and pressure in the piping system can be varied by changing the electric power output level, and these variations can cause different vibration phenomena in the piping system. The piping system vibration is important because it is directly related to the dynamic stress of the piping system and can affect the life of the piping system through structural fatigue. An assessment of vibration levels for the classes II and III piping systems of the Ko-Ri Unit 4950-MW nuclear power plant was performed according to the given pattern of the load-following operation to study its feasibility from the viewpoint of piping system vibration. The classes II and III piping system vibration of the Ko-Ri Unit 4 may not cause any potential problem under the given pattern of the load-following operation; however, it is recommended that long-term operation in the 85 to 95% power range be avoided as much as possible

40 CFR Table 14 to Subpart Uuu of... - Continuous Compliance With Operating Limits for Organic HAP Emissions From Catalytic Cracking Units

Science.gov (United States)

2010-07-01

... 40 Protection of Environment 12 2010-07-01 2010-07-01 true Continuous Compliance With Operating Limits for Organic HAP Emissions From Catalytic Cracking Units 14 Table 14 to Subpart UUU of Part 63... Compliance With Operating Limits for Organic HAP Emissions From Catalytic Cracking Units As stated in § 63...

40 CFR Table 21 to Subpart Uuu of... - Continuous Compliance With Operating Limits for Organic HAP Emissions From Catalytic Reforming Units

Science.gov (United States)

2010-07-01

... 40 Protection of Environment 12 2010-07-01 2010-07-01 true Continuous Compliance With Operating Limits for Organic HAP Emissions From Catalytic Reforming Units 21 Table 21 to Subpart UUU of Part 63... Compliance With Operating Limits for Organic HAP Emissions From Catalytic Reforming Units As stated in § 63...

Regulating manure application discharges from concentrated animal feeding operations in the United States

International Nuclear Information System (INIS)

Centner, Terence J.; Feitshans, Theodore A.

2006-01-01

In the United States, reducing pollution from agriculture has received attention due to data suggesting that this is the leading source of impairment of many waterbodies. The federal government revised its regulations governing concentrated animal feeding operations (CAFOs) to enhance governmental oversight over sources of pollution. For the application of manure resulting in pollutant discharges, CAFOs need to implement nutrient management plans. A federal court affirmed the ability of the US federal government to oversee the application of manure from CAFOs that have discharges. Simultaneously, owners and operators of CAFOs who have implemented an appropriate nutrient management plan may forgo securing a permit if their discharges qualify under the agricultural stormwater discharge exemption. - New rules applying to the application of manure by large concentrated animal feeding operations should reduce water contamination

Phase I and II feasibility study report for the 300-FF-5 operable unit

Energy Technology Data Exchange (ETDEWEB)

NONE

1993-12-31

The purpose of this Phase I/II feasibility study is to assemble and screen a list of alternatives for remediation of the 300-FF-5 operable site on the Hanford Reservation. This screening is based on information gathered in the Phase I Remedial Investigation (RI) and on currently available information on remediation technologies. The alternatives remaining after screening provide a range of response actions for remediation. In addition, key data needs are identified for collection during a Phase II RI (if necessary). This Phase I/II FS represents a primary document as defined by the Tri-Party Agreement, but will be followed by a Phase III FS that will further develop the alternatives and provide a detailed evaluation of them. The following remedial action objectives were identified for the 300-FF-5 operable unit: Limit current human exposure to contaminated groundwater in the unit; Limit discharge of contaminated groundwater to the Columbia River; Reduce contaminant concentrations in groundwater below acceptable levels by the year 2018.

Phase I and II feasibility study report for the 300-FF-5 operable unit

International Nuclear Information System (INIS)

1993-01-01

The purpose of this Phase I/II feasibility study is to assemble and screen a list of alternatives for remediation of the 300-FF-5 operable site on the Hanford Reservation. This screening is based on information gathered in the Phase I Remedial Investigation (RI) and on currently available information on remediation technologies. The alternatives remaining after screening provide a range of response actions for remediation. In addition, key data needs are identified for collection during a Phase II RI (if necessary). This Phase I/II FS represents a primary document as defined by the Tri-Party Agreement, but will be followed by a Phase III FS that will further develop the alternatives and provide a detailed evaluation of them. The following remedial action objectives were identified for the 300-FF-5 operable unit: Limit current human exposure to contaminated groundwater in the unit; Limit discharge of contaminated groundwater to the Columbia River; Reduce contaminant concentrations in groundwater below acceptable levels by the year 2018

Start up and commercial operation of Laguna Verde nuclear power plant. Unit 1

International Nuclear Information System (INIS)

Torres Ramirez, J.F.

1991-01-01

Prior to start up of Laguna Verde nuclear power plant preoperational tests and start tests were performed and they are described in its more eminent aspects. In relation to commercial operation of nuclear station a series of indicator were set to which allow the measurement of performance in unit 1, in areas of plant efficiency and personal safety. Antecedents. Laguna Verde station is located in Alto Lucero municipality in Veracruz state, 70 kilometers north-northeast from port of Veracruz and a 290 kilometers east-northeast from Mexico city. The station consist of two units manufactured by General Electric, with a nuclear system of vapor supply also called boiling water (BWR/5), and with a system turbine-generator manufactured by Mitsubishi. Each unit has a nominal power of 1931 MWt and a level design power of 675 Mwe and a net power of 654 Electric Megawatts

Safety evaluation report related to the operation of Limerick Generating Station, Units 1 and 2, Docket nos. 50-352 and 50-353

International Nuclear Information System (INIS)

1989-08-01

In August 1983 the staff of the Nuclear Regulatory commission issued its Safety Evaluation Report (NUREG-0991) regarding the application of the Philadelphia Electric Company (the licensee) for the licenses to operate the Limerick Generating Station, Units 1 and 2, located on a site in Montgomery and Chester Counties, Pennsylvania. Supplement 1 was issued in December 1983. Supplement 2 was issued in October 1984. Supplement 3 was issued in October 1984. Supplement 4 was issued in May 1985. Supplement 5 was issued in July 1985. Supplement 6 was issued in August 1985 and Supplement 7 was issued in April 1989. Supplement 7 addresses the major design differences between Units 1 and 2, the resolution of all issues that remained open when the Unit 1 full-power license was issued, the staff's assessment regarding the application by the licensee to operate Unit 2 and issues that require resolution before issuance of an operating license for Unit 2. Supplements 8 and 9 address further issues that require resolution prior to issuance of an operating license. 1 tab

Report on geological surveys in the 300-FF-1 operable unit

International Nuclear Information System (INIS)

Sandness, G.A.

1991-03-01

This report describes a set of geophysical surveys performed by the Pacific Northwest Laboratory at selected locations within the 300-FF-1 Operable Unit at Hanford. Field work and preliminary data processing activities were initiated in September 1989. These actions were terminated by the Westinghouse Hanford Company before completion in December 1989. Work was reinitiated in October 1990, to complete the processing of the data that had already been collected and to report the results. Because the field work was only partially completed, the task objectives, as presented in the Statement of Work, could not be fully met. This report is, therefore, a progress report covering the work performed through December 11, 1989. This task involved (1) ground-penetrating radar surveys of the 618-4 and 618-5 Burial Grounds, and (2) ground-penetrating radar and electromagnetic induction surveys along the assumed routes of the abandoned process sewers and radioactive liquid waste sewers in the 300-FF-1 Operable Unit. The surveys in the burial grounds were intended to identify burial trenches and pits, to determine the depth of fill, and to locate waste materials, including any that might be outside the perimeter fences. The surveys along the sewer routes were intended, first, to confirm the locations of the sewers as shown on existing maps or to otherwise accurately determine their locations, and second, to attempt to identify locations of possible leaks. 3 refs., 3 figs., 2 tabs

40 CFR Table 7 to Subpart Uuu of... - Continuous Compliance With Operating Limits for Metal HAP Emissions From Catalytic Cracking Units

Science.gov (United States)

2010-07-01

... 40 Protection of Environment 12 2010-07-01 2010-07-01 true Continuous Compliance With Operating Limits for Metal HAP Emissions From Catalytic Cracking Units 7 Table 7 to Subpart UUU of Part 63... With Operating Limits for Metal HAP Emissions From Catalytic Cracking Units As stated in § 63.1564(c)(1...

Analysis of the Vertical Takeoff and Landing Unmanned Aerial Vehicle (VTUAV) in Small Unit Urban Operations

National Research Council Canada - National Science Library

Cason, Roman

2004-01-01

...) to replace the aging Pioneer Unmanned Aerial Vehicle (UAV) system. This thesis examines the critical elements this platform must possess to effectively support small units operating in urban environments...

USDOE radioactive waste incineration technology: status review

International Nuclear Information System (INIS)

Borduin, L.C.; Taboas, A.L.

1980-01-01

Early attempts were made to incinerate radioactive wastes met with operation and equipment problems such as feed preparation, corrosion, inadequate off-gas cleanup, incomplete combustion, and isotope containment. The US Department of Energy (DOE) continues to sponsor research, development, and the eventual demonstration of radioactive waste incineration. In addition, several industries are developing proprietary incineration system designs to meet other specific radwaste processing requirements. Although development efforts continue, significant results are available for the nuclear community and the general public to draw on in planning. This paper presents an introduction to incineration concerns, and an overview of the prominent radwaste incineration processes being developed within DOE. Brief process descriptions, status and goals of individual incineration systems, and planned or potential applications are also included

Unit operations used to treat process and/or waste streams at nuclear power plants

International Nuclear Information System (INIS)

Godbee, H.W.; Kibbey, A.H.

1980-01-01

Estimates are given of the annual amounts of each generic type of LLW [i.e., Government and commerical (fuel cycle and non-fuel cycle)] that is generated at LWR plants. Many different chemical engineering unit operations used to treat process and/or waste streams at LWR plants include adsorption, evaporation, calcination, centrifugation, compaction, crystallization, drying, filtration, incineration, reverse osmosis, and solidification of waste residues. The treatment of these various streams and the secondary wet solid wastes thus generated is described. The various treatment options for concentrates or solid wet wastes, and for dry wastes are discussed. Among the dry waste treatment methods are compaction, baling, and incineration, as well as chopping, cutting and shredding. Organic materials [liquids (e.g., oils or solvents) and/or solids], could be incinerated in most cases. The filter sludges, spent resins, and concentrated liquids (e.g., evaporator concentrates) are usually solidified in cement, or urea-formaldehyde or unsaturated polyester resins prior to burial. Incinerator ashes can also be incorporated in these binding agents. Asphalt has not yet been used. This paper presents a brief survey of operational experience at LWRs with various unit operations, including a short discussion of problems and some observations on recent trends

Automated processing of whole blood units: operational value and in vitro quality of final blood components.

Science.gov (United States)

Jurado, Marisa; Algora, Manuel; Garcia-Sanchez, Félix; Vico, Santiago; Rodriguez, Eva; Perez, Sonia; Barbolla, Luz

2012-01-01

The Community Transfusion Centre in Madrid currently processes whole blood using a conventional procedure (Compomat, Fresenius) followed by automated processing of buffy coats with the OrbiSac system (CaridianBCT). The Atreus 3C system (CaridianBCT) automates the production of red blood cells, plasma and an interim platelet unit from a whole blood unit. Interim platelet unit are pooled to produce a transfusable platelet unit. In this study the Atreus 3C system was evaluated and compared to the routine method with regards to product quality and operational value. Over a 5-week period 810 whole blood units were processed using the Atreus 3C system. The attributes of the automated process were compared to those of the routine method by assessing productivity, space, equipment and staffing requirements. The data obtained were evaluated in order to estimate the impact of implementing the Atreus 3C system in the routine setting of the blood centre. Yield and in vitro quality of the final blood components processed with the two systems were evaluated and compared. The Atreus 3C system enabled higher throughput while requiring less space and employee time by decreasing the amount of equipment and processing time per unit of whole blood processed. Whole blood units processed on the Atreus 3C system gave a higher platelet yield, a similar amount of red blood cells and a smaller volume of plasma. These results support the conclusion that the Atreus 3C system produces blood components meeting quality requirements while providing a high operational efficiency. Implementation of the Atreus 3C system could result in a large organisational improvement.

Dose rate evaluation of workers on the operation floor in Fukushima-Daiichi Unit 3

Science.gov (United States)

Matsushita, Kaoru; Kurosawa, Masahiko; Shirai, Keisuke; Matsuoka, Ippei; Mukaida, Naoki

2017-09-01

At Fukushima Daiichi Nuclear Power Plant Unit 3, installation of a fuel handling machine is planned to support the removal of spent fuel. The dose rates at the workplace were calculated based on the source distribution measured using a collimator in order to confirm that the dose rates on the operation floor were within a manageable range. It was confirmed that the accuracy of the source distribution was C/M = 1.0-2.4. These dose rates were then used to plan the work on the operation floor.

Development of in-situ product removal strategies in biocatalysis applying scaled-down unit operations

DEFF Research Database (Denmark)

Heintz, Søren; Börner, Tim; Ringborg, Rolf Hoffmeyer

2017-01-01

different process steps while operating it as a combined system, giving the possibility to test and characterize the performance of novel process concepts and biocatalysts with minimal influence of inhibitory products. Here the capabilities of performing process development by applying scaled-down unit...... operations are highlighted through a case study investigating the asymmetric synthesis of 1-methyl-3-phenylpropylamine (MPPA) using ω-transaminase, an enzyme in the sub-family of amino transferases (ATAs). An on-line HPLC system was applied to avoid manual sample handling and to semi...

Potential contribution of currently operating nuclear-fueled electric-generating units to reducing US oil consumption

International Nuclear Information System (INIS)

Koppe, R.H.; Olson, E.A.J.; Van Howe, K.R.

1980-01-01

This study examines the prospect for performance improvement in the 62 light water reactors in operation in the US as of the end of last year and which are deemed to have current commercial design features. These units represent a total net capacity of 49,481 MW(e). In the last two years (1978 to 1979), total capacity factor losses for these units was 36.5%. This study finds that in the short-term, capacity factor improvement of about 16% could be achieved, for example, in response to a short-term energy crisis. In the long-term a gain of perhaps 18% could be achieved. Such gains would represent a decrease in equivalent oil consumption of approximately 350,000 barrels a day. In addition, this study evaluated potential increases in the operating power level of these units, and concluded that a short term power level increase of about 2500 MW(e) could be achieved, in addition to a long term increase of about 1700 MW(e). This total short term power level increase would be equivalent to 138,000 barrels of oil per day

40 CFR 257.5 - Disposal standards for owners/operators of non-municipal non-hazardous waste disposal units that...

Science.gov (United States)

2010-07-01

... compliance with §§ 257.7 through 257.30 prior to the receipt of CESQG hazardous waste. (b) Definitions.... Waste management unit boundary means a vertical surface located at the hydraulically downgradient limit.../operators of non-municipal non-hazardous waste disposal units that receive Conditionally Exempt Small...

Continuous operation of NPP Kori Unit 1 - Fireproof paint for cables

International Nuclear Information System (INIS)

Wendt, Dipl-Ing. Ruediger; Kim, Duill; Sik, Cho Hong

2008-01-01

Fireproof cable coating materials have been used in European NPP, especially in Germany, Russia, Ukraine, Czech Republic, Lithuania, Switzerland. Wide experiences were made during operation while applying these systems. In NPP Kori, Unit 1, a fire proof cable coating project was realised for the first time in a NPP of KHNP. The scope of services of the cable trays to coat amounts to 15,587m 2 . In different fire compartments and rooms the cables should be coated partially respectively completely with the fire proof cable coating system. The extent of cable surfaces to coat was stipulated by KHNP on the basis of an analysis made by KHNP. The project was tendered on the basis of a technical specification of KHNP. The specification is mainly predicted on Korean and US standards. The most important criteria for the fire proof cable coating is resumed as follows: The fireproof cable coating has to assure the fire protection of the cables for a period defined and for operational conditions defined in such a manner that the general conditions for the operation of the cable installation will not be affected

40 CFR Table 30 to Subpart Uuu of... - Operating Limits for HAP Emissions From Sulfur Recovery Units

Science.gov (United States)

2010-07-01

... 40 Protection of Environment 12 2010-07-01 2010-07-01 true Operating Limits for HAP Emissions From Sulfur Recovery Units 30 Table 30 to Subpart UUU of Part 63 Protection of Environment ENVIRONMENTAL..., Table 30 Table 30 to Subpart UUU of Part 63—Operating Limits for HAP Emissions From Sulfur Recovery...

Superfund record of decision (EPA Region 4): Savannah River Site (USDOE) D-Area Oil Seepage Basin (631-G), Aiken, SC, August 14, 1998

International Nuclear Information System (INIS)

1999-03-01

The D-Area Oil Seepage Basin (D-Area OSB) Operable Unit (OU) is listed as a Resource Conservation and Recovery Act (RCRA) 3004(u) Solid Waste Management Unit/Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) unit in Appendix C of the Federal Facility Agreement (FFA) for the Savannah River Site (SRS). No Action is the selected remedy for shallow soil, surface water and sediment, because no constituents of concern (COCs) were identified for them in the RCRA Facility Investigation/Remedial Investigation/Baseline Risk Assessment (RFI/RI/BRA). The selected remedy for D-Area OSB groundwater is Alternative GW-2: Natural Attenuation/Groundwater Mixing Zone (GWMZ) with Institutional Controls

NSSS design and cycle 1 operating history data for Arkansas Nuclear One, Unit-2. Final report

International Nuclear Information System (INIS)

Gagne, P.A.

1981-03-01

This report contains design and cycle 1 operating data for the Arkansas Nuclear One, Unit-2 nuclear steam supply system. The design data include descriptions of the reactor core, reactor coolant system, and control systems which are a part of the nuclear steam supply system. Operating history data are provided for the period of December 1978 through January 1980. The most important operating history data provided include reactor power, cumulative fuel burnup, control rod position, primary coolant temperature, and a series of power distribution state points

Organization and methodology applied to the control of commissioning tests to guarantee safe operation of nuclear units

International Nuclear Information System (INIS)

Clausner, J.P.; Jorel, M.

1990-12-01

This paper describes the activities of the Safety Analysis Department (DAS), which provides technical support for the French safety authorities in the specific context of analysis and control of startup test programme quality at each of the different stages of the programme. These activities combine to ensure that the objective of the startup tests is reached, in particular that the functions of each safety-related system are guaranteed in all operating configurations, that the performance levels of all components in the system comply with design criteria and that defects revealed during previous tests have been dealt with correctly. The special case of French nuclear facilities, linked to unit standardization, has made it possible to acquire a large amount of experience with the startup of the 900 MWe units and has illustrated the importance of defining a startup test programme. In 1981, a working group, comprising operating organization and safety authority representatives, studied the lessons which had to be learned from 900 MWe unit startup and the improvements which could be made and taken into account in the 1300 MWe unit startup programme. To illustrate the approach adopted by the DAS, we go on to describe the lessons learned from startup of the first 1300 MWe (P4) units

How do strategic decisions and operative practices affect operating room productivity?

Science.gov (United States)

Peltokorpi, Antti

2011-12-01

Surgical operating rooms are cost-intensive parts of health service production. Managing operating units efficiently is essential when hospitals and healthcare systems aim to maximize health outcomes with limited resources. Previous research about operating room management has focused on studying the effect of management practices and decisions on efficiency by utilizing mainly modeling approach or before-after analysis in single hospital case. The purpose of this research is to analyze the synergic effect of strategic decisions and operative management practices on operating room productivity and to use a multiple case study method enabling statistical hypothesis testing with empirical data. 11 hypotheses that propose connections between the use of strategic and operative practices and productivity were tested in a multi-hospital study that included 26 units. The results indicate that operative practices, such as personnel management, case scheduling and performance measurement, affect productivity more remarkably than do strategic decisions that relate to, e.g., units' size, scope or academic status. Units with different strategic positions should apply different operative practices: Focused hospital units benefit most from sophisticated case scheduling and parallel processing whereas central and ambulatory units should apply flexible working hours, incentives and multi-skilled personnel. Operating units should be more active in applying management practices which are adequate for their strategic orientation.

Assessing Energy Efficiency Opportunities in US Industrial and Commercial Building Motor Systems

Energy Technology Data Exchange (ETDEWEB)

Rao, Prakash; Sheaffer, Paul; McKane, Aimee; Scheihing, Paul

2015-09-01

In 2002, the United States Department of Energy (USDOE) published an energy efficiency assessment of U.S. industrial sector motor systems titled United States Industrial Electric Motor Systems Market Opportunities Assessment. The assessment advanced motor system efficiency by providing a greater understanding of the energy consumption, use characteristics, and energy efficiency improvement potential of industrial sector motor systems in the U.S. Since 2002, regulations such as Minimum Energy Performance Standards, cost reductions for motor system components such as variable frequency drives, system-integrated motor-driven equipment, and awareness programs for motor system energy efficiency have changed the landscape of U.S. motor system energy consumption. To capture the new landscape, the USDOE has initiated a three-year Motor System Market Assessment (MSMA), led by Lawrence Berkeley National Laboratory (LBNL). The MSMA will assess the energy consumption, operational and maintenance characteristics, and efficiency improvement opportunity of U.S. industrial sector and commercial building motor systems. As part of the MSMA, a significant effort is currently underway to conduct field assessments of motor systems from a sample of facilities representative of U.S. commercial and industrial motor system energy consumption. The Field Assessment Plan used for these assessments builds on recent LBNL research presented at EEMODS 2011 and EEMODS 2013 using methods for characterizing and determining regional motor system energy efficiency opportunities. This paper provides an update on the development and progress of the MSMA, focusing on the Field Assessment Plan and the framework for assessing the global supply chain for emerging motors and drive technologies.

Corrective economic dispatch and operational cycles for probabilistic unit commitment with demand response and high wind power

International Nuclear Information System (INIS)

Azizipanah-Abarghooee, Rasoul; Golestaneh, Faranak; Gooi, Hoay Beng; Lin, Jeremy; Bavafa, Farhad; Terzija, Vladimir

2016-01-01

Highlights: • Suggesting a new UC mixing a probabilistic security and incentive demand response. • Investigating the effects of uncertainty on UC using chance-constraint programming. • Proposing an efficient spinning reserve satisfaction based on a new ED correction. • Presenting a new operational cycles way to convert binary variable to discrete one. - Abstract: We propose a probabilistic unit commitment problem with incentive-based demand response and high level of wind power. Our novel formulation provides an optimal allocation of up/down spinning reserve. A more efficient unit commitment algorithm based on operational cycles is developed. A multi-period elastic residual demand economic model based on the self- and cross-price elasticities and customers’ benefit function is used. In the proposed scheme, the probability of residual demand falling within the up/down spinning reserve imposed by n − 1 security criterion is considered as a stochastic constraint. A chance-constrained method, with a new iterative economic dispatch correction, wind power curtailment, and commitment of cheaper units, is applied to guarantee that the probability of loss of load is lower than a pre-defined risk level. The developed architecture builds upon an improved Jaya algorithm to generate feasible, robust and optimal solutions corresponding to the operational cost. The proposed framework is applied to a small test system with 10 units and also to the IEEE 118-bus system to illustrate its advantages in efficient scheduling of generation in the power systems.

Indian Point Station, Unit 1 and 2. Semiannual operating report No. 24, July--December 1974

International Nuclear Information System (INIS)

1975-01-01

Net electrical power generated by Unit 1 was 519,130 MWH with the reactor critical for 2,400.39 hours and the generator on line for 2,316.14 hours. Unit 2 generated 2,427,828 MWH electrical power, was critical for 3,590.31 hours and the generator was on line for 3,485.41 hours. Operations and maintenance are summarized. Information is presented concerning radioactive effluent releases, occupational personnel radiation protection, primary coolant chemistry, changes, tests, and experiments. Environmental radioactivity is discussed. (U.S.)

Interim Action Proposed Plan for the Chemicals, Metals, and Pesticides (CMP) Pits Operable Unit; FINAL

International Nuclear Information System (INIS)

Bradley, J.

2002-01-01

The purpose of this Interim Action Proposed Plan (IAPP) is to describe the preferred interim remedial action for addressing the Chemicals, Metals, and Pesticides (CMP) Pits Operable Unit and to provide an opportunity for public input into the remedial action selection process

The new local control systems for operating gaseous diffusion plant units at Pierrelatte

International Nuclear Information System (INIS)

Delacroix, C.

1990-01-01

The development of a local control network for operating gaseous diffusion plant units is presented. The objective of the control system up date was to replace all the information network hardware. The new generation HP1000 calculators and a network architecture were chosen. The validation tests performed in laboratory and in situ, and the management policies towards the personnel during the technical changes are summarized [fr

Contaminant Attenuation and Transport Characterization of 200-DV-1 Operable Unit Sediment Samples

Energy Technology Data Exchange (ETDEWEB)

Truex, Michael J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Szecsody, James E. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Qafoku, Nikolla [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Strickland, Christopher E. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Moran, James J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Lee, Brady D. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Snyder, Michelle M.V. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Lawter, Amanda R. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Resch, Charles T. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Gartman, Brandy N. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Zhong, Lirong [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Nims, Megan K. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Saunders, Danielle L. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Williams, Benjamin D. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Horner, Jacob A. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Leavy, Ian I. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Baum, Steven R. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Christiansen, Beren B. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Clayton, Ray E. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); McElroy, Erin M. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Appriou, Delphine [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Tyrrell, Kimberly J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Striluk, Miranda L. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

2017-05-15

A laboratory study was conducted to quantify contaminant attenuation processes and associated contaminant transport parameters that are needed to evaluate transport of contaminants through the vadose zone to the groundwater. The laboratory study information, in conjunction with transport analyses, can be used as input to evaluate the feasibility of Monitored Natural Attenuation and other remedies for the 200-DV-1 Operable Unit at the Hanford Site.

Implementation and Operational Analysis of an Interactive Intensive Care Unit within a Smart Health Context.

Science.gov (United States)

Lopez-Iturri, Peio; Aguirre, Erik; Trigo, Jesús Daniel; Astrain, José Javier; Azpilicueta, Leyre; Serrano, Luis; Villadangos, Jesús; Falcone, Francisco

2018-01-29

In the context of hospital management and operation, Intensive Care Units (ICU) are one of the most challenging in terms of time responsiveness and criticality, in which adequate resource management and signal processing play a key role in overall system performance. In this work, a context aware Intensive Care Unit is implemented and analyzed to provide scalable signal acquisition capabilities, as well as to provide tracking and access control. Wireless channel analysis is performed by means of hybrid optimized 3D Ray Launching deterministic simulation to assess potential interference impact as well as to provide required coverage/capacity thresholds for employed transceivers. Wireless system operation within the ICU scenario, considering conventional transceiver operation, is feasible in terms of quality of service for the complete scenario. Extensive measurements of overall interference levels have also been carried out, enabling subsequent adequate coverage/capacity estimations, for a set of Zigbee based nodes. Real system operation has been tested, with ad-hoc designed Zigbee wireless motes, employing lightweight communication protocols to minimize energy and bandwidth usage. An ICU information gathering application and software architecture for Visitor Access Control has been implemented, providing monitoring of the Boxes external doors and the identification of visitors via a RFID system. The results enable a solution to provide ICU access control and tracking capabilities previously not exploited, providing a step forward in the implementation of a Smart Health framework.

Baseline risk assessment for the quarry residuals operable unit of the Weldon Spring Site, Weldon Spring, Missouri

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-02-01

The U.S. Department of Energy (DOE) is conducting cleanup activities at the Weldon Spring site, located in St. Charles County, Missouri, about 48 km (30 mi) west of St. Louis. Cleanup of the site consists of several integrated components. The quarry residuals operable unit (QROU), consisting of the Weldon Spring quarry and its surrounding area, is one of four operable units being evaluated. In accordance with requirements of the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA), as amended, DOE is conducting a remedial investigation/feasibility study (RI/FS) to determine the proper response to address various contaminated media that constitute the QROU. Specifically, the operable unit consists of the following areas and media: the residual material remaining at the Weldon Spring quarry after removal of the pond water and the bulk waste; groundwater underlying the quarry and surrounding area; and other media located in the surrounding vicinity of the quarry, including surface water and sediment at Femme Osage Slough, Little Femme Osage Creek, and Femme Osage Creek. An initial evaluation of conditions at the quarry area identified remaining data requirements needed to support the conceptual site exposure and hydrogeological models. These data requirements are discussed in the RI/FS work plan issued in January 1994. Soil contamination located at a property adjacent to the quarry, referred to as Vicinity Property 9 (VP9), was originally part of the scope of the QROU, as discussed in the work plan. However, a decision was subsequently made to remediate this vicinity property as part of cleanup activities for the chemical plant operable unit, as provided for in the Record of Decision (ROD). Remediation of VP9 was completed in early 1996. Hence, this baseline risk assessment (BRA) does not address VP9.

Baseline risk assessment for the quarry residuals operable unit of the Weldon Spring Site, Weldon Spring, Missouri

International Nuclear Information System (INIS)

1998-02-01

The U.S. Department of Energy (DOE) is conducting cleanup activities at the Weldon Spring site, located in St. Charles County, Missouri, about 48 km (30 mi) west of St. Louis. Cleanup of the site consists of several integrated components. The quarry residuals operable unit (QROU), consisting of the Weldon Spring quarry and its surrounding area, is one of four operable units being evaluated. In accordance with requirements of the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA), as amended, DOE is conducting a remedial investigation/feasibility study (RI/FS) to determine the proper response to address various contaminated media that constitute the QROU. Specifically, the operable unit consists of the following areas and media: the residual material remaining at the Weldon Spring quarry after removal of the pond water and the bulk waste; groundwater underlying the quarry and surrounding area; and other media located in the surrounding vicinity of the quarry, including surface water and sediment at Femme Osage Slough, Little Femme Osage Creek, and Femme Osage Creek. An initial evaluation of conditions at the quarry area identified remaining data requirements needed to support the conceptual site exposure and hydrogeological models. These data requirements are discussed in the RI/FS work plan issued in January 1994. Soil contamination located at a property adjacent to the quarry, referred to as Vicinity Property 9 (VP9), was originally part of the scope of the QROU, as discussed in the work plan. However, a decision was subsequently made to remediate this vicinity property as part of cleanup activities for the chemical plant operable unit, as provided for in the Record of Decision (ROD). Remediation of VP9 was completed in early 1996. Hence, this baseline risk assessment (BRA) does not address VP9

Current Conditions Risk Assessment for the 300-FF-5 Groundwater Operable Unit

Energy Technology Data Exchange (ETDEWEB)

Miley, Terri B.; Bunn, Amoret L.; Napier, Bruce A.; Peterson, Robert E.; Becker, James M.

2007-11-01

This report updates a baseline risk assessment for the 300 Area prepared in 1994. The update includes consideration of changes in contaminants of interest and in the environment that have occurred during the period of interim remedial action, i.e., 1996 to the present, as well as the sub-regions, for which no initial risk assessments have been conducted. In 1996, a record of decision (ROD) stipulated interim remedial action for groundwater affected by releases from 300 Area sources, as follows: (a) continued monitoring of groundwater that is contaminated above health-based levels to ensure that concentrations continue to decrease, and (b) institutional controls to ensure that groundwater use is restricted to prevent unacceptable exposure to groundwater contamination. In 2000, the groundwater beneath the two outlying sub-regions was added to the operable unit. In 2001, the first 5-year review of the ROD found that the interim remedy and remedial action objectives were still appropriate, although the review called for additional characterization activities. This report includes a current conditions baseline ecological and human health risk assessment using maximum concentrations in the environmental media of the 300-FF-5 Operable Unit and downstream conditions at the City of Richland, Washington. The scope for this assessment includes only current measured environmental concentrations and current use scenarios. Future environmental concentrations and future land uses are not considered in this assessment.

RISK-INFORMED SAFETY MARGIN CHARACTERIZATION

International Nuclear Information System (INIS)

Dinh, Nam; Szilard, Ronaldo

2009-01-01

The concept of safety margins has served as a fundamental principle in the design and operation of commercial nuclear power plants (NPPs). Defined as the minimum distance between a system's 'loading' and its 'capacity', plant design and operation is predicated on ensuring an adequate safety margin for safety-significant parameters (e.g., fuel cladding temperature, containment pressure, etc.) is provided over the spectrum of anticipated plant operating, transient and accident conditions. To meet the anticipated challenges associated with extending the operational lifetimes of the current fleet of operating NPPs, the United States Department of Energy (USDOE), the Idaho National Laboratory (INL) and the Electric Power Research Institute (EPRI) have developed a collaboration to conduct coordinated research to identify and address the technological challenges and opportunities that likely would affect the safe and economic operation of the existing NPP fleet over the postulated long-term time horizons. In this paper we describe a framework for developing and implementing a Risk-Informed Safety Margin Characterization (RISMC) approach to evaluate and manage changes in plant safety margins over long time horizons

Lake Whitney Comprehensive Water Quality Assessment, Phase 1B- Physical and Biological Assessment (USDOE)

Energy Technology Data Exchange (ETDEWEB)

Doyle, Robert D; Byars, Bruce W

2009-11-24

assessment of knowledge of watershed and water quality related issues by local residents and stakeholders of Lake Whitney and design an intervention educational program to address any deficiencies discovered. Phase IA was funded primarily from EPA Cooperative Agreement X7-9769 8901-0. Phase IC (USEPA, QAPP Study Element 5) of this research focused on the ambient toxicity of the reservoir with respect to periodic blooms of golden algae. Phase IC was funded primarily from Cooperative Agreement EM-96638001. Phase 1B (USDOE, Study Elements 6-11) complemented work being done via EPA funding on study elements 1-5 and added five new study elements: 6) Salinity Transport in the Brazos Watershed to Lake Whitney; 7) Bacterial Assessment; 8) Organic Contaminant Analysis on Lake Whitney; 9) Plankton Photosynthesis; 10) Lake Whitney Resident Knowledge Assessment; and 11) Engineering Scoping Perspective: Recommendations for Use.

Symptoms of Psychological Distress and Post-Traumatic Stress Disorder in United States Air Force Drone Operators

Science.gov (United States)

2014-08-01

Disorder in United States Air Force “ Drone ” Operators 5a. CONTRACT NUMBER 5b. GRANT NUMBER 5c. PROGRAM ELEMENT NUMBER 6. AUTHOR(S...referred to as “ drones .” Participants were assessed for self-reported sources of occupational stress, levels of clinical distress using the Outcome...providers are discussed. 15. SUBJECT TERMS Stress, drone operator, PTSD, USAF 16. SECURITY CLASSIFICATION OF: 17. LIMITATION OF ABSTRACT

Operable Unit 3: Proposed Plan/Environmental Assessment for interim remedial action

International Nuclear Information System (INIS)

1993-12-01

This document presents a Proposed Plan and an Environmental Assessment for an interim remedial action to be undertaken by the US Department of Energy (DOE) within Operable Unit 3 (OU3) at the Fernald Environmental Management Project (FEMP). This proposed plan provides site background information, describes the remedial alternatives being considered, presents a comparative evaluation of the alternatives and a rationnale for the identification of DOE's preferred alternative, evaluates the potential environmental and public health effects associated with the alternatives, and outlines the public's role in helping DOE and the EPA to make the final decision on a remedy

Hanford Site Waste management units report

International Nuclear Information System (INIS)

1992-01-01

This report summarizes the operable units in several areas of the Hanford Site Waste Facility. Each operable unit has several waste units (crib, ditch, pond, etc.). The operable units are summarized by describing each was unit. Some of the descriptions are unit name, unit type, waste category start data, site description, etc. The descriptions will vary for each waste unit in each operable unit and area of the Hanford Site

Site-specific waste management instruction for the 100-KR-4 Operable Unit drilling

International Nuclear Information System (INIS)

Hadley, J.T.

1996-07-01

This site-specific waste management instruction provides guidance for the management of waste generated as a result of groundwater well installations in the 100-KR-4 Operable Unit (OU). The well installations are necessary to implement the Remedial Action (RA) option (pump-and-treat using ion exchange) to prevent discharge of hexavalent chromium at levels above those considered protective of aquatic life in the Columbia River and riverbed sediments

The nuclear industry's transition to risk-informed regulation and operation in the United States

International Nuclear Information System (INIS)

Kadak, Andrew C.; Matsuo, Toshihiro

2007-01-01

This paper summarizes a study of the transition of the United States nuclear industry from a prescriptive regulatory structure to a more risk informed approach to operations and regulations. The transition occurred over a 20 yr period in which gradual changes were made in the fundamental regulations and to the approach to nuclear safety and operations. While the number of actual regulatory changes were few, they are continuing. The utilities that embraced risk informed operations made dramatic changes in the way they approached operations and outage management. Those utilities that used risk in operations showed dramatic improvement in safety based on Institute of Nuclear Power Operations (INPO) performance indicators. It was also shown that the use of risk did not negatively affect safety performance of the plants compared to standard prescriptive approaches. This was despite having greater flexibility in compliance to regulatory standards and the use of the newly instituted risk-informed reactor oversight process. Key factors affecting the successful transition to a more risk-informed approach to regulations and operations are: strong top management support and leadership both at the regulator and the utility; education and training in risk principles and probabilistic risk Assessment tools for engineers, operators and maintenance staff; a slow and steady introduction of risk initiatives in areas that can show value to both the regulator and the industry; a transparent regulatory foundation built around a safety goal policy and the development of a strong safety culture at the utility to allow for more independence in safety compliance and risk management. The experience of the United States shows positive results in both safety and economics. The INPO and NRC metrics presented show that the use of risk information in operations and regulation is marginally better with no degradation in safety when plants that have embraced risk-informed approaches are compared

On an Integral-Type Operator Acting between Bloch-Type Spaces on the Unit Ball

Directory of Open Access Journals (Sweden)

Stevo Stević

2010-01-01

Full Text Available Let 𝔹 denote the open unit ball of ℂn. For a holomorphic self-map φ of 𝔹 and a holomorphic function g in 𝔹 with g(0=0, we define the following integral-type operator: Iφgf(z=∫01ℜf(φ(tzg(tz(dt/t, z∈𝔹. Here ℜf denotes the radial derivative of a holomorphic function f in 𝔹. We study the boundedness and compactness of the operator between Bloch-type spaces ℬω and ℬμ, where ω is a normal weight function and μ is a weight function. Also we consider the operator between the little Bloch-type spaces ℬω,0 and ℬμ,0.

Influence of unit operations on the levels of polyacetylenes in minimally processed carrots and parsnips: An industrial trial.

Science.gov (United States)

Koidis, Anastasios; Rawson, Ashish; Tuohy, Maria; Brunton, Nigel

2012-06-01

Carrots and parsnips are often consumed as minimally processed ready-to-eat convenient foods and contain in minor quantities, bioactive aliphatic C17-polyacetylenes (falcarinol, falcarindiol, falcarindiol-3-acetate). Their retention during minimal processing in an industrial trial was evaluated. Carrot and parsnips were prepared in four different forms (disc cutting, baton cutting, cubing and shredding) and samples were taken in every point of their processing line. The unit operations were: peeling, cutting and washing with chlorinated water and also retention during 7days storage was evaluated. The results showed that the initial unit operations (mainly peeling) influence the polyacetylene retention. This was attributed to the high polyacetylene content of their peels. In most cases, when washing was performed after cutting, less retention was observed possibly due to leakage during tissue damage occurred in the cutting step. The relatively high retention during storage indicates high plant matrix stability. Comparing the behaviour of polyacetylenes in the two vegetables during storage, the results showed that they were slightly more retained in parsnips than in carrots. Unit operations and especially abrasive peeling might need further optimisation to make them gentler and minimise bioactive losses. Copyright © 2011 Elsevier Ltd. All rights reserved.

Development, implementation and operational experience with 900 mm R1T pocket-type bearings at Oskarshamn unit 3 nuclear steam turbine generator

International Nuclear Information System (INIS)

Peel, P.; Roos, A.

2015-01-01

The Oskarshamn unit 3 nuclear steam turbine generator in Sweden is operated by OKG and, following the extensive PULS upgrade project, delivers an increased rated output of 1450 MW making it the most powerful BWR unit worldwide. Several turbine bearing incidents occurred in 2009 and 2010, which initiated a detailed root cause analysis to determine the reasons and propose appropriate mitigation measures to ensure reliable unit operation. Together with OKG, ALSTOM Power implemented a short-term solution to operate the unit over the winter period of 2010-11. Subsequently, during the annual outage in June 2011, a permanent solution involving a R1T pocket-type bearing design was installed at three shaft-line positions. Since the 1980's, R1T bearings with diameters from 250 to 670 mm have been operating in numerous full-speed (3000/3600 rpm) steam turbine generators. However, this was the first application of a R1T bearing developed at a diameter of 900 mm and for half-speed operation. This paper presents an overview of the bearing development and details the successful operational feedback gathered to date on the three installed bearings. In comparison with the three tilting pad bearing design, which has typically been used on large half-speed ALSTOM Power steam turbine generators to date, it confirms the R1T bearing design as a viable alternative. (authors)

Explicit isospectral flows associated to the AKNS operator on the unit interval. II

Science.gov (United States)

Amour, Laurent

2012-10-01

Explicit flows associated to any tangent vector fields on any isospectral manifold for the AKNS operator acting in L2 × L2 on the unit interval are written down. The manifolds are of infinite dimension (and infinite codimension). The flows are called isospectral and also are Hamiltonian flows. It is proven that they may be explicitly expressed in terms of regularized determinants of infinite matrix-valued functions with entries depending only on the spectral data at the starting point of the flow. The tangent vector fields are decomposed as ∑ξkTk where ξ ∈ ℓ2 and the Tk ∈ L2 × L2 form a particular basis of the tangent vector spaces of the infinite dimensional manifold. The paper here is a continuation of Amour ["Explicit isospectral flows for the AKNS operator on the unit interval," Inverse Probl. 25, 095008 (2009)], 10.1088/0266-5611/25/9/095008 where, except for a finite number, all the components of the sequence ξ are zero in order to obtain an explicit expression for the isospectral flows. The regularized determinants induce counter-terms allowing for the consideration of finite quantities when the sequences ξ run all over ℓ2.

200-ZP-1 operable unit borehole summary report for FY 1995 and FY 1996

International Nuclear Information System (INIS)

Darrach, M.E.

1996-10-01

This document details the well construction, sampling, analyses, and geologic character of the Ringold Formation fluvial unit E gravels as encountered in 16 boreholes in the 200-ZP-1 Operable Unit. These boreholes were drilled by Water Development Hanford Corporation during fiscal years 1995 and 1996. Two of the sixteen boreholes were abandoned; the remaining 14 boreholes were completed as functioning production and compliance wells. The borehole logs and well summary sheets included as Appendices A and B of this document, respectively, depict and describe the vadose zone stratigraphic units encountered during the course of drilling. Appendix C contains the results of sieve analyses conducted on samples obtained via resonant sonic coring and standard split-spoon methods. The sieve analyses were the driver behind the majority of the well designs. Also, for completeness, Appendices D and E contain the well design calculations and the well development process

Implementation and Operational Analysis of an Interactive Intensive Care Unit within a Smart Health Context

Science.gov (United States)

Aguirre, Erik

2018-01-01

In the context of hospital management and operation, Intensive Care Units (ICU) are one of the most challenging in terms of time responsiveness and criticality, in which adequate resource management and signal processing play a key role in overall system performance. In this work, a context aware Intensive Care Unit is implemented and analyzed to provide scalable signal acquisition capabilities, as well as to provide tracking and access control. Wireless channel analysis is performed by means of hybrid optimized 3D Ray Launching deterministic simulation to assess potential interference impact as well as to provide required coverage/capacity thresholds for employed transceivers. Wireless system operation within the ICU scenario, considering conventional transceiver operation, is feasible in terms of quality of service for the complete scenario. Extensive measurements of overall interference levels have also been carried out, enabling subsequent adequate coverage/capacity estimations, for a set of Zigbee based nodes. Real system operation has been tested, with ad-hoc designed Zigbee wireless motes, employing lightweight communication protocols to minimize energy and bandwidth usage. An ICU information gathering application and software architecture for Visitor Access Control has been implemented, providing monitoring of the Boxes external doors and the identification of visitors via a RFID system. The results enable a solution to provide ICU access control and tracking capabilities previously not exploited, providing a step forward in the implementation of a Smart Health framework. PMID:29382148

Implementation and Operational Analysis of an Interactive Intensive Care Unit within a Smart Health Context

Directory of Open Access Journals (Sweden)

Peio Lopez-Iturri

2018-01-01

Full Text Available In the context of hospital management and operation, Intensive Care Units (ICU are one of the most challenging in terms of time responsiveness and criticality, in which adequate resource management and signal processing play a key role in overall system performance. In this work, a context aware Intensive Care Unit is implemented and analyzed to provide scalable signal acquisition capabilities, as well as to provide tracking and access control. Wireless channel analysis is performed by means of hybrid optimized 3D Ray Launching deterministic simulation to assess potential interference impact as well as to provide required coverage/capacity thresholds for employed transceivers. Wireless system operation within the ICU scenario, considering conventional transceiver operation, is feasible in terms of quality of service for the complete scenario. Extensive measurements of overall interference levels have also been carried out, enabling subsequent adequate coverage/capacity estimations, for a set of Zigbee based nodes. Real system operation has been tested, with ad-hoc designed Zigbee wireless motes, employing lightweight communication protocols to minimize energy and bandwidth usage. An ICU information gathering application and software architecture for Visitor Access Control has been implemented, providing monitoring of the Boxes external doors and the identification of visitors via a RFID system. The results enable a solution to provide ICU access control and tracking capabilities previously not exploited, providing a step forward in the implementation of a Smart Health framework.

An analysis of post-traumatic stress symptoms in United States Air Force drone operators.

Science.gov (United States)

Chappelle, Wayne; Goodman, Tanya; Reardon, Laura; Thompson, William

2014-06-01

Remotely piloted aircraft (RPA), commonly referred to as "drones," have emerged over the past decade as an innovative warfighting tool. Given there is a paucity of empirical research assessing drone operators, the purpose of this study was to assess for the prevalence of PTSD symptoms among this cohort. Of the 1084 United States Air Force (USAF) drone operators that participated, a total of 4.3% endorsed a pattern of symptoms of moderate to extreme level of severity meeting criteria outlined in the Diagnostic and Statistical Manual of Mental Disorders-4th edition. The incidence of PTSD among USAF drone operators in this study was lower than rates of PTSD (10-18%) among military personnel returning from deployment but higher than incidence rates (less than 1%) of USAF drone operators reported in electronic medical records. Although low PTSD rates may be promising, limitations to this study are discussed. Copyright © 2014 Elsevier Ltd. All rights reserved.

Operation of Beaver Valley Power Station, Unit 2, Docket No. 50-412, Beaver County, Pennsylvania

International Nuclear Information System (INIS)

1985-09-01

The final environmental impact statement (EPA No. 850438F) assesses the effects of operating a pressurized water reactor in Pennsylvania on the south bank of the Ohio River, which would serve as the final heat sink for the cooling system. Operation of Unit 2 would add 836 MW of capacity and increase system reliability. The plant would employ 465 at an $18 million payroll. Facilities for the plant would take up 56 acres of agricultural land. The operation result in both water and noise pollution. There is only a small probability of impacts due to potential radiation exposure. The Federal Water Pollution Control Act of 1972 and Nuclear Regulatory Commission Regulations require the impact statement

The Evolving Contingency Contracting Market: Private Sector Self regulation and United States Government Monitoring of Procurement of Stability Operations Services

Science.gov (United States)

2016-01-01

statements of work would be useful in ensuring ethical govern- ment procurement practices. Conclusions The United States conducts diplomatic, defense...THE EVOLVING CONTINGENCY CONTRACTING MARKET: PRIVATE SECTOR SELF-REGULATION AND UNITED STATES GOVERNMENT MONITORING OF PROCUREMENT OF STABILITY...MARKET: PRIVATE SECTOR SELF-REGULATION AND UNITED STATES GOVERNMENT MONITORING OF PROCUREMENT OF STABILITY OPERATIONS SERVICES Whitney Grespin January

State heating oil and propane program. Final report, 1993--1994

International Nuclear Information System (INIS)

Rizzolo, D.R.

1997-01-01

In cooperation with the United States Department of Energy (USDOE), Energy Information Administration (EIA), the New Jersey Department of Environmental Protection and Energy (DEPE), Office of Energy participated in an ongoing program to monitor retail prices of no. 2 heating oil and propane in New Jersey. According to program instructions, we conducted twelve price surveys on a semi-monthly basis to obtain the necessary information from retail fuel merchants and propane dealers identified by the EIA. According to program instructions and at the discretion of the USDOE, we conducted three additional propane surveys on January 31 and February 14 and 28, 1994. The surveys began on October 4, 1993 and ended on March 21, 1994. We submitted data collected as of specified report dates to the EIA, within two working days of those dates

Data validation report for the 100-KR-4 operable unit first quarter, 1994

International Nuclear Information System (INIS)

Krug, A.D.

1994-01-01

Samples were obtained from the 100-KR-4 Operable Unit first Quarter 1994 Groundwater Sampling event. The data from the chemical analysis of fifty-eight samples from this sampling event and their related quality assurance samples were reviewed and validated to verify that reported samples results were of sufficient quality to support decisions regarding remedial actions performed at this site. Information fro the sampling event and the information validation processes are presented in this document

Sampling and Analysis Plan Update for Groundwater Monitoring 1100-EM-1 Operable Unit

International Nuclear Information System (INIS)

DR Newcomer

1999-01-01

This document updates the sampling and analysis plan (Department of Energy/Richland Operations--95-50) to reflect current groundwater monitoring at the 1100-EM-1Operable Unit. Items requiring updating included sampling and analysis protocol, quality assurance and quality control, groundwater level measurement procedure, and data management. The plan covers groundwater monitoring, as specified in the 1993 Record of Decision, during the 5-year review period from 1995 through 1999. Following the 5-year review period, groundwater-monitoring data will be reviewed by Environmental Protection Agency to evaluate the progress of natural attenuation of trichloroethylene. Monitored natural attenuation and institutional controls for groundwater use at the inactive Horn Rapids Landfill was the selected remedy specified in the Record of Decision

40 CFR Table 9 to Subpart Uuu of... - Operating Limits for Organic HAP Emissions From Catalytic Cracking Units

Science.gov (United States)

2010-07-01

... 40 Protection of Environment 12 2010-07-01 2010-07-01 true Operating Limits for Organic HAP Emissions From Catalytic Cracking Units 9 Table 9 to Subpart UUU of Part 63 Protection of Environment..., Subpt. UUU, Table 9 Table 9 to Subpart UUU of Part 63—Operating Limits for Organic HAP Emissions From...

40 CFR Table 16 to Subpart Uuu of... - Operating Limits for Organic HAP Emissions From Catalytic Reforming Units

Science.gov (United States)

2010-07-01

... 40 Protection of Environment 12 2010-07-01 2010-07-01 true Operating Limits for Organic HAP Emissions From Catalytic Reforming Units 16 Table 16 to Subpart UUU of Part 63 Protection of Environment..., Subpt. UUU, Table 16 Table 16 to Subpart UUU of Part 63—Operating Limits for Organic HAP Emissions From...

Combined operation of AC and DC distribution system with distributed generation units

International Nuclear Information System (INIS)

Noroozian, R.; Abedi, M.; Gharehpetian, G.

2010-01-01

This paper presents a DC distribution system which has been supplied by external AC systems as well as local DG units in order to demonstrate an overall solution to power quality issue. In this paper, the proposed operation method is demonstrated by simulation of power transfer between external AC systems, DG units, AC and DC loads. The power flow control in DC distribution system has been achieved by network converters and DG converters. Also, the mathematical model of the network, DG and load converters are obtained by using the average technique, which allows converter systems accurately simulated and control strategies for this converters is achieved. A suitable control strategy for network converters has been proposed that involves DC voltage droop regulator and novel instantaneous power regulation scheme. Also, a novel control technique has been proposed for DG converters. In this paper, a novel control system based on stationary and synchronously rotating reference frame has been proposed for load converters for supplying AC loads connected to the DC bus by balanced voltages. The several case studies have been studied based on proposed methods. The simulation results show that DC distribution systems including DG units can improve the power quality at the point of common coupling (PCC) in the power distribution system or industrial power system. (authors)

A research on threat (hazard) categorization method for nuclear facilities

International Nuclear Information System (INIS)

Tang Rongyao; Xu Xiaoxiao; Zhang Jiangang; Zhao Bin; Wang Xuexin

2011-01-01

The threat categorization method suggested by International Atomic Energy Agency (IAEA) and hazard categorization standard by the Department of Energy of United States (USDOE) for nuclear facilities are compared and discussed in this paper. The research shows the two types of categorization method for nuclear facilities are similar, though each has its own specialty. The categorization method suggested by IAEA for the purpose of emergency planning is quite completed and updated. The categorization method of DOE is advanced in its operability, and fits for safety surveillance. But the dispersible radioactive material thresholds used for categorization need to be updated. The threshold of category 3 is somewhat disputable for many reasons. The recommended categorization method for China is also given in this paper. (author)

78 FR 37584 - U.S. Steel Tubular Products, Inc., Mckeesport Tubular Operations Division, Subsidiary of United...

Science.gov (United States)

2013-06-21

... make the following certification: All workers of U.S. Steel Tubular Products, McKeesport Tubular... Products, Inc., Mckeesport Tubular Operations Division, Subsidiary of United States Steel Corporation, Mckeesport, Pennsylvania; Notice of Amended Certification Pursuant to Section 221 of the Trade Act of 1974...

Safety Evaluation Report related to the operation of LaSalle County Station, Units 1 and 2. Docket Nos. 50-373 and 50-374

International Nuclear Information System (INIS)

1984-03-01

This supplement to the Safety Evaluation Report of Commonwealth Edison Company's application for a license to operate its La Salle County Station, Unit 2, located in Brookfield Township, La Salle County, Illinois, has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. This supplement is to update evaluations on Unit 2 issues identified in the previous Safety Evaluation Report and Supplements that need resolution prior to issuance of the full power operating license for Unit 2

Black Fox Station, Units 1 and 2. Application for construction permits and operating licenses

International Nuclear Information System (INIS)

1975-01-01

An application to construct and operate Black Fox Station, Units 1 and 2, is presented. The two BWR type reactors will have a rated core thermal power of 3579 MW(t) and a net electrical power of approximately 1150 MW(e). The facility will be located in Inola Township, 23 miles east of Tulsa on the east side of the Verdigris River in Rogers County, Oklahoma

Storm water control plan for the Lower East Fork Poplar Creek Operable Unit, Oak Ridge, Tennessee

International Nuclear Information System (INIS)

1996-04-01

This document provides the Environmental Restoration Program with information about the erosion and sediment control, storm water management, maintenance, and reporting and record keeping practices to be employed during Phase II of the remediation project for the Lower East Fork Poplar Creek (LEFPC) Operable Unit

Description of the U.S. Geological Survey's water-quality sampling and water-level monitoring program at the Hallam Nuclear Facility, June through September 1996

International Nuclear Information System (INIS)

1997-01-01

A water-quality and water-level program of the US Department of Energy (USDOE) in cooperation with the US Geological Survey (USGS) was re-established in June 1996 to develop six new USDOE observation wells, collect one set of water-quality samples from 17 of the 19 USDOE observation wells, and take monthly water-level measurements for a 3-month period in all 19 USDOE observation wells at the Hallam Nuclear Facility, Hallam, Nebraska. Thirteen of the observation wells were installed by HWS Consulting Group, Inc., in June 1993 and the remaining six were installed by Applied Research Associates in August 1995

Operation of Browns Ferry, Units 1 and 2 following the March 22, 1975 fire. Safety evaluation report

International Nuclear Information System (INIS)

1976-03-01

The Safety Evaluation Report issued February 23, 1976, presents the NRC evaluation regarding the acceptability of the restoration and modifications at the Browns Ferry Plant Units 1 and 2, following the March 22, 1975 fire, to establish that the facility may be operated in the restored and modified condition without endangering the health and safety of the public. The modifications involved enhancing separation of redundant safeguards equipment by some rerouting of cable and by the application of a fire-retardant coating to the cable; enhancing fire extinguishing capability by the addition of fixed spray and sprinkler systems and expanded smoke and heat detection systems; and enhancing the overall fire protection program by changes in procedures, training, and organization. The NRC staff indicated some items that remained to be resolved prior to operation and concluded that subject to their satisfactory resolution the restoration of Browns Ferry Nuclear Plants Units 1 and 2 including the modifications is acceptable and that there is reasonable assurance that the health and safety of the public will not be endangered by operation of the facility as restored and modified

Safety-evaluation report related to operation of McGuire Nuclear Station, Units 1 and 2. Docket Nos. 50-369 and 50-370

International Nuclear Information System (INIS)

1983-05-01

This report supplements the Safety Evaluation Report Related to the Operation of McGuire Nuclear Station, Units 1 and 2 (SER (NUREG-0422)) issued in March 1978 by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission with respect to the application filed by Duke Power Company, as applicant and owner, for licenses to operate the McGuire Nuclear Station, Units 1 and 2 (Docket Nos. 50-369 and 50-370). The facility is located in Mecklenburg County, North Carolina, about 17 mi north-northwest of Charlotte, North Carolina. This supplement provides information related to issuance of a full-power authorization for Unit 2. The staff concludes that the McGuire Nuclear Station can be operated by the licensee without endangering the health and safety of the public

Superfund record of decision (EPA Region 3), Westinghouse Elevator Company Plant, Operable Unit 2, Cumberland Township, Adams County, Gettysburg, PA, March 31, 1995

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-04-01

This Record of Decision (ROD) presents the selected remedial action for Operable Unit 2 (Soils) at the Westinghouse Elevator Company Plant Site in Adams County, Pennsylvania. The selected remedy for the soils at the Westinghouse Elevator Plant is No Additional Action for this Operable Unit. The other alternatives evaluated would produce little or no environmental benefit at substantial cost.

Multiobjective Optimization of a Counterrotating Type Pump-Turbine Unit Operated at Turbine Mode

Directory of Open Access Journals (Sweden)

Jin-Hyuk Kim

2014-05-01

Full Text Available A multiobjective optimization for improving the turbine output and efficiency of a counterrotating type pump-turbine unit operated at turbine mode was carried out in this work. The blade geometry of both the runners was optimized using a hybrid multiobjective evolutionary algorithm coupled with a surrogate model. Three-dimensional Reynolds-averaged Navier-Stokes equations with the shear stress transport turbulence model were discretized by finite volume approximations and solved on hexahedral grids to analyze the flow in the pump-turbine unit. As major hydrodynamic performance parameters, the turbine output and efficiency were selected as objective functions with two design variables related to the hub profiles of both the runner blades. These objectives were numerically assessed at twelve design points selected by Latin hypercube sampling in the design space. Response surface approximation models for the objectives were constructed based on the objective function values at the design points. A fast nondominated sorting genetic algorithm for the local search coupled with the response surface approximation models was applied to determine the global Pareto-optimal solutions. The trade-off between the two objectives was determined and described with respect to the Pareto-optimal solutions. The results of this work showed that the turbine outputs and efficiencies of optimized pump-turbine units were simultaneously improved in comparison to the reference unit.

A Formula for the Units to Satisfy an Operation's Desired Rate of Return in CVP Analysis--A Conceptual Approach

Science.gov (United States)

Anderson, Johann A.; Leese, Wallace R.

2016-01-01

A common formula presented in many managerial- and cost-accounting textbooks makes possible the determination of the quantity of units which must be produced and sold to generate a desired dollar-amount of operating income. This article addresses the question "What formula can be used to determine the quantity of units needed to yield a…

Licensed operating reactors

International Nuclear Information System (INIS)

1990-01-01

The US Nuclear Regulatory Commission's monthly LICENSED OPERATING REACTORS Status Summary Report provides data on the operation of nuclear units as timely and accurately as possible. This information is collected by the Office of Information Resources Management, from the Headquarters Staff of NRC's Office of Inspection and Enforcement, from NRC's Regional Offices, and from utilities. Since all of the data concerning operation of the units is provided by the utility operators less than two weeks after the end of the month, necessary corrections to published information are shown on the ERRATA page. This report is divided into three sections: the first contains monthly highlights and statistics for commercial operating units, and errata from previously reported data; the second is a compilation of detailed information on each unit, provided by NRC Regional Offices, IE Headquarters and the Utilities; and the third section is an appendix for miscellaneous information such as spent fuel storage capability, reactor years of experience and non-power reactors in the United States

Licensed operating reactors

International Nuclear Information System (INIS)

1989-06-01

The US Nuclear Regulatory Commission's monthly LICENSED OPERATING REACTORS Status Summary Report provides data on the operation of nuclear units as timely and accurately as possible. This information is collected by the Office of Information Resources Management, from the Headquarters Staff of NRC's Office of Inspection and Enforcement, from NRC's Regional Offices, and from utilities. Since all of the data concerning operation of the units are provided by the utility operators less than two weeks after the end of the month, necessary corrections to published information are shown on the ERRATA page. This report is divided into three sections: the first contains monthly highlights and statistics for commercial operating units, and errata from previously reported data; the second is a compilation of detailed information on each unit, provided by NRC Regional Offices, IE Headquarters and the Utilities; and the third section is an appendix for miscellaneous information such as spent fuel storage capability, reactor years of experience and non-power reactors in the United States

The Building Blocks for JWST I and T (Integrations and Test) to Operations - From Simulator to Flight Units

Science.gov (United States)

Fatig, Curtis; Ochs, William; Johns, Alan; Seaton, Bonita; Adams, Cynthia; Wasiak, Francis; Jones, Ronald; Jackson, Wallace

2012-01-01

The James Webb Space Telescope (JWST) Project has an extended integration and test (I&T) phase due to long procurement and development times of various components as well as recent launch delays. The JWST Ground Segment and Operations group has developed a roadmap of the various ground and flight elements and their use in the various JWST I&T test programs. The JWST Project s building block approach to the eventual operational systems, while not new, is complex and challenging; a large-scale mission like JWST involves international partners, many vendors across the United States, and competing needs for the same systems. One of the challenges is resource balancing so simulators and flight products for various elements congeal into integrated systems used for I&T and flight operations activities. This building block approach to an incremental buildup provides for early problem identification with simulators and exercises the flight operations systems, products, and interfaces during the JWST I&T test programs. The JWST Project has completed some early I&T with the simulators, engineering models and some components of the operational ground system. The JWST Project is testing the various flight units as they are delivered and will continue to do so for the entire flight and operational system. The JWST Project has already and will continue to reap the value of the building block approach on the road to launch and flight operations.

FEASIBILITY STUDY REPORT FOR THE 200-ZP-1 GROUNDWATER OPERABLE UNIT

Energy Technology Data Exchange (ETDEWEB)

BYRNES ME

2008-07-18

The Hanford Site, managed by the U.S. Department of Energy (DOE), encompasses approximately 1,517 km{sup 2} (586 mi{sup 2}) in the Columbia Basin of south-central Washington State. In 1989, the U.S. Environmental Protection Agency (EPA) placed the 100, 200, 300, and 1100 Areas of the Hanford Site on the 40 Code of Federal Regulations (CFR) 300, 'National Oil and Hazardous Substances Pollution Contingency Plan' National Contingency Plan [NCPD], Appendix B, 'National Priorities List' (NPL), pursuant to the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA). The 200 Areas NPL sites consist of the 200 West and 200 East Areas (Figure 1-1). The 200 Areas contain waste management facilities, inactive irradiated fuel reprocessing facilities, and the 200 North Area (formerly used for interim storage and staging of irradiated fuel). Several waste sites in the 600 Area, located near the 200 Areas, also are included in the 200 Areas NPL site. The 200 Areas NPL site is in a region referred to as the 'Central Plateau' and consists of approximately 700 waste sites, excluding sites assigned to the tank farm waste management areas (WMAs). The 200-ZP-1 Groundwater Operable Unit (OU) consists of the groundwater located under the northern portion of the 200 West Area. Waste sources that contributed to the 200-ZP-1 OU included cribs and trenches that received liquid and/or solid waste in the past from the Z Plant and T Plant aggregate areas, WMA-T, WMA-TX/TY, and the State-Approved Land Disposal Site (SALDS). This feasibility study (FS) for the 200-ZP-1 Groundwater OU was prepared in accordance with the requirements of CERCLA decision documents. These decision documents are part of the Administrative Record for the selection of remedial actions for each waste site and present the selected remedial actions that are chosen in accordance with CERCLA, as amended by the Superfund Amendments and Reauthorization Act of 1986

IMBA expert(r): Internal dosimetry made simple

International Nuclear Information System (INIS)

Birchall, A.; Puncher, M.; James, A.C.; Marsh, J.W.; Jarvis, N.S.; Peace, M.S.; Davis, K.; King, D.J.

2003-01-01

In 1997, a collaboration between British Nuclear Fuels plc (BNFL), Westlakes Research Institute and NRPB started, with the aim of producing IMBA (Integrated Modules for Bioassay Analysis), a suite of software modules that implement the new ICRP models for estimation of intakes and doses. This was partly in response to new UK regulations, and partly due to the requirement for a unified approach in estimating intakes and doses from bioassay measurements within the UK. Over the past 5 years, the IMBA modules have been developed further, have gone through extensive quality assurance, and are now used for routine dose assessment by approved dosimetry services throughout the UK. More recently, interest in the IMBA methodology has been shown by the United States Department of Energy (USDOE), and in 2001 an ambitious project to develop a software package (IMBA Expert TM USDOE Edition) which would meet the requirements of all of the major USDOE sites began. Interest in IMBA Expert is now being expressed in many other countries. The aim of this paper is to outline the origin and evolution of the IMBA modules (the past); to describe the full capabilities of the current IMBA Expert system (the present) and to indicate possible future directions in terms of capabilities and availability (the future). (author)

IMBA expert(r): Internal dosimetry made simple

Energy Technology Data Exchange (ETDEWEB)

Birchall, A.; Puncher, M.; James, A.C.; Marsh, J.W.; Jarvis, N.S.; Peace, M.S.; Davis, K.; King, D.J

2003-07-01

In 1997, a collaboration between British Nuclear Fuels plc (BNFL), Westlakes Research Institute and NRPB started, with the aim of producing IMBA (Integrated Modules for Bioassay Analysis), a suite of software modules that implement the new ICRP models for estimation of intakes and doses. This was partly in response to new UK regulations, and partly due to the requirement for a unified approach in estimating intakes and doses from bioassay measurements within the UK. Over the past 5 years, the IMBA modules have been developed further, have gone through extensive quality assurance, and are now used for routine dose assessment by approved dosimetry services throughout the UK. More recently, interest in the IMBA methodology has been shown by the United States Department of Energy (USDOE), and in 2001 an ambitious project to develop a software package (IMBA Expert{sup TM} USDOE Edition) which would meet the requirements of all of the major USDOE sites began. Interest in IMBA Expert is now being expressed in many other countries. The aim of this paper is to outline the origin and evolution of the IMBA modules (the past); to describe the full capabilities of the current IMBA Expert system (the present) and to indicate possible future directions in terms of capabilities and availability (the future). (author)

Licensed operating reactors

International Nuclear Information System (INIS)

1989-08-01

THE OPERATING UNITS STATUS REPORT - LICENSED OPERATING REACTORS provides data on the operation of nuclear units as timely and accurately as possible. This information is collected by the Office of Information Resources Management from the Headquarters staff of NRC's Office of Enforcement (OE), from NRC's Regional Offices, and from utilities. The three sections of the report are: monthly highlights and statistics for commercial operating units, and errata from previously reported data; a compilation of detailed information on each unit, provided by NRC's Regional Offices, OE Headquarters and the utilities; and an appendix for miscellaneous information such as spent fuel storage capability, reactor-years of experience and non-power reactors in the US

Licensed operating reactors

International Nuclear Information System (INIS)

1990-04-01

The Operating Units Status Report --- Licensed Operating Reactors provides data on the operation of nuclear units as timely and accurately as possible. This information is collected by the Office of Information Resources Management from the Headquarters staff on NRC's Office of Enforcement (OE), from NRC's Regional Offices, and from utilities. The three sections of the report are: monthly highlights and statistics for commercial operating units, and errata from previously reported data; a compilation of detailed information on each unit, provided by NRC's Regional Offices, OE Headquarters and the utilities; and an appendix for miscellaneous information such as spent fuel storage capability, reactor-years of experience and non- power reactors in the US

Basewide Groundwater Operable Unit. Groundwater Operable Unit Remedial Investigation/Feasibility Study Report. Volume 1

Science.gov (United States)

1994-06-01

units would be reused in the remedy. Contingency measures to be included in the remedy are potential metals removal prior to water end use, potential...onbase reuse of a portion of the water, and wellhead treatment on offbase supply wells. The contingency measures will only be implemented if necessary...94 LEGEND Ouatmar aluvi dposts agua Frmaion(cosoldatd aluval epoits W iead rdetilnsMhte omtin(neitccnlmeae ansoe9ndkeca F 70 Quvatei-lernayalvu e pk

Data validation report for the 100-HR-3 Operable Unit, fifth round groundwater samples

International Nuclear Information System (INIS)

Vukelich, S.E.

1994-01-01

The data from the chemical analysis of 68 samples from the 100-HR-3 Operable Unit Third Quarter 1993 Groundwater Sampling Investigation and their related quality assurance samples were reviewed and validated to verify that reported sample results were of sufficient quality to support decisions regarding remedial actions performed at the site. Sample analysis included inorganics and general chemical parameters. Fifty three samples were validated for radiochemical parameters

Data validation report for the 100-D Ponds Operable Unit: 100-D ponds sampling

International Nuclear Information System (INIS)

Stankovich, M.T.

1994-01-01

Westinghouse-Hanford has requested that 100 percent of the Sample Delivery Groups be validated for the 100-D Ponds Operable Unit Sampling Investigation. Therefore the data from the chemical analysis of all 30 samples from this sampling event and their related quality assurance samples were reviewed and validated to verify that reported sample results were of sufficient quality to support decisions regarding remedial actions performed at this site

Final environmental statement related to operation of Indian Point Nuclear Generating Plant, Unit No. 3: (Docket No. 50-286): Volume 1

International Nuclear Information System (INIS)

1975-02-01

The proposed action is the issuance of a license to consolidated Edison Company of New York, Inc., for the operation of the Indian Point Nuclear Generating Plant, Unit No. 3, located in the State of New York, Westchester County, Village of Buchanan, 24 miles north of the New York City boundary line. Although the present action is the issuance of an operating license for Unit No. 3, this Statement considers the environmental impacts from simultaneous operation of all three Units. A Final Environmental Statement has been issued for Unit No. 2. Furthermore, in view of the proximity to the Indian Point site of existing and presently proposed power plants on the Hudson River, the cumulative environmental benefits and impacts of the plants within a 30-mile reach of the river have been assessed. The proposed action is interreleated to other actions taken by other Federal agencies such as the Environmental Protection Agency, in regard to granting or denying application for discharge permits under the National Pollutant Discharge Elimination System (NPDES) instituted through the Federal Water Pollution Control Act Amendments of 1972, and the Federal Power Commission, in licensing of other facilities on the Hudson River. 128 figs., 210 tabs

Limited field investigation report for the 100-HR-1 Operable Unit

International Nuclear Information System (INIS)

1994-08-01

This limited field investigation (LFI) report summarizes the data collection and analysis activities conducted during the 100-HR-1 Source Operable Unit LFI and the associated qualitative risk assessment (QRA) (WHC 1993a), and makes recommendations on the continued candidacy of high-priority sites for interim remedial measures (IRM). The results and recommendations presented in this report are generally independent of future land use scenarios. A LFI Report is required, in accordance with the HPPS, when waste sites are to be considered for IRMs. The LFI is an integral part of the remedial investigation/feasibility study (RI/FS) or Resource Conservation and Recovery Act (RCRA) facility investigation/corrective measures study (RFI/CMS) and process and functions as a focused RI or RFI for selection of IRMs. The purpose of the report is to identify those sites that are recommended to remain as candidates for IRMs, provide a preliminary summary of site characterization studies, refine the conceptual model as needed, identify contaminant- and location-specific applicable or relevant and appropriate requirements (ARA), and provide a qualitative assessment of the risks associated with the sites. This assessment includes consideration of whether contaminant concentrations pose an unacceptable risk that warrants action through IRMs. The 100-HR-1 unit encompasses approximately 100 acres adjacent to the Columbia River shoreline. It contains waste units associated with the original plant facilities constructed to support the H Reactor. The area also contains evaporation basins which received liquid process wastes and nonroutine deposits of chemical wastes from the 300 Area, where fuel elements for the N Reactor were produced

USDOE applied R ampersand D private sector initiatives

International Nuclear Information System (INIS)

Lien, S.C.T.

1990-01-01

The Department of Energy (DOE) has recently consolidated its Environmental Restoration and Waste Management activities. Within that new organization, DOE has committed to conduct Research, Development, Demonstration, Testing, and Evaluation (RDDT ampersand E) activities within the Office of Technology Development (OTD) to reduce cost, reduce risk, and otherwise improve the technologies to meet its cleanup goals. Currently available technology is not adequate to assess environmental contamination, take permanent remedial action, and to eliminate or minimize the environmental impact of future operations. To focus private sector capabilities on the high-priority needs of DOE, a series of competitive solicitations will be issued starting in FY 1990. This paper describes the range and scope of the DOE initiatives for private sector involvement in Applied R ampersand D. 2 tabs

Use of the LITEE Lorn Manufacturing Case Study in a Senior Chemical Engineering Unit Operations Laboratory

Science.gov (United States)

Abraham, Nithin Susan; Abulencia, James Patrick

2011-01-01

This study focuses on the effectiveness of incorporating the Laboratory for Innovative Technology and Engineering Education (LITEE) Lorn Manufacturing case into a senior level chemical engineering unit operations course at Manhattan College. The purpose of using the case study is to demonstrate the relevance of ethics to chemical engineering…

Design and operational considerations of United States commercial nea-surface low-level radioactive waste disposal facilities

International Nuclear Information System (INIS)

Birk, Sandra M.

1997-01-01

Low-level radioactive waste disposal standards and techniques in the United States have evolved significantly since the early 1960's. Six commercial LLW disposal facilities(Barnwell, Richland, Ward Valley, Sierra Blanca, Wake County and Boyd County) operated and proposed between 1962 and 1997. This report summarizes each site's design and operational considerations for near-surface disposal of low-level radioactive waste. These new standards and mitigating efforts at closed facilities (Sheffield, Maxey Flats, Beatty and West Valley) have helped to ensure that the public has been safely protected from LLW. 15 refs

The Agency's technical co-operation programme with the United Arab Emirates 1984-1994 country programme summaries

International Nuclear Information System (INIS)

1994-01-01

This report contains a review of the Agency's technical co-operation activities in the United Arab Emirates carried out during 1984-1994. In terms of coverage and analytical depth, country programmes summaries stand somewhere midway between in-depth country programme evaluations and individual project evaluations. They attempt to provide a comprehensive, descriptive picture of the Agency's co-operation with a Member State in a manner that will be particularly useful for programming decisions. The attempt is very much to describe - largely through statistical data - not to provide independent analysis and evaluation

Operable Unit 1 remedial investigation report, Eielson Air Force Base, Alaska

International Nuclear Information System (INIS)

Gilmore, T.J.; Fruland, R.M.; Liikala, T.L.

1994-06-01

This remedial investigation report for operable Unit 1 (OU-1) at Eielson Air Force Base presents data, calculations, and conclusions as to the nature and extent of surface and subsurface contamination at the eight source areas that make up OU-1. The information is based on the 1993 field investigation result and previous investigations. This report is the first in a set of three for OU-1. The other reports are the baseline risk assessment and feasibility study. The information in these reports will lead to a Record of Decision that will guide and conclude the environmental restoration effort for OU-1 at Eielson Air Force Base. The primary contaminants of concern include fuels and fuel-related contaminants (diesel; benzene, toluene, ethylbenzene, and xylene; total petroleum hydrocarbon; polycyclic aromatic hydrocarbons), maintenance-related solvents and cleaners (volatile chlorinated hydrocarbons such as trichloroothylene), polychlorinated biphenyls, and dichlorodiphenyltrichloroethane (DDT). The origins of contaminants of concern include leaks from storage tanks, drums and piping, and spills. Ongoing operations and past sitewide practices also contribute to contaminants of concern at OU-1 source areas. These include spraying mixed oil and solvent wastes on unpaved roads and aerial spraying of DDT

No Correlation Between Work-Hours and Operative Volumes--A Comparison Between United States and Danish Operative Volumes Achieved During Surgical Residency.

Science.gov (United States)

Kjærgaard, Jane; Sillesen, Martin; Beier-Holgersen, Randi

2016-01-01

Since 2003, United States residents have been limited to an 80-hour workweek. This has prompted concerns of reduced educational quality, especially inadequate operating exposure. In contrast, the Danish surgical specialty-training program mandates a cap on working hours of 37 per week. We hypothesize that there is no direct correlation between work-hours and operative volume achieved during surgical residency. To test the hypothesis, we compare Danish and US operative volumes achieved during surgical residency training. Retrospective comparative study. The data from the US population was extracted from the Accreditation Council for Graduate Medical Education database for General Surgery residents from 2012 to 2013. For Danish residents, a questionnaire with case categories matching the Accreditation Council for Graduate Medical Education categories were sent to all Danish surgeons graduating the national surgical residency program in 2012 or 2013, 54 in total. In all, 30 graduated residents (55%) responded to the Danish survey. We found no significant differences in mean total major procedures (1002.4 vs 976.9, p = 0.28) performed during residency training, but comparing average major procedures per year, the US residents achieve significantly more (132.3 vs 195.4, p work-hours and operative volumes achievable. Factors other than work-hours seem to effect on operative volumes achieved during training. Copyright © 2016 Association of Program Directors in Surgery. Published by Elsevier Inc. All rights reserved.

40 CFR 73.18 - Submittal procedures for units commencing commercial operation during the period from January 1...

Science.gov (United States)

2010-07-01

... commencing commercial operation during the period from January 1, 1993, through December 31, 1995. 73.18 Section 73.18 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) AIR PROGRAMS (CONTINUED) SULFUR DIOXIDE ALLOWANCE SYSTEM Allowance Allocations § 73.18 Submittal procedures for units...

Final environmental statement related to the operation of Callaway Plant, Unit No. 1 (Docket No. 50-483)

International Nuclear Information System (INIS)

1982-01-01

The final environmental statement contains the second assessment of the environmental impact associated with operation of Callaway Plant Unit 1, pursuant to the National Environmental Policy Act of 1969 (NEPA) and 10 CFR Par 51, as amended, of the NRC's regulations. This statement examines: the purpose and need for the Callaway project, alternatives to the project, the affected environment, environmental consequences and mitigating actions, and environmental and economic benefits and costs. No water-use impacts are expected from cooling-tower markup withdrawn from, or blowdown discharged into, the Missouri River. Land-use and terrestrial- and aquatic-ecological impacts will be small. Air-quality impacts from cooling-tower drift and other emissions and dust will also be small. Impacts to historic and prehistoric sites will be negligible with the development and implementation of the applicant's cultural-resources management plan. No significant impacts are anticipated from normal operational releases of radioactivity. The risk associated with accidental radiation exposure is very low. The net socioeconomic effects of the project will be beneficial. The action called for is the issuance of an operating license for Unit 1 of the Callaway Plant. 18 figs., 16 tabs

Draft environmental statement: Related to operation of the Edwin I. Hatch Nuclear Plant Unit No. 2, Georgia Power Company: Docket No. 50-366

International Nuclear Information System (INIS)

1977-04-01

The proposed action is the issuance of an operation license to the Georgia Power Company for the startup and operation of the Edwin I. Hatch Nuclear Plant, Unit No. 2 (Docket No. 50-366), located on the Altamaha River in Appling County, approximately 11 miles north from Baxley, Georgia. The information in this Statement represents the second, assessment of the environmental impact associated with the Edwin I. Hatch Nuclear Plant, Unit No. 2, pursuant to the guidelines of the National Environmental Policy Act of 1969 (NEPA) and 10 CFR Part 51 of the Commission's Regulations. After receipt of an application, in 1970, to construct this plant, the staff carried out a review of impact that would occur during the construction and operation of this plant. That evaluation was issued as a Final Environmental Statement in October 1972. As the result of that environmental review, a safety review, an evaluation by the Advisory Committee on Reactor Safeguards, and a public hearing in Baxley, Georgia and Washington, D.C., the AEC (now NRC) issued a permit in December 1972, for the construction of Unit No. 2 of the Edwin I. Hatch Nuclear Plant. As of February 1977, the construction of Unit No. 2 was 70% complete. With a proposed fuel-loading date of April 1978 for Unit No. 2, the applicant has petitioned for license to operate Unit No. 2 and has submitted (July 1975) the required safety and environmental reports to substantiate this petition. 97 refs., 18 figs., 37 tabs

Study of accelerated unit unloading mode initiated by turbine feed pump trip with TVSA fuel assemblies operation in WWER-1000

International Nuclear Information System (INIS)

Borysenko, V.I.; Kadenko, I.N.; Samoilenko, D.V.

2012-01-01

This paper provides the study results of accelerated unit unloading mode (AUU) initiated at WWER-1000 unit operated at 100 % power and its expediency in the event of single Turbo Feed Pump (TFP) failure. Modeling was performed using an advanced calculation code RELAP/SCDAPSIM/Mod3.4 and relevant model for KhNPP Unit No. 2. As the study shows, SCRAM cannot be prevented in case of failure of 3 main circulation pumps due to steam generators (SG) level drop. Based on the results obtained, it is reasonably justified to allow SCRAM signal instead of AUU activation in case of single TFP failure at power level more than 90 % of N n om. This will provide more sparing temperature modes for fuel assemblies and equipment, as well as prevent additional thermal cycling loads and violation of safe operation limits as SG water levels

Inverse spectral results for Schroedinger operators on the unit interval with partial information given on the potentials

International Nuclear Information System (INIS)

Amour, L.; Raoux, T.; Faupin, J.

2009-01-01

We pursue the analysis of the Schroedinger operator on the unit interval in inverse spectral theory initiated in the work of Amour and Raoux [''Inverse spectral results for Schroedinger operators on the unit interval with potentials in Lp spaces,'' Inverse Probl. 23, 2367 (2007)]. While the potentials in the work of Amour and Raoux belong to L 1 with their difference in L p (1≤p k,1 spaces having their difference in W k,p , where 1≤p≤+∞, k(set-membership sign)(0,1,2). It is proved that two potentials in W k,1 ([0,1]) being equal on [a,1] are also equal on [0,1] if their difference belongs to W k,p ([0,a]) and if the number of their common eigenvalues is sufficiently high. Naturally, this number decreases as the parameter a decreases and as the parameters k and p increase

Proposed plan for interim remedial measures at the 100-KR-1 Operable Unit. Revision 1

International Nuclear Information System (INIS)

1995-09-01

This proposed plan identifies the preferred alternative for interim remedial measures for remedial action of radioactive liquid waste disposal sites that include contaminated soils and structures at the 100-KR-1 Operable Unit, located at the Hanford Site. It also summarizes other remedial alternatives evaluated for interim remedial measures in this Operable Unit. The intent of interim remedial measures is to speed up actions to address contaminated areas that pose potential threats to human health and the environment. This proposed plan is being issued by the US Environmental Protection Agency (EPA), the lead regulatory agency; the Washington State Department of Ecology (Ecology), the support regulatory agency; and the US Department of Energy (DOE), the responsible agency. The EPA, Ecology, and the DOE are issuing this proposed plan as part of their public participation responsibilities under Section 117(a) of the Comprehensive Environmental Response, Compensation and Liability Act (CERCLA), commonly known as the ''Superfund Law.'' This proposed plan is intended to be a fact sheet for public review which briefly describes the remedial alternatives analyzed, identifies a preferred alternative, and summarizes the information relied upon to recommend the preferred alternative

Solving optimum operation of single pump unit problem with ant colony optimization (ACO) algorithm

International Nuclear Information System (INIS)

Yuan, Y; Liu, C

2012-01-01

For pumping stations, the effective scheduling of daily pump operations from solutions to the optimum design operation problem is one of the greatest potential areas for energy cost-savings, there are some difficulties in solving this problem with traditional optimization methods due to the multimodality of the solution region. In this case, an ACO model for optimum operation of pumping unit is proposed and the solution method by ants searching is presented by rationally setting the object function and constrained conditions. A weighted directed graph was constructed and feasible solutions may be found by iteratively searching of artificial ants, and then the optimal solution can be obtained by applying the rule of state transition and the pheromone updating. An example calculation was conducted and the minimum cost was found as 4.9979. The result of ant colony algorithm was compared with the result from dynamic programming or evolutionary solving method in commercial software under the same discrete condition. The result of ACO is better and the computing time is shorter which indicates that ACO algorithm can provide a high application value to the field of optimal operation of pumping stations and related fields.

Explanation of significant differences for the TNX groundwater operable unit

International Nuclear Information System (INIS)

Palmer, E.R.

1997-01-01

This Explanation of Significant Differences (ESD) is being issued by the Department of Energy (DOE), the lead agency for the Savannah River Site (SRS), with concurrence by the Environmental Protection Agency-Region IV (EPA) and South Carolina Department of Health and Environmental Control (SCDHEC) to announce changes in the interim remediation strategy selected for the TNX Groundwater Operable Unit. The TNX Area is located adjacent to the Savannah River in the southwestern portion of SRS. The remedy selected in the Interim Record of Decision (IROD) to achieve the interim action goals was the Hybrid Groundwater Corrective Action (HGCA). The HGCA consisted of a recirculation well system and an air stripper with a series of groundwater extraction wells. The original remediation strategy needs to be modified because the recirculation well system was determined to be ineffective in this area due to geological factors and the nature of the contamination

Hanford Site waste management units report

International Nuclear Information System (INIS)

1993-04-01

The Hanford Site Waste Management Units Report was originated to provide information responsive to Section 3004(u) of the Hazardous and Solid Waste Amendments of the 1984. This report provides a comprehensive inventory of all types of waste management units at the Hanford Site, including a description of the units and the waste they contain. Waste management units in the report include: (1) Resource Conservation and Recovery Act of 1976 (RCRA) disposal units, (2) Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA) disposal units, (3) unplanned releases, (4) inactive contaminated structures, (5) RCRA treatment, storage, and disposal (TSD) units, and (6) other storage areas. Because of the comprehensive nature of the units report, the list of units is more extensive than required by Section 3004(u) of Hazardous and Solid Waste Amendments of the 1984. In Sections 3.0 through 6.0 of this report, the four aggregate areas are subdivided into their operable units. The operable units are further divided into two parts: (1) those waste management units assigned to the operable unit that will be remediated as part of the Environmental Restoration Remedial Actions (ERRA) Program, and (2) those waste management units located within the operable unit boundaries but not assigned to the ERRA program. Only some operable unit sections contain the second part.Volume two contains Sections 4.0 through 6.0 and the following appendices: Appendix A -- acronyms and definition of terms; Appendix B -- unplanned releases that are not considered to be units; and Appendix C -- operable unit maps

Condition based monitoring, diagnosis and maintenance on operating equipments of a hydraulic generator unit

International Nuclear Information System (INIS)

Liu, X T; Feng, F Z; Si, A W

2012-01-01

According to performance characteristics of operating equipments in a hydraulic generator unit (HGU), the relative techniques on condition monitoring and fault diagnosis (CMFD) are introduced in this paper, especially the key technologies are emphasized, such as equipment monitoring, expert system (ES), intelligent diagnosis and condition based maintenance (CBM). Meanwhile, according to the instructor on CBM proposed by State electric power corporation, based on integrated mode, the main steps on implementation of CBM are discussed in this paper.

Final environmental statement related to the operation of Millstone Nuclear Power Station, Unit No. 3 (Docket No. 50-423)

International Nuclear Information System (INIS)

1984-12-01

This Final Environmental Statement contains the second assessment of the environmental impact associated with the operation of Millstone Nuclear Power Station, Unit 3, pursuant to the National Environmental Policy Act of 1969 (NEPA) and Title 10 of the Code of Federal Regulations, Part 51, as amended, of the Nuclear Regulatory Commission regulations. This statement examines the environment, environmental consequences and mitigating actions, and environmental and economic benefits and costs. Land use and terrestrial and aquatic ecological impacts will be small. Operational impacts to historic and archeologic sites will be small. The effects of routine operations, energy transmission, and periodic maintenance of rights-of-way and transmission facilities should not jeopardize any populations of endangered or threatened species. No significant impacts are anticipated from normal operational releases of radioactivity. The risk of radiation exposure associated with accidental release of radioactivity is very low. The net socioeconomic effects of the project will be beneficial. On the basis of the analysis and evaluation set forth in this environmental statement, it is concluded that the action called for under NEPA and 10 CFR 51 is the issuance of an operating license for Millstone Nuclear Power Station, Unit 3. 101 references, 33 figures, 30 tables

THE FINANCING OF THE ADMINISTRATIVE TERRITORIAL UNITS IN THE WEST DEVELOPMENT REGION THROUGH THE REGIONAL OPERATIONAL PROGRAMME 2007 - 2013

Directory of Open Access Journals (Sweden)

Munteanu Nicolae-Eugen

2011-07-01

Full Text Available It is very important to be found methods to increase the competitiveness between the Romanian administrative-territorial units, under the current conditions of the economic crisis, by means of the existing economic levers successfully used within the European Union regions. The development regions of Romania do not have the statute of administrative units, but they represent territorial units large enough to constitute a good basis for the elaboration and implementation of regional development strategies, allowing an efficient use of the financial and human resources. The scope for which these development regions were created had in view the support granted for the larger communities in their action to settle the problems which go beyond the administrative borders and which surpass the financial possibilities of one county. In Romania, the communes, towns, municipalities and counties are defined as administrative-territorial units within which the local autonomy is exercised and the authorities of the local public administration are organized and operate. The local, communal, town, municipality and county councils, as deliberative authorities, and also the mayors and the presidents of county councils as executive authorities have the duties to solve the public matters of the community, acting as authorities of the Romanian public administration. In Romania, the local autonomy is only administrative and financial, having as objective the organization, operation, competencies and tasks, and also the management of the inland resources. The principle of the local financial autonomy implies the fact that the administrative-territorial units have the right to financial resources, which can be used by the authorities of the local public administration when exercising their tasks. According to the Law of the local public finances, the local budget incomes could be made also of the non-reimbursable funds granted by the European Union. Based on the

Store-operate-coherence-on-value

Science.gov (United States)

Chen, Dong; Heidelberger, Philip; Kumar, Sameer; Ohmacht, Martin; Steinmacher-Burow, Burkhard

2014-11-18

A system, method and computer program product for performing various store-operate instructions in a parallel computing environment that includes a plurality of processors and at least one cache memory device. A queue in the system receives, from a processor, a store-operate instruction that specifies under which condition a cache coherence operation is to be invoked. A hardware unit in the system runs the received store-operate instruction. The hardware unit evaluates whether a result of the running the received store-operate instruction satisfies the condition. The hardware unit invokes a cache coherence operation on a cache memory address associated with the received store-operate instruction if the result satisfies the condition. Otherwise, the hardware unit does not invoke the cache coherence operation on the cache memory device.

Mass and number size distributions of emitted particulates at five important operation units in a hazardous industrial waste incineration plant.

Science.gov (United States)

Lin, Chi-Chi; Huang, Hsiao-Lin; Hsiao, Wen-Yuan

2016-01-01

Past studies indicated particulates generated by waste incineration contain various hazardous compounds. The aerosol characteristics are very important for particulate hazard control and workers' protection. This study explores the detailed characteristics of emitted particulates from each important operation unit in a rotary kiln-based hazardous industrial waste incineration plant. A dust size analyzer (Grimm 1.109) and a scanning mobility particle sizer (SMPS) were used to measure the aerosol mass concentration, mass size distribution, and number size distribution at five operation units (S1-S5) during periods of normal operation, furnace shutdown, and annual maintenance. The place with the highest measured PM10 concentration was located at the area of fly ash discharge from air pollution control equipment (S5) during the period of normal operation. Fine particles (PM2.5) constituted the majority of the emitted particles from the incineration plant. The mass size distributions (elucidated) made it clear that the size of aerosols caused by the increased particulate mass, resulting from work activities, were mostly greater than 1.5 μm. Whereas the number size distributions showed that the major diameters of particulates that caused the increase of particulate number concentrations, from work activities, were distributed in the sub micrometer range. The process of discharging fly ash from air pollution control equipment can significantly increase the emission of nanoparticles. The mass concentrations and size distributions of emitted particulates were different at each operation unit. This information is valuable for managers to take appropriate strategy to reduce the particulate emission and associated worker exposure.

Safety-Evaluation Report related to the operation of Grand Gulf Nuclear Station, Units 1 and 2. Docket Nos. 50-416 and 50-417

International Nuclear Information System (INIS)

1983-05-01

Supplement 4 to the Safety Evaluation Report for Mississippi Power and Light Company, et. al., joint application for licenses to operate the Grand Gulf Nuclear Station, Units 1 and 2, located on the east bank of the Mississippi River near Port Gibson in Claiborne County, Mississippi, has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. This supplement reports the status on the resolution of those issues that required further evaluation before authorizing operation of Unit 1 above 5% rated power and other issues that were to be evaluated during the first cycle of power operation

Chapter 3. Coordination and collaboration with interface units. Recommendations and standard operating procedures for intensive care unit and hospital preparations for an influenza epidemic or mass disaster

NARCIS (Netherlands)

Joynt, Gavin M.; Loo, Shi; Taylor, Bruce L.; Margalit, Gila; Christian, Michael D.; Sandrock, Christian; Danis, Marion; Leoniv, Yuval; Sprung, Charles L.; Camargo, Ruben; Ceraso, Daniel; Azoulay, Elie; Duguet, Alexandre; Guery, Benoit; Reinhart, Konrad; Adini, Bruria; Barlavie, Yaron; Benin-Goren, Odeda; Cohen, Robert; Klein, Motti; Rubinovitch, Bina; Sonnenblick, Moshe; Steinberg, Avraham; Weissman, Charles; Wolff, Donna; Kesecioglu, Jozef; de Jong, Menno; Moreno, Rui; An, Youzhong; Du, Bin; Joyng, Gavin M.; Colvin, John; Richards, Guy; Artigas, Antonio; Pugin, Jerome; Amundson, Dennis; Devereaux, Asha; Beigel, John; Farmer, Chris; Hick, John L.; Maki, Dennis; Masur, Henry; Rubinson, Lewis; Talmor, Daniel; Truog, Robert; Zimmerman, Janice; Brett, Steve; Montgomery, Hugh; Rhodes, Andrew; Sanderson, Frances

2010-01-01

To provide recommendations and standard operating procedures (SOPs) for intensive care unit (ICU) and hospital preparations for an influenza pandemic or mass disaster with a specific focus on enhancing coordination and collaboration between the ICU and other key stakeholders. Based on a literature

76 FR 388 - Southern Nuclear Operating Company; Vogtle Electric Generating Plant, Unit Nos. 1 and 2; Notice...

Science.gov (United States)

2011-01-04

... Operating Company; Vogtle Electric Generating Plant, Unit Nos. 1 and 2; Notice of Consideration of Issuance... Web site http://www.regulations.gov . Because your comments will not be edited to remove any... will not edit their comments to remove any identifying or contact information, and therefore, they...

Overview of the Habitat Demonstration Unit Power System Integration and Operation at Desert RATS 2010

Science.gov (United States)

Colozza, Anthony J.; George, Pat; Gambrell, Ronnie; Chapman, Chris

2013-01-01

A habitat demonstration unit (HDU) was constructed at NASA Johnson Space Center (JSC) and designed by a multicenter NASA team led out of NASA Kennedy Space Center (KSC). The HDU was subsequently utilized at the 2010 Desert Research and Technology Studies (RATS) program held at the Black Point Lava Flow in Arizona. This report describes the power system design, installation and operation for the HDU. The requirements for the power system were to provide 120 VAC, 28 VDC, and 120 VDC power to the various loads within the HDU. It also needed to be capable of providing power control and real-time operational data on the load's power consumption. The power system had to be capable of operating off of a 3 phase 480 VAC generator as well as 2 solar photovoltaic (PV) power systems. The system operated well during the 2 week Desert RATS campaign and met all of the main goals of the system. The power system is being further developed to meet the future needs of the HDU and options for this further development are discussed.

Oak Ridge National Laboratory site data for safety-analysis report

International Nuclear Information System (INIS)

Fitzpatrick, F.C.

1982-12-01

The Oak Ridge National Laboratory site data contained herein were compiled in support of the United States Department of Energy (USDOE) Oak Ridge Operations Office Order OR 5481.1. That order sets forth assignment of responsibilities for safety analysis and review responsibilities and provides guidance relative to the content and format of safety analysis reports. The information presented in this document is intended for use by reference in individual safety analysis reports where applicable to support accident analyses or the establishment of design bases of significance to safety, and it is applicable only to Oak Ridge National Laboratory facilities in Bethel and Melton Valleys. This information includes broad descriptions of the site characteristics, radioactive waste handling and monitoring practices, and the organization and operating policies at Oak Ridge National Laboratory. The historical background of the Laboratory is discussed briefly and the overall physical situation of the facilities is described in the following paragraphs

Oak Ridge National Laboratory site data for safety-analysis report

Energy Technology Data Exchange (ETDEWEB)

Fitzpatrick, F.C.

1982-12-01

The Oak Ridge National Laboratory site data contained herein were compiled in support of the United States Department of Energy (USDOE) Oak Ridge Operations Office Order OR 5481.1. That order sets forth assignment of responsibilities for safety analysis and review responsibilities and provides guidance relative to the content and format of safety analysis reports. The information presented in this document is intended for use by reference in individual safety analysis reports where applicable to support accident analyses or the establishment of design bases of significance to safety, and it is applicable only to Oak Ridge National Laboratory facilities in Bethel and Melton Valleys. This information includes broad descriptions of the site characteristics, radioactive waste handling and monitoring practices, and the organization and operating policies at Oak Ridge National Laboratory. The historical background of the Laboratory is discussed briefly and the overall physical situation of the facilities is described in the following paragraphs.

Superfund Record of Decision (EPA Region 6): United Nuclear Corporation, Mckinley County, New Mexico, ground-water operable unit (first remedial action) September 1988

International Nuclear Information System (INIS)

1988-01-01

The United Nuclear Corporation (UNC) site is located approximately 17 miles northeast of Gallup, New Mexico in McKinley County. The site operated as a State-licensed uranium mill facility from June 1977 to May 1982. It includes an ore-processing mill (about 25 acres) and an unlined tailings pond area (about 100 acres). In July 1979, approximately 23 million gallons of tailings and pond water were released to a nearby river as a result of a dam breach in the tailings pond area. The site damage was repaired; however, attention was focused on ground-water contamination resulting from tailings seepage. Nevertheless, the offsite migration of radionuclides and chemical constituents from uranium milling byproduct materials into the ground water, as well as to surface water and air, are still principal threats at the site. The remedial action will address onsite ground water contamination. Source control and onsite surface reclamation will be implemented under the direction of the Nuclear Regulatory Commission and integrated with this ground water operable unit. The primary contaminants of concern affecting the ground water are metals including arsenic, and radioactive substances including radium-226/228 and gross alpha. The selected remedial action for the site is included

Hanford Site waste management units report

International Nuclear Information System (INIS)

1993-04-01

The Hanford Site Waste Management Units Report was originated to provide information responsive to Section 3004(u) of the Hazardous and Solid Waste Amendments of the 1984. This report provides a comprehensive inventory of all types of waste management units at the Hanford Site, including a description of the units and the waste they contain. Waste management units in the report include: (1) Resource Conservation and Recovery Act of 1976 (RCRA) disposal units, (2) Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA) disposal units, (3) unplanned releases, (4) inactive contaminated structures, (5) RCRA treatment, storage, and disposal (TSD) units, and (6) other storage areas. Because of the comprehensive nature of the units report, the list of units is more extensive than required by Section 3004(u) of Hazardous and Solid Waste Amendments of the 1984. In Sections 3.0 through 6.0 of this report, the four aggregate areas are subdivided into their operable units. The operable units are further divided into two parts: (1) those waste management units assigned to the operable unit that will be remediated as part of the Environmental Restoration Remedial Actions (ERRA) Program, and (2) those waste management units located within the operable unit boundaries but not assigned to the ERRA program. Only some operable unit sections contain the second part

ENHANCING THE OPERATIONAL EFFICIENCY OF DIRECT CURRENT DRIVE BASED ON USE OF SUPERCONDENSER POWER STORAGE UNITS

Directory of Open Access Journals (Sweden)

А. M. Mukha

2017-10-01

Full Text Available Purpose.The scientific work is intended to analyse the expansion of the load range and the implementation of regeneration braking (RB of the direct current drive by using the supercondenser power storage units. Methodology.To solve the problem, we use the methods of the electric drive theory, impulse electronics and the method of calculation of transient electromagnetic processes in linear electric circuits in the presence of super-condensers therein. Findings.The stiffness of the mechanical and electromechanical characteristics of a series motor is significantly increased, which makes it possible to use a DC drive under load, much smaller than 15…20% of the nominal one. Numerical calculations of the operation process of the supercondenser power storage unit were fulfilled with a sharp decrease in the load of a traction electric motor of a direct current electric locomotive. The possibility of RB of the direct current drive with the series motor is substantiated. The equations of the process of charging and discharging of super-condenser storage unit in RB mode are solved. The authors examined the effect of capacitance on the nature of maintaining the excitation current of an electric motor in the mode of small loads.Originality.The paper developed theoretical approaches for the transformation of soft (mechanical and electromechanical characteristics into hard ones of DC series motors. For the first time a new, combined method of the series motor RB is proposed and substantiated. Further development obtained the methods for evaluating the storage unit parameters, taking into account the criteria for reliable parallel operation of super-condensers with an electric motor field. Practical value.The proposed and substantiated transformation of soft characteristics into stiff ones allows us to use general-purpose electric drives with series motors and at low loads, and in traction electric drives - to reduce the intensity of electric stockwheel

Remedial design report and remedial action work plan for the 100-HR-3 and 100-KR-4 groundwater operable units' interim action

International Nuclear Information System (INIS)

1996-09-01

This document is a combination remedial design report and remedial action work plan for the 100-HR-3 and 100-KR-4 Operable Units (located on the Hanford Site in Richland, Washington) interim action. The interim actions described in this document represent the first of an ongoing program to address groundwater contamination in each operable unit. This document describes the design basis, provides a description of the interim action, and identifies how they will meet the requirements set forth in the interim action Record of Decision

Final Environmental Statement related to the operation of Beaver Valley Power Station, Unit 2 (Docket No. 50-412)

International Nuclear Information System (INIS)

1985-09-01

This Final Environmental Statement contains the second assessment of the environmental impact associated with Beaver Valley Power Station Unit 2 pursuant to the National Environmental Policy Act of 1969 (NEPA) and Title 10 of the Code of Federal Regulations, Part 51, as amended, of the Nuclear Regulatory Commission regulations. This statement examines the environment, environmental consequences and mitigating actions, and environmental benefits and costs, and concludes that the action called for is the issuance of an operating license for Beaver Valley Unit 2

Clinical microbiology in the intensive care unit: Strategic and operational characteristics

Directory of Open Access Journals (Sweden)

Bhattacharya S

2010-01-01

Full Text Available Infection is a major cause of morbidity and mortality among patients admitted in intensive care units (ICUs. The application of the principles and the practice of Clinical Microbiology for ICU patients can significantly improve clinical outcome. The present article is aimed at summarising the strategic and operational characteristics of this unique field where medical microbiology attempts to venture into the domain of direct clinical care of critically ill patients. The close and strategic partnership between clinical microbiologists and intensive care specialists, which is essential for this model of patient care have been emphasized. The article includes discussions on a variety of common clinical-microbiological problems faced in the ICUs such as ventilator-associated pneumonia, blood stream infections, skin and soft tissue infection, UTI, infection control, besides antibiotic management.

Estimation of the radiation risks for population in the process of the BN-600 power unit operation at the Beloyarsk NPP

International Nuclear Information System (INIS)

Koltik, I.I.; Oshkanov, N.N.

2005-01-01

Dose burdens on the population are the main criterion in estimating the radiological risks during NPP operation. Results of analysis of annual dose burdens on the population in the period of the BN-600 unit operation are presented. Data on individual and collective doses due to gas-aerosol and liquid effluents of radionuclides from the BN-600 unit on critical groups of population are presented. Data on collective doses due to other types of reactors are provided. It is shown that the risks stemming from the BN type reactors are approximately 2 orderers below the risks of channel-type and WWER-reactors [ru

Site-specific waste management instruction for the 100-KR-4 Operable Unit drilling. Revision 1

International Nuclear Information System (INIS)

Hadley, J.T.

1996-08-01

This site-specific waste management instruction provides guidance for the management of waste generated as a result of groundwater well installations in the 100-KR-4 Operable Unit (OU). The well installations are necessary to implement the Remedial Action (RA) option (pump-and-treat using ion exchange) to prevent discharge of hexavalent chromium at levels above those considered protective of aquatic life in the Columbia River and riverbed sediments

46 CFR 153.903 - Operating a United States ship in special areas: Categories A, B, and C.

Science.gov (United States)

2010-10-01

... NLS residue in a special area unless— (a) The ship's Certificate of Inspection is endorsed in... 46 Shipping 5 2010-10-01 2010-10-01 false Operating a United States ship in special areas... (CONTINUED) CERTAIN BULK DANGEROUS CARGOES SHIPS CARRYING BULK LIQUID, LIQUEFIED GAS, OR COMPRESSED GAS...

Description of the U.S. Geological Survey's water-quality sampling and water-level monitoring program at the Hallam Nuclear Facility, August through September 1997

International Nuclear Information System (INIS)

1997-01-01

A water-quality and water-level program between the US Department of Energy (USDOE) and the US Geological Survey (USGS) was re-established in August 1997 to (1) collect one set of water-quality samples from 17 of the 19 USDOE monitor wells, and (2) make five water-level measurements during a 2-month period from the 19 USDOE monitor wells at the Hallam Nuclear Facility, Hallam, Nebraska. Data from these wells are presented

Aquifer test plan for the 100-HR-3 Operable Unit

International Nuclear Information System (INIS)

Swanson, L.C.; Hartman, M.J.

1994-01-01

This test plan directs hydrologic testing activities planned at three existing Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA) wells in the 100-HR-3 Operable Unit of the Hanford Site. Three additional wells will be installed near these existing wells and used as additional testing arid observation points during the field activities. Figure 1 shows the locations of the three test sites. A primary objective of the testing program is to provide more detailed hydraulic characterization information for the unconfined aquifer and targeted test sites than provided by the initial reconnaissance-level slug testing of Vukelich. A second objective is to evaluate the applicability of slug interference and dipole flow tests for detailed hydraulic characterization in an unconfined aquifer. This aquifer testing program will also be useful for substantiating hydraulic conductivities reported from previous slug tests and evaluating the effects of filter pack volume/configuration on slug test data. Vukelich recommended additional testing to address the latter two issues

Final environmental statement related to the operation of South Texas Project, Units 1 and 2 (Docket Nos. 50-498 and 50-499)

International Nuclear Information System (INIS)

1986-08-01

This Final Environmental Statement contains the second assessment of the environmental impact associated with the operation of the South Texas Project, Units 1 and 2, pursuant to the National Environmental Policy Act of 1969 (NEPA) and Title 10 of the Code of Federal Regulations, Part 51, as amended, of the Nuclear Regulatory Commission regulations. This statement examines the environmental impacts, environmental consequences and mitigating actions, and environmental and economic benefits and costs associated with station operation. Land use and terrestrial and aquatic ecological impacts will be small. No operational impacts to historic and archeological sites are anticipated. The effects of routine operations, energy transmission, and periodic maintenance of rights-of-way and transmission facilities should not jeopardize any populations of endangered or threatened species. No significant impacts are anticipated from normal operational releases of radioactivity. The risk of radiation exposure associated with accidental release of radioactivity is very low. Socioeconomic impacts of the project are anticipated to be minimal. The action called for is the issuance of an operating license for South Texas Project, Units 1 and 2

State heating oil and propane program. Final report, 1992--1993

International Nuclear Information System (INIS)

Rizzolo, D.R.

1997-01-01

In cooperation with the United States Department of Energy (USDOE), Energy Information Administration (EIA) the New Jersey Department of Environmental Protection and Energy (DEPE), Office of Energy participated in an ongoing program to monitor retail prices of no. 2 heating oil and propane in New Jersey. According to program instructions, we conducted price surveys on a semi-monthly basis to obtain the necessary information from retail fuel merchants and propane dealers identified by the EIA. According to program instructions and at the discretion of the USDOE, we conducted four additional propane surveys on January 11 and 25, and April 5 and 19, 1993. The heating oil surveys began on October 5, 1992 and ended on March 15, 1993. The propane surveys began on October 5, 1992 and ended on April 19, 1993. We submitted data collected as of specified report dates to the EIA, within two working days of those dates

Strategic Psychological Operations management

OpenAIRE

Sokoloski, Joseph A.

2005-01-01

United States Military Psychological Operations are engaged in a type of mass marketing of ideas. To accomplish this The United States Army Civil Affairs and Psychological Operations Command (USACAPOC) employs active and reserve PSYOP units to conduct PSYOP campaigns. However the methodology used to manage these campaigns often hinders the effective employment of timely and effective Psychological Operations. PSYOP has a difficult job to accomplish but PSYOP does not have the proper managemen...

Treatment/Disposal Plan for Drummed Waste from the 300-FF-1 Operable Unit, 618-4 Burial Ground

International Nuclear Information System (INIS)

Lerch, J.A.

1999-01-01

The objective of this plan is to support selection of a safe, environmentally responsible, and cost-effective treatment and disposal method for drums containing depleted uranium metal chips submerged in oil that have been and will be excavated from the 618-4 Burial Ground. Remediation of the 300-FF-1 Operable Unit, 618-4 Burial Ground was initiated in fiscal year (FY) 1998 as an excavation and removal operation. Routine processes were established to excavate and ship contaminated soil and debris to the Environmental Restoration Disposal Facility (ERDF) for disposal

Safety evaluation report related to the operation of Diablo Canyon Nuclear Power Plant, Units 1 and 2 (Docket Nos. 50-275 and 50-323)

International Nuclear Information System (INIS)

1983-12-01

Supplement 20 to the Safety Evaluation Report for Pacific Gas and Electric Company's application for licenses to operate Diablo Canyon Nuclear Power Plant, Unit 1 and Unit 2 (Docket Nos. 50-275 and 50-323), has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. This supplement reports on the verification effort for Diablo Canyon Unit 1 that was performed between November 1981 and the present in response to Commission Order CLI-81-30 and an NRC letter of November 19, 1981 to the licensee. Specifically, Supplement 20 addresses those issues and other matters identified in Supplements 18 and 19 that must be resolved prior to Unit 1 achieving criticality and operating at power levels up to 5% of rated full power. This SER Supplement applies only to Diablo Canyon Unit 1

Research and development associated with licensing of MHTGR [Modular High Temperature Gas-Cooled Reactor

International Nuclear Information System (INIS)

Jones, H.

1990-01-01

The Modular High Temperature Gas-Cooled Reactor (MHTGR) currently under development by the US Department of Energy (US-DOE) for commercial applications has top-level goals of producing safe, economical power for the US utility industry. The utility industry has been represented in formulating design and licensing requirements through both a ''Utility User Requirements Document'' and by participating in the DOE system engineering process known as the ''Integrated Approach.'' The result of this collaboration has been to set stringent goals for both the safety and operational reliability of the MHTGR. To achieve these goals, the designer must have access to a more comprehensive data base of properties in several fields of technology than is currently available. A technology development program has been planned to provide this data to the designer in time to support both his design activities and the submittal of formal licensing application documents. The US-DOE has chosen the Oak Ridge National Laboratory (ORNL) to take the lead in planning and executing these technology programs. When completed these will augment the designer's current data base and provide the necessary depth to meet the stringent goals which have been set for the MHTGR. It is worth noting that the goals of safety and operational reliability are complementary, and the data required from the technology development program will be similar. Therefore, the program to support the licensing of the MHTGR is not separate from that required for design, but is a subset of that which meets all the requirements that result from implementing the US-DOE's integrated approach. 38 figs

76 FR 30206 - Southern Nuclear Operating Company, Inc., Vogtle Electric Generating Plant, Unit 1 and 2; Notice...

Science.gov (United States)

2011-05-24

... Operating Company, Inc., Vogtle Electric Generating Plant, Unit 1 and 2; Notice of Consideration of Issuance..., http://www.regulations.gov . Because your comments will not be edited to remove any identifying or... received from other persons for submission to the NRC inform those persons that the NRC will not edit their...

Fessenheim 2: ASN's green light for continuing operation - Beginning of the works for unit 1

International Nuclear Information System (INIS)

Anon.

2013-01-01

Every 10 years a nuclear power plant operator has to make a re-assessment of the nuclear safety standard of his plant. This re-assessment is made of 2 parts: first the review of the safety conformity and secondly a thorough re-examination of the safety that takes into account today's safety standards and feedback experience from similar plants. This detailed assessment of the safety aims at checking that the consequences of the different aging phenomena are well mastered for the next 10 years at least. At the end of this re-assessment, the ASN (French Nuclear Safety Authorities) decide or not the continuation of plant activity or can prescribe safety improvements. In the case of the unit 2 of the Fessenheim plant that has just finished its third decennial safety re-assessment, the ASN has prescribed the same improvements as for the unit 1, that is to say the reinforcement of the resistance to corium of the foundation raft and an improvement on the emergency cooling system. The works on the unit 1 have begun despite contestation from anti-nuclear associations that question the cost of the safety upgrading (20 to 30 millions euros) while the unit is expected to be decommissioned by end 2016. (A.C.)

Operational challenges and opportunities in pastured poultry operations in the United States.

Science.gov (United States)

Elkhoraibi, C; Pitesky, M; Dailey, N; Niemeier, D

2017-06-01

As pastured poultry production has gained increased popularity in the United States in recent years, there is a growing need for research and outreach efforts aimed at this sector of poultry production. In order to get familiarized with American pastured poultry producers, we conducted an online questionnaire aimed primarily at evaluating what operational challenges are faced by producers and what educational opportunities should be initiated by researchers. Results showed that pastured poultry farms largely vary in total number of acres farmed and total number of birds kept. The vast majority of farms (96%) rotate their flocks on pasture and include livestock species (78%) in their rotation systems. Mobile coops are the preferred housing option provided by producers (88%). The most common source of mortality listed by respondents was predation (52%), followed by "other" (32%). However, predation was not selected as the most important challenge by the majority of respondents. Sixty-four percent of participants instead mentioned providing adequate feed at reasonable cost as the major challenge in raising poultry on pasture, followed again by "other" (52%) and lack of processing facilities for small numbers of birds (40%). Finally, the topics considered by respondents as the most helpful to learn more about were how to improve egg production rate and/or feed conversion ratio (67%), followed by how to improve pasture condition and optimum vegetative cover all year round (62%). Despite its small sample size, this study's results provide some valuable insights of challenges encountered and information needed on pastured poultry farms. © 2017 Poultry Science Association Inc.

Surface radiation survey and soil sampling of the 300-FF-1 operable unit, Hanford Site, southeastern Washington: A case study

International Nuclear Information System (INIS)

Teel, S.S.; Olsen, K.B.

1990-10-01

The methods used for conducting a radiological characterization of the soil surface for the Phase I Remedial Investigation of a Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) site is presented via a case study. The study site is an operable unit (300-FF-1) located in and adjacent to the 300 Area of the US Department of Energy's Hanford Site in southeastern Washington State. The operable unit contains liquid and solid waste disposal facilities associated with nuclear fuels fabrication. Continuous surface radiation surveying and soil sampling of selected locations were conducted. Contamination was found in several locations within the operable unit including areas near the liquid and solid waste disposal facilities. Instruments used during surveying included portable beta/gamma (P-11) detectors, and the Ultrasonic Ranging and Data System using an NaI (Tl) detector. Laboratory analyses results indicate that above-background radiation levels were primarily due to the presence of uranium. Both types of field instruments used in the study were effective in detecting surface contamination from radionuclides; however, each had specific advantages. Guidelines are presented for the optimum use of these instruments when performing a radiological characterization of the soil surface. 4 refs., 3 figs., 3 tabs

Model for Determining the Consumption of Machinery, Tableware, Fuel, Oils and Lubricants with the Participation of Units from the Bulgarian Army in Humanitarian Operations

Directory of Open Access Journals (Sweden)

Nichev Nikolay

2017-06-01

Full Text Available Regulating documents of the Bulgarian Army considered norms for support classic combat operations and in fact Bulgarian Army has no planning methods to be used for planning of humanitarian operations. Solving this problem can be achieved through the use of planning factors. Planning factors are generally based on experience or data on the use of resources from previous operations. The participation of units of the Bulgarian Army in humanitarian operations have failed to bring to the accumulation of data needed to create a suitable planning factors. The purpose of the study is to develop a model by which to bring out planning factors in determining the the consumption of machinery, tableware, fuel, oils and lubricants with the participation of units from the Bulgarian Army in humanitarian operations.

Ageing Management of the reactor internals in Belgian nuclear units in view of Long Term Operation

International Nuclear Information System (INIS)

Gerard, R.; Bertolis, D.; Vissers, S.

2012-01-01

The reactor internals support the reactor core, distribute the coolant flow through the core, and guide and protect the rod control cluster assemblies and in-core instrumentation. Their integrity must be guaranteed in all operating and accident conditions. They are exposed to specific degradation mechanisms linked to the intense neutron irradiation, like Irradiation Assisted Stress Corrosion Cracking (IASCC) or potentially void swelling, in addition to more classical mechanisms like fatigue, wear and stress corrosion cracking. A rigorous follow-up of in-service degradation and an effective ageing management is therefore of crucial importance and contributes to the safe and economical operation of nuclear PWR units. (author)

Ergonomic relationship during work in nursing staff of intensive care unit with operating room

Directory of Open Access Journals (Sweden)

Yousef Mahmoudifar

2017-01-01

Full Text Available Background and Objectives: High prevalence of work-related musculoskeletal disorders, especially in jobs such as nursing which covers tasks like patients' repositioning, has attracted great attentions from occupational healthcare experts to necessitate the knowledge of ergonomic science. Therefore, this study was performed aiming at ergonomic relationship during work in nursing staff of Intensive Care Unit (ICU with operating room. Materials and Methods: In this descriptive-analytical study (cohort, fifty personnel of ICU staff and fifty of operating room staff were selected through a census method and were assessed using tools such as Nordic questionnaire and Rapid Entire Body Assessment (REBA standards in terms of body posture ergonomics. The obtained data were analyzed by SPSS software and Chi-Square test after collection. Results: The most complaints were from the operating room group (68% and ICU staff (60% for the lumbar musculoskeletal system. There was a significant relationship between the total REBA scores of body, legs, neck, arm, force status, load fitting with hands and static or dynamic activities in the operating room and ICU staff groups (P < 0.05. In operating room and ICU groups, most subjects obtained score 11–15 and very high-risk level. Conclusion: Nurses working at operating room and ICU ward are subjected to high-risk levels and occupational injuries which is dramatically resulted from inappropriate body posture or particular conditions of their works. As a result, taking corrective actions along with planning and identifying ways will help prohibiting the prevalence of disorders in the future.

Rate of generation of tritium during the operation of Tsuruga Power Station Unit No. 2

International Nuclear Information System (INIS)

Funamoto, Hisao; Yoshinari, Masaharu; Fukuda, Masayuki; Makino, Shinichi; Watari, Tuneo

1994-01-01

Total amount of 3 H activity in primary coolant due to the operation of Tsuruga Power Station Unit No. 2 was estimated. The 3 H inventory was measured for samples from the spent fuel pool, primary coolant and miscellaneous tanks. From the result of the measurement and the data of environmental release of 3 H, the rate of generation of 3 H in the reactor was found to be 25 TBq/GWa. Since Tsuruga Power Station Unit No. 2 is a PWR type reactor, we presume that most of the 3 H in primary coolant is formed by 10 B(n, 2α) 3 H reaction. It is necessary to release about 23 TBq/GWa of 3 H to maintain the station inventory at the present level. (author)

Data validation summary report for the 100-BC-5 Operable Unit Round 8 Groundwater Sampling

International Nuclear Information System (INIS)

Kearney, A.T.

1996-03-01

The information provided in this validation summary report includes data from the chemical analyses of samples from the 100-BC-5 Operable Unit Round 8 Groundwater Sampling Investigation. All of the data from this sampling event and their related quality assurance samples were reviewed and validated to verify that the reported sample results were of sufficient quality to support decisions regarding remedial actions performed at this site. Sample analyses included metals, general chemistry and radiochemistry

Research in Support of Remediation Activities at the Savannah River Site

International Nuclear Information System (INIS)

Seaman, J.C.; B.B. Looney and M.K. Harris

2007-01-01

The USDOE Savannah River Site (SRS), an 803-km 2 (310-mile 2 ) facility located south of Aiken, SC on the upper Atlantic Coastal Plain and bounded to the west by the Savannah River, was established in the 1950s for the production and refinement of nuclear materials. To fulfill this mission during the past 50 years SRS has operated five nuclear reactors, two large chemical separation areas, waste disposal facilities (landfills, waste ponds, waste tanks, and waste stabilization), and a large number of research and logistics support facilities. Contaminants of concern (COC) resulting from site operations include chlorinated solvents, radionuclides, metals, and metalloids, often found as complex mixtures that greatly complicate remediation efforts when compared with civilian industries. The objective of this article is to provide a description of the lithology and hydrostratigraphy of the SRS, as well as a brief history of site operations and research activities as a preface to the current special section of Vadose Zone Journal (VZJ) dedicated to SRS, focusing mainly on issues that are unique to the USDOE complex. Contributions to the special section reflect a diverse range of topics, from hydrologic tracer experiments conducted both within the vadose and saturated zones to studies specifically aimed at identifying geochemical processes controlling the migration and partitioning of specific contaminants (e.g., TCE, 137 Cs, U, and Pu) in SRS subsurface environments. Addressing the diverse environmental challenges of the SRS provides a unique opportunity to conduct both fundamental and applied research across a range of experimental scales. Hence, the SRS has been a pioneering force in several areas of environmental research and remediation, often through active interdisciplinary collaboration with researchers from other USDOE facilities, academic and federal institutions, and commercial entities

Safety Evaluation Report related to the operation of Diablo Canyon Nuclear Power Plant, Units 1 and 2 (Docket Nos. 50-275 and 50-323)

International Nuclear Information System (INIS)

1991-06-01

Supplement 34 to the Safety Evaluation Report for the application by Pacific Gas and Electric Company (PG ampersand E) for licenses to operate Diablo Canyon Nuclear Power Plant, Unit Nos. 1 and 2 (Docket Nos. 50-275 and 50-323, respectively) has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. This supplement documents the NRC staff review of the Long-Term Seismic Program conducted by PG ampersand E in response to License Condition 2.C.(7) of Facility Operating License DPR-80, the Diablo Canyon Unit 1 operating license. 111 refs., 20 figs., 31 tabs

Safety evaluation report related to the operation of LaSalle County Station, Units 1 and 2, (Docket Nos. 50-373 and 50-374). Supplement No. 7

International Nuclear Information System (INIS)

1983-12-01

Supplement No. 7 to the Safety Evaluation Report of Commonwealth Edison Company's application for a license to operate its La Salle County Station, Unit 2, located on Brookfield Township, La Salle County, Illinois, has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. This supplement is to update our evaluations on Unit 2 issues identified in the previous Safety Evaluation Report and Supplements that need resolution prior to issuance of the operating license for Unit 2

Chapter 1. Introduction. Recommendations and standard operating procedures for intensive care unit and hospital preparations for an influenza epidemic or mass disaster

NARCIS (Netherlands)

Sprung, Charles L.; Cohen, Robert; Adini, Bruria; Christian, Michael D.; Camargo, Ruben; Ceraso, Daniel; Azoulay, Elie; Duguet, Alexandre; Guery, Benoit; Reinhart, Konrad; Barlavie, Yaron; Benin-Goren, Odeda; Klein, Motti; Leoniv, Yuval; Margalit, Gila; Rubinovitch, Bina; Sonnenblick, Moshe; Steinberg, Avraham; Weissman, Charles; Wolff, Donna; Kesecioglu, Jozef; de Jong, Menno; Moreno, Rui; An, Youzhong; Du, Bin; Joynt, Gavin M.; Colvin, John; Loo, Shi; Richards, Guy; Artigas, Antonio; Pugin, Jerome; Amundson, Dennis; Devereaux, Asha; Beigel, John; Danis, Marion; Farmer, Chris; Hick, John L.; Maki, Dennis; Masur, Henry; Rubinson, Lewis; Sandrock, Christian; Talmor, Daniel; Truong, Robert; Zimmerman, Janice; Brett, Steve; Montgomery, Hugh; Rhodes, Andrew; Sanderson, Frances; Taylor, Bruce; Monrgomery, Hugh

2010-01-01

In December 2007, the European Society of Intensive Care Medicine established a Task Force to develop standard operating procedures (SOPs) for operating intensive care units (ICU) during an influenza epidemic or mass disaster. To provide direction for health care professionals in the preparation and

OPERATIONAL EXPERIENCE: UPGRADED MPC AND A SYSTEMS FOR THE RADIOCHEMICAL PLANT OF THE SIBERIAN CHEMICAL COMBINE

International Nuclear Information System (INIS)

RODRIGUEZ, C.; GOLOSKOKOV, I.; FISHBONE, L.; GOODEY, K.; LOOMIS, M.; CRAIN, B. JR.; LARSEN, R.

2003-01-01

The success of reducing the risk of nuclear proliferation through physical protection and material control/accounting systems depends upon the development of an effective design that includes consideration of the objectives of the systems and the resources available to implement the design. Included among the objectives of the design are facility characterization, definition of threat, and identification of targets. When considering resources, the designer must consider funds available, rapid low-cost elements, technology elements, human resources, and the availability of resources to sustain operation of the end system. The Siberian Chemical Combine (SCC) is a multi-function nuclear facility located in the Tomsk region of Siberia, Russia. Beginning in 1996, SCC joined with the United States Department of Energy (US/DOE) Material Protection, Control, and Accounting (MPC and A) Program to develop and implement MPC and A upgrades for the Radiochemical, Chemical Metallurgical, Conversion, Uranium Enrichment, and Reactor Plants of the SCC. At the Radiochemical Plant the MPC and A design and implementation process has been largely completed for the Plutonium Storage Facility and related areas of the Radiochemical Plant. Design and implementation of upgrades for the Radiochemical Plant include rapid physical protection upgrades such as bricking up of doors and windows, and installation of security-hardened doors. Rapid material control and accounting upgrades include installation of modern balances and bar code equipment. Comprehensive MPC and A upgrades include the installation of access controls to sensitive areas of the Plant, alarm communication and display (AC and D) systems to detect and annunciate alarm conditions, closed circuit (CCTV) systems to assess alarm conditions, central and secondary alarm station upgrades that enable security forces to assess and respond to alarm conditions, material control and accounting upgrades that include upgraded physical

Licensed operating reactors

International Nuclear Information System (INIS)

1990-01-01

The US Nuclear Regulatory Commission's monthly LICENSED OPERATING REACTORS Status Summary Report provides data on the operation of nuclear units as timely and accurately as possible. This information is collected by the Office of Information Resources Management, from the Headquarters Staff of NRC's Office of Inspection and Enforcement, from NRC's Regional Offices, and from utilities. This report is divided into three sections: the first contains monthly highlights and statistics for commercial operating units, and errata from previously reported data; the second is a compilation of detailed information on each unit, provided by NRC Regional Offices, IE Headquarters and the Utilities; and the third section is an appendix for miscellaneous information such as spent fuel storage capability, reactor years of experience and non-power reactors in the United States

Licensed operating reactors

International Nuclear Information System (INIS)

Hartfield, R.A.

1990-03-01

The US Nuclear Regulatory Commission's monthly Licensed Operating Reactors Status Summary Report provides data on the operation of nuclear units as timely and accurately as possible. This information is collected by the Office of Information Resources Management, from the Headquarters Staff of NRC's Office of Inspection and Enforcement, from NRC's Regional Offices, and from utilities. This report is divided into three sections: the first contains monthly highlights and statistics for commercial operating units, and errata from previously reported data; the second is a compilation of detailed information on each unit, provided by NRC Regional Offices, IE Headquarters and the Utilities; and the third section is an appendix for miscellaneous information such as spent fuel storage capability, reactor years of experience and non-power reactors in the United States

Licensed operating reactors

International Nuclear Information System (INIS)

1989-08-01

The US Nuclear Regulatory Commission's monthly LICENSED OPERATING REACTORS Status Summary Report provides data on the operation of nuclear units as timely and accurately as possible. This information is collected by the Office of Information Resources Management, from the Headquarters Staff of NRC's Office of Inspection and Enforcement, from NRC's Regional Offices, and from utilities. This report is divided into three sections: the first contains monthly highlights and statistics for commercial operating units, and errata from previously reported data; the second is a compilation of detailed information on each unit, provided by NRC Regional Offices, IE Headquarters and the utilities; and the third section is an appendix for miscellaneous information such as spent fuel storage capability, reactor years of experience and non-power reactors in the United States

Model for Sucker-Rod Pumping Unit Operating Modes Analysis Based on SimMechanics Library

Science.gov (United States)

Zyuzev, A. M.; Bubnov, M. V.

2018-01-01

The article provides basic information about the process of a sucker-rod pumping unit (SRPU) model developing by means of SimMechanics library in the MATLAB Simulink environment. The model is designed for the development of a pump productivity optimal management algorithms, sensorless diagnostics of the plunger pump and pumpjack, acquisition of the dynamometer card and determination of a dynamic fluid level in the well, normalization of the faulty unit operation before troubleshooting is performed by staff as well as equilibrium ratio determining by energy indicators and outputting of manual balancing recommendations to achieve optimal power consumption efficiency. Particular attention is given to the application of various blocks from SimMechanics library to take into account the pumpjack construction principal characteristic and to obtain an adequate model. The article explains in depth the developed tools features for collecting and analysis of simulated mechanism data. The conclusions were drawn about practical implementation possibility of the SRPU modelling results and areas for further development of investigation.

A Survey on Operator Monotonicity, Operator Convexity, and Operator Means

Directory of Open Access Journals (Sweden)

Pattrawut Chansangiam

2015-01-01

Full Text Available This paper is an expository devoted to an important class of real-valued functions introduced by Löwner, namely, operator monotone functions. This concept is closely related to operator convex/concave functions. Various characterizations for such functions are given from the viewpoint of differential analysis in terms of matrix of divided differences. From the viewpoint of operator inequalities, various characterizations and the relationship between operator monotonicity and operator convexity are given by Hansen and Pedersen. In the viewpoint of measure theory, operator monotone functions on the nonnegative reals admit meaningful integral representations with respect to Borel measures on the unit interval. Furthermore, Kubo-Ando theory asserts the correspondence between operator monotone functions and operator means.

Quality and productivity drive innovation and improvement at United Technologies Aerospace Operations, Inc.

Science.gov (United States)

Jamar, L. G.

1986-01-01

Quality and innovation are the hallmarks of the national space program. In programs that preceded the Shuttle Program the emphasis was on meeting the risks and technical challenges of space with safety, quality, reliability, and success. At United Technologies Aerospace Operations, Inc. (UTAO), the battle has developed along four primary fronts. These fronts include programs to motivate and reward people, development and construction of optimized processes and facilities, implementation of specifically tailored management systems, and the application of appropriate measurement and control systems. Each of these initiatives is described. However, to put this quality and productivity program in perspective, UTAO and its role in the Shuttle Program are described first.

Safety Evaluation Report related to the operation of Diablo Canyon Nuclear Power Plant, Units 1 and 2 (Docket Nos. 50-275 and 50-323)

International Nuclear Information System (INIS)

1984-07-01

Supplement 27 to the Safety Evaluation Report for Pacific Gas and Electric Company's application for a license to operate Diablo Canyon Nuclear Power Plant, Unit 1 (Docket No. 50-275), has been prepared by the Office of Nuclear Reactor Regulation of the US Nuclear Regulatory Commission. This supplement addresses the revisions to the license conditions and to the Technical Specifications as they relate to Amendment 10 to Diablo Canyon, Unit 1 Facility Operating License, DPR-76

Licensed operating reactors

International Nuclear Information System (INIS)

1989-11-01

The US Nuclear Regulatory Commission's monthly Licensed Operating Reactors Status Summary Report provides data on the operation of nuclear units as timely and accurately as possible. This information is collected by the Office of Information Resources Management, from the Headquarters Staff of NRC's Office of Inspection and Enforcement, from NRC's Regional Offices, and from utilities. Since all of the data concerning operation of the units is provided by the utility operators less than two weeks after the end of the month, necessary corrections to published information are shown on the errata page