Liquid Metal Fast Breeder Reactor Program: Argonne facilities

International Nuclear Information System (INIS)

Stephens, S.V.

1976-09-01

The objective of the document is to present in one volume an overview of the Argonne National Laboratory test facilities involved in the conduct of the national LMFBR research and development program. Existing facilities and those under construction or authorized as of September 1976 are described. Each profile presents brief descriptions of the overall facility and its test area and data relating to its experimental and testing capability. The volume is divided into two sections: Argonne-East and Argonne-West. Introductory material for each section includes site and facility maps. The profiles are arranged alphabetically by title according to their respective locations at Argonne-East or Argonne-West. A glossary of acronyms and letter designations in common usage to describe organizations, reactor and test facilities, components, etc., involved in the LMFBR program is appended

The organization of ALARA program at a DOE facility

International Nuclear Information System (INIS)

Setaro, J.A.

1992-01-01

The organization of an ALARA Program at a DOE Facility (Oak Ridge National Laboratory), it's relationship with laboratory management, facility operators, and the radiation protection program is described. The use of chartered ALARA committees at two distinct levels is discussed

Review of biological monitoring programs at nuclear facilities

International Nuclear Information System (INIS)

Quintana, L.R.; Oakes, T.W.; Shank, K.E.

Biological monitoring programs, as well as relevant radioecological research studies, are reviewed at specific Department of Energy facilities; the program at Oak Ridge National Laboratory is discussed in detail. The biological measurements that are being used for interpreting the impact of a facility on its surrounding environment and nearby population are given. Suggestions which could facilitate interlaboratory comparison studies are presented

Experimental facilities for plate-out investigations and future work

International Nuclear Information System (INIS)

Muenchow, K.; Dederichs, H.; Iniotakis, N.; Sackmann, B.

1981-01-01

The safety of HTR under normal operation and accident conditions, the possibility of inspection, maintenance and repair or decontamination of single primary components as well as the safety of maintenance personnel are essentially determined by the transport- and deposition behaviour of the non gaseous fission - and activation products in the primary loop of the reactor. A comprehensive program has been started in 1969 in KFA in collaboration with various industrial firms and foreign institutions to investigate these problems. The program includes in-pile and out-pile experiments, simulating reactor conditions and also different laboratory experiments and extensive theoretical investigations. The aim of these efforts is to test experimentally the models and computercodes, which are used for prediction of transport and deposition behaviour of fission products for HTR's as well under normal as under accident conditions. Further more a verified dataset is to be established. In this paper a survey is given of the experimental facilities carried out by KFA or in cooperation with KFA

Assessment of the facilities on Jackass Flats and other Nevada Test Site facilities for the new nuclear rocket program

International Nuclear Information System (INIS)

Chandler, G.; Collins, D.; Dye, K.; Eberhart, C.; Hynes, M.; Kovach, R.; Ortiz, R.; Perea, J.; Sherman, D.

1992-01-01

Recent NASA/DOE studies for the Space Exploration Initiative have demonstrated a critical need for the ground-based testing of nuclear rocket engines. Experience in the ROVER/NERVA Program, experience in the Nuclear Weapons Testing Program, and involvement in the new nuclear rocket program has motivated our detailed assessment of the facilities used for the ROVER/NERVA Program and other facilities located at the Nevada Test Site (NTS). The ROVER/NERVA facilities are located in the Nevada Research L, Development Area (NRDA) on Jackass Flats at NTS, approximately 85 miles northwest of Las Vegas. To guide our assessment of facilities for an engine testing program we have defined a program goal, scope, and process. To execute this program scope and process will require ten facilities. We considered the use of all relevant facilities at NTS including existing and new tunnels as well as the facilities at NRDA. Aside from the facilities located at remote sites and the inter-site transportation system, all of the required facilities are available at NRDA. In particular we have studied the refurbishment of E-MAD, ETS-1, R-MAD, and the interconnecting railroad. The total cost for such a refurbishment we estimate to be about $253M which includes additional contractor fees related to indirect, construction management, profit, contingency, and management reserves. This figure also includes the cost of the required NEPA, safety, and security documentation

10 CFR 611.202 - Advanced Technology Vehicle Manufacturing Facility Award Program.

Science.gov (United States)

2010-01-01

... 10 Energy 4 2010-01-01 2010-01-01 false Advanced Technology Vehicle Manufacturing Facility Award... TECHNOLOGY VEHICLES MANUFACTURER ASSISTANCE PROGRAM Facility/Funding Awards § 611.202 Advanced Technology Vehicle Manufacturing Facility Award Program. DOE may issue, under the Advanced Technology Vehicle...

ORNL Isotopes Facilities Shutdown Program Plan

International Nuclear Information System (INIS)

Gibson, S.M.; Patton, B.D.; Sears, M.B.

1990-10-01

This plan presents the results of a technical and economic assessment for shutdown of the Oak Ridge National Laboratory (ORNL) isotopes production and distribution facilities. On December 11, 1989, the Department of Energy (DOE), Headquarters, in a memorandum addressed to DOE Oak Ridge Operations Office (DOE-ORO), gave instructions to prepare the ORNL isotopes production and distribution facilities, with the exception of immediate facility needs for krypton-85, tritium, and yttrium-90, for safe shutdown. In response to the memorandum, ORNL identified 17 facilities for shutdown. Each of these facilities is located within the ORNL complex with the exception of Building 9204-3, which is located at the Y-12 Weapons Production Plant. These facilities have been used extensively for the production of radioactive materials by the DOE Isotopes Program. They currently house a large inventory of radioactive materials. Over the years, these aging facilities have inherited the problems associated with storing and processing highly radioactive materials (i.e., facilities' materials degradation and contamination). During FY 1990, ORNL is addressing the requirements for placing these facilities into safe shutdown while maintaining the facilities under the existing maintenance and surveillance plan. The day-to-day operations associated with the surveillance and maintenance of a facility include building checks to ensure that building parameters are meeting the required operational safety requirements, performance of contamination control measures, and preventative maintenance on the facility and facility equipment. Shutdown implementation will begin in FY 1993, and shutdown completion will occur by the end of FY 1994

Fast reactor test facilities in the US safety program

International Nuclear Information System (INIS)

Avery, R.; Dickerman, C.E.; Lennox, D.H.; Rose, D.

1979-01-01

The needs for safety information derivable from in-pile programs are reviewed, and the correlation made with existing and planned capability. In view of the current status of the U.S. breeder program, emphasis is given in the review to the impact of different fast breeder options on the required program and facilities. It is concluded that facility needs are somewhat independent of specific fast breeder concept, even though the relative emphasis on the various safety issues will differ. 8 refs

The NRU blowdown test facility commissioning program

Energy Technology Data Exchange (ETDEWEB)

Walsworth, J A; Zanatta, R J; Yamazaki, A R; Semeniuk, D D; Wong, W; Dickson, L W; Ferris, C E; Burton, D H [Atomic Energy of Canada Ltd., Chalk River, ON (Canada). Chalk River Nuclear Labs.

1990-12-31

A major experimental program has been established at the Chalk River Nuclear Laboratories (CRL) that will provide essential data on the thermal and mechanical behaviour of nuclear fuel under abnormal reactor operating conditions and on the transient release, transport and deposition of fission product activity from severely degraded fuel. A number of severe fuel damage (SFD) experiments will be conducted within the Blowdown Test Facility (BTF) at CRL. A series of experiments are being conducted to commission this new facility prior to the SFD program. This paper describes the features and the commissioning program for the BTF. A development and testing program is described for critical components used on the reactor test section. In-reactor commissioning with a fuel assembly simulator commenced in 1989 June and preliminary results are given. The paper also outlines plans for future all-effects, in-reactor tests of CANDU-designed fuel. (author). 11 refs., 3 tabs., 7 figs.

Effective flow-accelerated corrosion programs in nuclear facilities

International Nuclear Information System (INIS)

Esselman, Thomas C.; McBrine, William J.

2004-01-01

Piping Flow-Accelerated Corrosion Programs in nuclear power generation facilities are classically comprised of the selection of inspection locations with the assistance of a predictive methodology such as the Electric Power Research Institute computer codes CHECMATE or CHECWORKS, performing inspections, conducting structural evaluations on the inspected components, and implementing the appropriate sample expansion and corrective actions. Performing such a sequence of steps can be effective in identifying thinned components and implementing appropriate short term and long term actions necessary to resolve flow-accelerated corrosion related problems. A maximally effective flow-accelerated corrosion (FAC) program requires an understanding of many programmatic details. These include the procedural control of the program, effective use of historical information, managing the activities performed during a limited duration outage, allocating resources based on risk allocation, having an acute awareness of how the plant is operated, investigating components removed from the plant, and several others. This paper will describe such details and methods that will lead to a flow-accelerated corrosion program that effectively minimizes the risk of failure due to flow-accelerated corrosion and provide full and complete documentation of the program. (author)

Feasibility Investigation for a Solar Power Generation Facility

Science.gov (United States)

Nathan, Lakshmi

2010-01-01

The Energy Policy Act of 2005 states that by fiscal year 2013, at least 7.5% of the energy consumed by the government must be renewable energy. In an effort to help meet this goal, Johnson Space Center (JSC) is considering installing a solar power generation facility. The purpose of this project is to conduct a feasibility investigation for such a facility. Because Kennedy Space Center (KSC) has a solar power generation facility, the first step in this investigation is to learn about KSC's facility and obtain information on how it was constructed. After collecting this information, the following must be determined: the amount of power desired, the size of the facility, potential locations for it, and estimated construction and maintenance costs. Contacts with JSC's energy provider must also be established to determine if a partnership would be agreeable to both parties. Lastly, all of this data must be analyzed to decide whether or not JSC should construct the facility. The results from analyzing the data collected indicate that a 200 kW facility would provide enough energy to meet 1% of JSC's energy demand. This facility would require less than 1 acre of land. In the map below, potential locations are shown in green. The solar power facility is projected to cost $2 M. So far, the information collected indicates that such a facility could be constructed. The next steps in this investigation include contacting JSC's energy provider, CenterPoint Energy, to discuss entering a partnership; developing a life cycle cost analysis to determine payback time; developing more detailed plans; and securing funding.

A simulation based research on chance constrained programming in robust facility location problem

Directory of Open Access Journals (Sweden)

Kaijun Leng

2017-03-01

Full Text Available Since facility location decisions problem include long-term character and potential parameter variations, it is important to consider uncertainty in its modeling. This paper examines robust facility location problem considering supply uncertainty, in which we assume the supply of the facility in the actual operation is not equal to the supply initially established, the supply is subject to random fluctuation. The chance constraints are introduced when formulating the robust facility location model to make sure the system operate properly with a certain probability while the supply fluctuates. The chance constraints are approximated safely by using Hoeffding’s inequality and the problem is transformed to a general deterministic linear programming. Furthermore, how the facility location cost change with confidence level is investigated through a numerical example. The sensitivity analysis is conducted for important parameters of the model and we get the main factors that affect the facility location cost.

Four critical facilities: their capabilities and programs

International Nuclear Information System (INIS)

Whitesides, G.E.

1980-01-01

Information is presented on the critical experiments facilities at Babcock and Wilcox, Lynchburg, Virginia; at Battelle Pacific Northwest Laboratory in Hanford, Washington; at Rockwell-International in Rocky Flats, Colorado; and at Los Alamos Scientific Laboratory in New Mexico. It is noted that the critical mass facilities which still exist in this country represent a bare minimum for maintaining a measurement program sufficient for meeting data requirements

The Pinellas Plant RCRA facility investigation - A case study

International Nuclear Information System (INIS)

Kilbury, Richard; Keshian, Berg; Farley, Dwain; Meyer, David; Ingle, David; Biedermann, Charles

1992-01-01

Under the direction of the U.S. Department of Energy Albuquerque Field Office Environmental Restoration Program, a Resource Conservation and Recovery Act (RCRA) Facility Investigation (RFI) was completed at the Pinellas Plant to fulfill requirements of the Hazardous and Solid Waste Amendments of 1984 (HSWA) permit issued on February 9, 1990 by the U.S. Environmental Protection Agency (EPA). This RFI addressed potential contaminant releases and environmental conditions at 15 solid waste management units (SWMUs). The RFI characterization program began in April 1990 and was completed in May 1991. The scope of RFI data collection activities is presented in the Pinellas Plant RFI Workplan issued in May 1990 and approved by EPA on April 16, 1991. An RFI Report was submitted to EPA on September 1, 1991. This paper presents a summary of RFI results and conclusions. Primary environmental concerns at the Pinellas Plant are emphasized. (author)

Risk management program for the 283-W water treatment facility

International Nuclear Information System (INIS)

Green, W.E.

1999-01-01

This Risk Management (RM) Program covers the 283-W Water Treatment Facility (283W Facility), located in the 200 West Area of the Hanford Site. A RM Program is necessary for this facility because it stores chlorine, a listed substance, in excess of or has the potential to exceed the threshold quantities defined in Title 40 of the Code of Federal Regulations (CFR) Part 68 (EPA, 1998). The RM Program contains data that will be used to prepare a RM Plan, which is required by 40 CFR 68. The RM Plan is a summary of the RM Program information, contained within this document, and will be submitted to the U.S. Environmental Protection Agency (EPA) ultimately for distribution to the public. The RM Plan will be prepared and submitted separately from this document

Progress and problems in the Formerly Utilized Sites Remedial Action Program and Surplus Facilities Management Program

International Nuclear Information System (INIS)

Fiore, J.J.; Turi, G.P.

1988-01-01

The Formerly Utilized Sites Remedial Action Program (FUSRAP) was established in 1974 to identify, evaluate, and as appropriate, conduct remedial actions at sites used in the early years of nuclear energy development by the Manhattan Engineer District and the Atomic Energy Commission (AEC). This program currently has 29 sites and is evaluating 350 other sites for possible inclusion in the program. Another remedial action program in the Department of Energy's (DOE) Division of Facility and Site Decommissioning Projects is the Surplus Facilities Management Program (SFMP). The SFMP involves the safe management, decontamination and disposal of surplus DOE contaminated facilities which were not related to defense activities. There are currently 33 projects at 15 different sites in the program. These two programs have made steady progress over the last 10 or so years in cleaning up sites so that they can be reused or released for unrestricted use. Work has been completed at 8 of the FUSRAP sites and three of the SFMP sites

Performance indicator program for U.S. Department of Energy reactors and facilities

International Nuclear Information System (INIS)

Sastry, R.; Fielding, J.R.; Snyder, B.J.; Usher, J.; Boccio, J.

1990-01-01

The U.S. Department of Energy (DOE) is developing a Performance Indicator (PI) Program for all facilities. The objective is to periodically collect, statistically analyze and present performance-related information in a concise and consistent format for DOE and safety of facility operations. A set of 14 DOE-Hq. defined PI's has been established after review of programs used by other organizations. Since July 1989, these PI's have been used in a trial program for eight diverse DOE facilities. Electronic reporting is directly to the DOE Safety Performance Measurement System computer. This paper reports on results demonstrated for the feasibility and usefulness of a DOE-wide PI Program and steps being taken to include all DOE facilities

200 Area Liquid Effluent Facilities -- Quality assurance program plan

International Nuclear Information System (INIS)

Fernandez, L.

1995-01-01

This Quality Assurance Program Plan (QAPP) describes the quality assurance and management controls used by the 200 Area Liquid Effluent Facilities (LEF) to perform its activities in accordance with DOE Order 5700.6C. The 200 Area LEF consists of the following facilities: Effluent Treatment Facility (ETF); Treated Effluent Disposal Facility (TEDF); Liquid Effluent Retention facility (LERF); and Truck Loading Facility -- (Project W291). The intent is to ensure that all activities such as collection of effluents, treatment, concentration of secondary wastes, verification, sampling and disposal of treated effluents and solids related with the LEF operations, conform to established requirements

Recommendations for quality assurance programs in nuclear medicine facilities. Radiation recommendations series

International Nuclear Information System (INIS)

Segal, P.; Hamilton, D.R.

1984-10-01

The publication provides the elements that should be considered by nuclear medicine facilities to improve their existing programs or develop new quality assurance programs. The important administrative aspects of quality assurance programs are stressed. Each facility is encouraged to adopt those elements of the recommended program that are appropriate to its individual needs and resources

45 CFR 2490.150 - Program accessibility: Existing facilities.

Science.gov (United States)

2010-10-01

... 45 Public Welfare 4 2010-10-01 2010-10-01 false Program accessibility: Existing facilities. 2490.150 Section 2490.150 Public Welfare Regulations Relating to Public Welfare (Continued) JAMES MADISON... ACTIVITIES CONDUCTED BY THE JAMES MADISON MEMORIAL FELLOWSHIP FOUNDATION § 2490.150 Program accessibility...

Horonobe Underground Research Laboratory project. Investigation program for the 2008 fiscal year

International Nuclear Information System (INIS)

Nakayama, Masashi; Sanada, Hiroyuki; Yamaguchi, Takehiro; Sugita, Yutaka

2008-09-01

As part of the research and development program on geological disposal of high-level radioactive waste (HLW), the Horonobe Underground Research Center, a division of the Japan Atomic Energy Agency (JAEA), is implementing the Horonobe Underground Research Laboratory Project (Horonobe URL Project) with the aim at investigating sedimentary rock formations. According to the research plan described in the Midterm Plan of JAEA, geological investigations are to be carried out during the drilling of a shaft down to intermediate depth, while research and development in the areas of engineering technology and safety assessment are to be promoted by collaboration with other research organizations. The results of the R and D activities will be systematized as a 'knowledge base' that supports a wide range of arguments related to the safety of geological disposal. The Horonobe URL Project is planned to extend over a period of 20 years. The investigations will be conducted in three phases, namely 'Phase 1: Surface-based investigations', 'Phase 2: Construction phase' (investigations during construction of the underground facilities) and 'Phase 3: Operation phase' (research in the underground facilities). This report summarizes the investigation program for the 2008 fiscal year (2008/2009), the 4th year of the Phase 2 investigations. In the 2008 fiscal year, investigations in geoscientific research', including 'development of techniques for investigating the geological environment', 'development of techniques for long-term monitoring of the geological environment', 'development of engineering techniques for use in the deep underground environment' and studies on the long-term stability of the geological environment', are continuously carried out. Investigations in 'research and development on geological disposal technology', including 'improving the reliability of disposal technologies' and 'enhancement of safety assessment methodologies', are also continuously carried out

5 CFR 1636.150 - Program accessibility: Existing facilities.

Science.gov (United States)

2010-01-01

... fundamental alteration in the nature of a program or activity or in undue financial and administrative burdens... facilities. 1636.150 Section 1636.150 Administrative Personnel FEDERAL RETIREMENT THRIFT INVESTMENT BOARD ENFORCEMENT OF NONDISCRIMINATION ON THE BASIS OF HANDICAP IN PROGRAMS OR ACTIVITIES CONDUCTED BY THE FEDERAL...

49 CFR 28.150 - Program accessibility: Existing facilities.

Science.gov (United States)

2010-10-01

... 49 Transportation 1 2010-10-01 2010-10-01 false Program accessibility: Existing facilities. 28.150 Section 28.150 Transportation Office of the Secretary of Transportation ENFORCEMENT OF NONDISCRIMINATION ON THE BASIS OF HANDICAP IN PROGRAMS OR ACTIVITIES CONDUCTED BY THE DEPARTMENT OF TRANSPORTATION § 28...

ORNL Surplus Facilities Management Program maintenance and surveillance plan for fiscal year 1984

International Nuclear Information System (INIS)

Coobs, J.H.; Myrick, T.E.

1986-10-01

The Surplus Facilities Management Program (SFMP) at Oak Ridge National Laboratory (ORNL) is part of the Department of Energy's (DOE) National SFMP, administered by the Richland Operations Office. The purpose and objectives of the national program are set forth in the current SFMP Program Plan and include (1) the maintenance and surveillance of facilities awaiting decommissioning, (2) planning for the orderly decommissioning of these facilities, and (3) implementation of a program to accomplish the facility disposition in a safe, cost-effective, and timely manner. As outlined in the national program plan, participating SFMP contractors are required to prepare a formal plan that documents the maintenance and surveillance (M and S) programs established for each site. This report has been prepared to provide this documentation for those facilties included in the ORNL SFMP

25 CFR 170.803 - What facilities are eligible under the BIA Road Maintenance Program?

Science.gov (United States)

2010-04-01

... AND WATER INDIAN RESERVATION ROADS PROGRAM BIA Road Maintenance § 170.803 What facilities are eligible under the BIA Road Maintenance Program? (a) The following public transportation facilities are eligible for maintenance under the BIA Road Maintenance Program: (1) BIA transportation facilities listed in...

FY11 Facility Assessment Study for Aeronautics Test Program

Science.gov (United States)

Loboda, John A.; Sydnor, George H.

2013-01-01

This paper presents the approach and results for the Aeronautics Test Program (ATP) FY11 Facility Assessment Project. ATP commissioned assessments in FY07 and FY11 to aid in the understanding of the current condition and reliability of its facilities and their ability to meet current and future (five year horizon) test requirements. The principle output of the assessment was a database of facility unique, prioritized investments projects with budgetary cost estimates. This database was also used to identify trends for the condition of facility systems.

Overview of the Defense Programs Research and Technology Development Program for fiscal year 1993. Appendix II research laboratories and facilities

Energy Technology Data Exchange (ETDEWEB)

1993-09-30

This document contains summaries of the research facilities that support the Defense Programs Research and Technology Development Program for FY 1993. The nine program elements are aggregated into three program clusters as follows: (1) Advanced materials sciences and technologies; chemistry and materials, explosives, special nuclear materials (SNM), and tritium. (2) Design sciences and advanced computation; physics, conceptual design and assessment, and computation and modeling. (3) Advanced manufacturing technologies and capabilities; system engineering science and technology, and electronics, photonics, sensors, and mechanical components. Section I gives a brief summary of 23 major defense program (DP) research and technology facilities and shows how these major facilities are organized by program elements. Section II gives a more detailed breakdown of the over 200 research and technology facilities being used at the Laboratories to support the Defense Programs mission.

Characterization of mixed waste for shipment to TSD Facilities Program

International Nuclear Information System (INIS)

Chandler, K.; Goyal, K.

1995-01-01

In compliance with the Federal Facilities Compliance Agreement, Los Alamos National Laboratory (LANL) is striving to ship its low-level mixed waste (LLMW) off-site for treatment and disposal. In order to ship LLMW off site to a commercial facility, LANL must request exemption from the DOE Order 5820.2A requirement that LLMW be shipped only to Department of Energy facilities. Because the process of obtaining the required information and approvals for a mixed waste shipment campaign can be very expensive, time consuming, and frustrating, a well-planned program is necessary to ensure that the elements for the exemption request package are completed successfully the first time. LANL has developed such a program, which is cost- effective, quality-driven, and compliance-based. This program encompasses selecting a qualified analytical laboratory, developing a quality project-specific sampling plan, properly sampling liquid and solid wastes, validating analytical data, documenting the waste characterization and decision processes, and maintaining quality records. The products of the program are containers of waste that meet the off-site facility's waste acceptance criteria, a quality exemption request package, documentation supporting waste characterization, and overall quality assurance for the process. The primary goal of the program is to provide an avenue for documenting decisions, procedures, and data pertinent to characterizing waste and preparing it for off-site treatment or disposal

12 CFR 410.150 - Program accessibility: Existing facilities.

Science.gov (United States)

2010-01-01

... 12 Banks and Banking 4 2010-01-01 2010-01-01 false Program accessibility: Existing facilities. 410.150 Section 410.150 Banks and Banking EXPORT-IMPORT BANK OF THE UNITED STATES ENFORCEMENT OF NONDISCRIMINATION ON THE BASIS OF HANDICAP IN PROGRAMS OR ACTIVITIES CONDUCTED BY EXPORT-IMPORT BANK OF THE UNITED...

Hanford Site waste tank farm facilities design reconstitution program plan

International Nuclear Information System (INIS)

Vollert, F.R.

1994-01-01

Throughout the commercial nuclear industry the lack of design reconstitution programs prior to the mid 1980's has resulted in inadequate documentation to support operating facilities configuration changes or safety evaluations. As a result, many utilities have completed or have ongoing design reconstitution programs and have discovered that without sufficient pre-planning their program can be potentially very expensive and may result in end-products inconsistent with the facility needs or expectations. A design reconstitution program plan is developed here for the Hanford waste tank farms facility as a consequence of the DOE Standard on operational configuration management. This design reconstitution plan provides for the recovery or regeneration of design requirements and basis, the compilation of Design Information Summaries, and a methodology to disposition items open for regeneration that were discovered during the development of Design Information Summaries. Implementation of this plan will culminate in an end-product of about 30 Design Information Summary documents. These documents will be developed to identify tank farms facility design requirements and design bases and thereby capture the technical baselines of the facility. This plan identifies the methodology necessary to systematically recover documents that are sources of design input information, and to evaluate and disposition open items or regeneration items discovered during the development of the Design Information Summaries or during the verification and validation processes. These development activities will be governed and implemented by three procedures and a guide that are to be developed as an outgrowth of this plan

The BNL Accelerator Test Facility and experimental program

International Nuclear Information System (INIS)

Ben-Zvi, I.; State Univ. of New York, Stony Brook, NY

1992-01-01

The Accelerator Test Facility (ATF) at BNL is a users' facility for experiments in Accelerator and Beam Physics. The ATF provides high brightness electron beams and high-power laser pulses synchronized to the electron beam, suitable for studies of new methods of high-gradient acceleration and state-of-the-art Free-Electron Lasers. The electrons are produced by a laser photocathode rf gun and accelerated to 50 MeV by two traveling wave accelerator sections. The lasers include a 10 mJ, 10 ps ND:YAG laser and a 500 mJ, 10 to 100 ps C0 2 laser. A number of users from National Laboratories, universities and industry take part in experiments at the ATF. The experimental program includes various laser acceleration schemes, Free-Electron Laser experiments and a program on the development of high-brightness electron beams. The ATF's experimental program commenced in early 1991 at an energy of about 4 MeV. The full program, with 50 MeV and the high-power laser will begin operation this year

The BNL Accelerator Test Facility and experimental program

International Nuclear Information System (INIS)

Ben-Zvi, I.; State Univ. of New York, Stony Brook, NY

1991-01-01

The Accelerator Test Facility (ATF) at BNL is a users' facility for experiments in Accelerator and Beam Physics. The ATF provides high brightness electron beams and high power laser pulses synchronized to the electron beam, suitable for studies of new methods of high gradient acceleration and state of the art free electron lasers. The electrons are produced by a laser photocathode rf gun and accelerated to 50 to 100 MeV by two traveling wave accelerator sections. The lasers include a 10 mJ, 10 ps Nd:YAG laser and a 100 mJ, 10 ps CO 2 laser. A number of users from National Laboratories, universities and industry take part in experiments at the ATF. The experimental program includes various acceleration schemes, Free-Electron Laser experiments and a program on the development of high brightness electron beams. The AFT's experimental program commenced in early 1991 at an energy of about 4 MeV. The full program, with 50 MeV and the High power laser will begin operation this year. 28 refs., 4 figs

The DOE/EM facility transition program

International Nuclear Information System (INIS)

Bixby, W.

1994-01-01

The mission of EM-60 is to plan, implement, and manage receipt of surplus facilities resulting from downsizing of the DOE Weapons Complex facilities and DOE operating program offices to EM, and to ensure prompt deactivation of such facilities in order to reach a minimum surveillance and maintenance condition. The revised organizational structure of EM-60 into four offices (one at headquarters, and the other three at field sites), reflects increased operating functions associated with deactivation, surveillance, and maintenance of facilities. EM-60's deactivation and transition role concerns technical, socioeconomic, institutional, and administrative issues. The primary objective of the deactivation process is to put facilities in the lowest surveillance and maintenance condition safely and quickly by driving down the open-quotes mortgageclose quotes costs of maintaining them until final disposition. EM-60's three key activities are: (1) Inventory of surplus facilities - The 1993 Surplus Facility Inventory and Assessment (SFIA) serves as a planning tool to help the Department and EM-60 determine optimal transition phasing, with safety and cost-effectiveness remaining a priority. (2) Management of accelerated facility life cycle transition - Transitions currently underway illustrate site issues. These include addressing the interests of federal and state regulatory agencies as well as interests of local stakeholders, safe management of large amounts of production residues, and options for treatment, storage, transportation, and disposal. Of equal importance in the transition process is planning the optimal transition of the labor force. (3) Economic development - to address the socio-economic impacts on affected communities of the severe and rapid downsizing of the DOE Weapons Complex, DOE is pursuing an approach that uses the land, equipment, technology assets, and highly skilled local workforces as a basis for alternative economic development

Seismic qualification program plan for continued operation at DOE-SRS nuclear material processing facilities

International Nuclear Information System (INIS)

Talukdar, B.K.; Kennedy, W.N.

1991-01-01

The Savannah River Facilities for the most part were constructed and maintained to standards that were developed by Du Pont and are not rigorously in compliance with the current General Design Criteria (GDC); DOE Order 6430.IA requirements. In addition, many of the facilities were built more than 30 years ago, well before DOE standards for design were issued. The Westinghouse Savannah River Company (WSRC) his developed a program to address the evaluation of the Nuclear Material Processing (NMP) facilities to GDC requirements. The program includes a facility base-line review, assessment of areas that are not in compliance with the GDC requirements, planned corrective actions or exemptions to address the requirements, and a safety assessment. The authors from their direct involvement with the Program, describe the program plan for seismic qualification including other natural phenomena hazards,for existing NMP facility structures to continue operation Professionals involved in similar effort at other DOE facilities may find the program useful

Self-imposed self-assessment program at a DOE Nuclear Facility

International Nuclear Information System (INIS)

Geoffrion, R.R.; Loud, J.J.; Walter, E.C.

1996-01-01

The Nuclear Materials and Technology (NMT) Division at Los Alamos National Laboratory (LANL) has implemented a performance-based self-assessment program at the TA-55 plutonium facility. The program was conceptualized and developed by LANL's internal assessment group, AA-2. The management walkaround program fosters continuous improvement in NMT products and performance of its activities. The program, based on experience from the Institute of Nuclear Power Operations, is endorsed at the site by the U.S. Department of Energy (DOE) Environment, Safety, and Health (ES ampersand H) personnel and by the Defense Nuclear Facility Safety Board. The self-assessment program focuses on how work is actually performed rather than on paperwork or process compliance. Managers critically and continually assess ES ampersand H, conduct of operations, and other functional area requirements

49 CFR 37.61 - Public transportation programs and activities in existing facilities.

Science.gov (United States)

2010-10-01

... 49 Transportation 1 2010-10-01 2010-10-01 false Public transportation programs and activities in... TRANSPORTATION SERVICES FOR INDIVIDUALS WITH DISABILITIES (ADA) Transportation Facilities § 37.61 Public transportation programs and activities in existing facilities. (a) A public entity shall operate a designated...

Developing a model lifeline protection program for DOE facilities

International Nuclear Information System (INIS)

Lowing, A.N.

1996-01-01

A National Lifeline Standard Development Program is currently being conducted by FEMA and NIST. The Department of Energy is following these developments and supplementing them to meet Life-Safety and mission requirements for all DOE facilities as part of the Natural Phenomena Hazards Mitigation Plan. The task will be overseen by a DOE management team with technical guidance provided by a Steering Group of management and operating contractor representatives. The DOE will participate in the federal program by conducting a workshop on lifeline protection issues, developing an overall plan, organizing a Steering Group, and conducting a pilot study at a DOE facility

Clinton P. Anderson Meson Physics Facility and its operational safety program

International Nuclear Information System (INIS)

Putnam, T.M.

1975-01-01

The Clinton P. Anderson Meson Physics Facility (LAMPF) at the Los Alamos Scientific Laboratory consists of/ (1) a medium-energy, high-intensity linear proton accelerator; (2) experimental areas designed to support a multidisciplined program of research and practical applications; and (3) support facilities for accelerator operations and the experimental program. The high-intensity primary and secondary beams at LAMPF and the varied research program create many interesting and challenging problems for the Health Physics staff. A brief overview of LAMPF is presented, and the Operational Safety Program is discussed, with emphasis on the radiological safety and health physics aspects

Surplus Facilities and Resource Conservation and Recovery Act Closure program plan, fiscal year 1992

International Nuclear Information System (INIS)

Hughes, M.C.; Wahlen, R.K.; Winship, R.A.

1991-10-01

The Surplus Facilities and Resource Conservation and Recovery Act Closure program is responsible to US Department of Energy Field Office, Richland for the safe, cost-effective surveillance, maintenance, and decommissioning of surplus facilities at the Hanford Site. The Surplus Facilities and Resource Conservation and Recovery Act Closure program is also responsible to US Department of Energy Field Office, Richland for the program management of specific Resource Conservation and Recovery Act closures at the Hanford Site. This program plan addresses only the surplus facilities. The criteria used to evaluate each factor relative to decommissioning are based on the guidelines presented by the US Department of Energy Field Office, Richland, Environmental Restoration Division. The guidelines are consistent with the Westinghouse Hanford Company commitment to decommission Hanford Site retired facilities in the safest and most cost-effective way achievable. This document outlines the plan for managing these facilities until disposal

75 FR 18850 - National Protection and Programs Directorate; Chemical Facility Anti-Terrorism Standards...

Science.gov (United States)

2010-04-13

... Directorate; Chemical Facility Anti-Terrorism Standards Personnel Surety Program AGENCY: National Protection...-terrorism Vulnerability Information (CVI), Sensitive Security Information (SSI), or Protected Critical... . SUPPLEMENTARY INFORMATION: Program Description The Chemical Facility Anti-Terrorism Standards (CFATS), 6 CFR...

Facility Decontamination and Decommissioning Program Surveillance and Maintenance Plan, Revision 2

Energy Technology Data Exchange (ETDEWEB)

Poderis, Reed J. [NSTec; King, Rebecca A. [NSTec

2013-09-30

This Surveillance and Maintenance (S&M) Plan describes the activities performed between deactivation and final decommissioning of the following facilities located on the Nevada National Security Site, as documented in the Federal Facility Agreement and Consent Order under the Industrial Sites program as decontamination and decommissioning sites: ? Engine Maintenance, Assembly, and Disassembly (EMAD) Facility: o EMAD Building (Building 25-3900) o Locomotive Storage Shed (Building 25-3901) ? Test Cell C (TCC) Facility: o Equipment Building (Building 25-3220) o Motor Drive Building (Building 25-3230) o Pump Shop (Building 25-3231) o Cryogenic Lab (Building 25-3232) o Ancillary Structures (e.g., dewars, water tower, piping, tanks) These facilities have been declared excess and are in various stages of deactivation (low-risk, long-term stewardship disposition state). This S&M Plan establishes and implements a solid, cost-effective, and balanced S&M program consistent with federal, state, and regulatory requirements. A graded approach is used to plan and conduct S&M activities. The goal is to maintain the facilities in a safe condition in a cost-effective manner until their final end state is achieved. This plan accomplishes the following: ? Establishes S&M objectives and framework ? Identifies programmatic guidance for S&M activities to be conducted by National Security Technologies, LLC, for the U.S. Department of Energy, National Nuclear Security Administration Nevada Field Office (NNSA/NFO) ? Provides present facility condition information and identifies hazards ? Identifies facility-specific S&M activities to be performed and their frequency ? Identifies regulatory drivers, NNSA/NFO policies and procedures, and best management practices that necessitate implementation of S&M activities ? Provides criteria and frequencies for revisions and updates ? Establishes the process for identifying and dispositioning a condition that has not been previously identified or

Education and training program for graduate school student with synchrotron radiation facility

International Nuclear Information System (INIS)

Harada, Isao; Ikeda, Naoshi; Yokoya, Takayoshi

2008-01-01

We report the education and training program for graduate students of Graduate School of Natural Science and Technology Okayama University made at synchrotron facilities, SPring-8 and HiSOR. This program is a joint course of graduate school lecture and synchrotron facility training with company researchers, that was authorized by the Ministry of Education, Culture, Sports, Science and Technology. The purpose of this program is the development of human resources who can understand the potential ability of synchrotron experiment. We report our plan and actual activity of the training program. (author)

Facilities Programming.

Science.gov (United States)

Bullis, Robert V.

1992-01-01

A procedure for physical facilities management written 17 years ago is still worth following today. Each of the steps outlined for planning, organizing, directing, controlling, and evaluating must be accomplished if school facilities are to be properly planned and constructed. However, lessons have been learned about energy consumption and proper…

Analysis of removal of residual decay heat from interim storage facilities by means of the CFD program FLUENT

International Nuclear Information System (INIS)

Stratmann, W.; Hages, P.

2004-01-01

Within the scope of nuclear licensing procedures of on-site interim storage facilities for dual purpose casks it is necessary, among other things, to provide proof of sufficient removal of the residual decay heat emitted by the casks. The results of the analyses performed for this purpose define e.g. the boundary conditions for further thermal analyses regarding the permissible cask component temperatures or the maximum permissible temperatures of the fuel cladding tubes of the fuel elements stored in the casks. Up to now, for the centralized interim storage facilities in Germany such analyses were performed on the basis of experimental investigations using scaled-down storage geometries. In the engineering phase of the Lingen on-site interim storage facility, proof was furnished for the first time using the CFD (computational fluid dynamics) program FLUENT. The program FLUENT is an internationally recognized and comprehensively verified program for the calculation of flow and heat transport processes. Starting from a brief discussion of modeling and the different boundary conditions of the computation, this contribution presents various results regarding the temperatures of air, cask surfaces and storage facility components, the mass flows through the storage facility and the heat transfer at the cask surface. The interface point to the cask-specific analyses is defined to be the cask surface

CEBAF [Continuous Electron Beam Accelerator Facility] scientific program

International Nuclear Information System (INIS)

Gross, F.

1986-01-01

The principal scientific mission of the Continuous Electron Beam Facility (CEBAF) is to study collective phenomena in cold (or normal) nucler matter in order to understand the structure and behavior of macroscopic systems constructed from nuclei. This document discusses in broad popular terms those issues which the CEBAF experimental and theoretical program are designed to address. Specific experimental programs currently planned for CEBAF are also reivewed. 35 refs., 19 figs

The role of SANRAD facility in quantitative and morphological investigation

International Nuclear Information System (INIS)

Nshimirimana, Robert; Beer, Frikkie de; Radebe, Mabuti

2011-01-01

The SANRAD (South African Neutron Radiography) facility hosts a neutron/X-ray tomography system, which is extensively being utilized in non-destructive examination experiments where it is necessary to determine the properties (e.g. size, porosity, permeability and morphology) of samples. Those properties have a great importance in a variety of fields such as nuclear shielding, paleontology, geosciences, anatomy and reverse engineering studies. Quantitative and morphological investigations require a tomography system capable of producing tomograms with a high spatial resolution and free of artefacts where specialized imaging software is applied in the investigations. The SANRAD facility is used by the scientific and engineering communities in their qualitative, quantitative and morphological investigations. The capability of the SANRAD facility to investigate qualitatively and quantitatively the internal structure of several objects non-destructively is demonstrated with special emphasis on the precision and accuracy of the system.

Test facility for investigation of heat transfer of promising coolants for the nuclear power industry

Science.gov (United States)

Belyaev, I. A.; Sviridov, V. G.; Batenin, V. M.; Biryukov, D. A.; Nikitina, I. S.; Manchkha, S. P.; Pyatnitskaya, N. Yu.; Razuvanov, N. G.; Sviridov, E. V.

2017-11-01

The results are presented of experimental investigations into liquid metal heat transfer performed by the joint research group consisting of specialist in heat transfer and hydrodynamics from NIU MPEI and JIHT RAS. The program of experiments has been prepared considering the concept of development of the nuclear power industry in Russia. This concept calls for, in addition to extensive application of water-cooled, water-moderated (VVER-type) power reactors and BN-type sodium cooled fast reactors, development of the new generation of BREST-type reactors, fusion power reactors, and thermonuclear neutron sources. The basic coolants for these nuclear power installations will be heavy liquid metals, such as lead and lithium-lead alloy. The team of specialists from NRU MPEI and JIHT RAS commissioned a new RK-3 mercury MHD-test facility. The major components of this test facility are a unique electrical magnet constructed at Budker Nuclear Physics Institute and a pressurized liquid metal circuit. The test facility is designed for investigating upward and downward liquid metal flows in channels of various cross-sections in a transverse magnetic field. A probe procedure will be used for experimental investigation into heat transfer and hydrodynamics as well as for measuring temperature, velocity, and flow parameter fluctuations. It is generally adopted that liquid metals are the best coolants for the Tokamak reactors. However, alternative coolants should be sought for. As an alternative to liquid metal coolants, molten salts, such as fluorides of lithium and beryllium (so-called FLiBes) or fluorides of alkali metals (so-called FLiNaK) doped with uranium fluoride, can be used. That is why the team of specialists from NRU MPEI and JIHT RAS, in parallel with development of a mercury MHD test facility, is designing a test facility for simulating molten salt heat transfer and hydrodynamics. Since development of this test facility requires numerical predictions and verification

Present status of ESNIT (energy selective neutron irradiation test facility) program

International Nuclear Information System (INIS)

Noda, K.; Ohno, H.; Sugimoto, M.; Kato, Y.; Matsuo, H.; Watanabe, K.; Kikuchi, T.; Sawai, T.; Usui, T.; Oyama, Y.; Kondo, T.

1994-01-01

The present status of technical studies of a high energy neutron irradiation facility, ESNIT (energy selective neutron irradiation test facility), is summarized. Technological survey and feasibility studies of ESNIT have continued since 1988. The results of technical studies of the accelerator, the target and the experimental systems in ESNIT program were reviewed by an International Advisory Committee in February 1993. Recommendations for future R and D on ESNIT program are also summarized in this paper. ((orig.))

Quality Assurance Program Plan (QAPP) Waste Encapsulation and Storage Facility (WESF)

International Nuclear Information System (INIS)

ROBINSON, P.A.

2000-01-01

This Quality Assurance Plan describes how the Waste Encapsulation and Storage Facility (WESF) implements the quality assurance (QA) requirements of the Quality Assurance Program Description (QAPD) (HNF-Mp-599) for Project Hanford activities and products. This QAPP also describes the organizational structure necessary to successfully implement the program. The QAPP provides a road map of applicable Project Hanford Management System Procedures, and facility specific procedures, that may be utilized by WESF to implement the requirements of the QAPD

I and C security program for nuclear facilities: implementation guide - TAFICS/IG/2

International Nuclear Information System (INIS)

2016-04-01

This is the second in a series of documents being developed by TAFICS for protecting computer-based I and C systems of Indian nuclear facilities from cyber attacks. The document provides guidance to nuclear facility management to establish, implement and maintain a robust I and C security program - consisting of security plan and a set of security controls. In order to provide a firm basis for the security program, the document also identifies the fundamental security principles and foundational security requirements related to computer-based I and C systems of nuclear facilities. It is recommended that all applicable Indian nuclear facilities should implement the security program - with required adaptation - so as to provide the necessary assurance that the I and C systems are adequately protected against cyber attacks. (author)

Radiation protection program at an accelerator facility complex

International Nuclear Information System (INIS)

Ramanuja, Jaya

2007-01-01

Broad aspects of Radiation Protection Program at the Tyco Healthcare/Mallinckrodt Inc. will be presented with emphasis on Occupational dose, Public dose and ALARA program. Regulatory requirements, compliance and radio nuclides of concern for external exposure and internal contamination will be discussed. The facility is subject to in depth annual inspections by the Nuclear Regulatory Commission (NRC) to ensure compliance with regulations and operating license requirements. The facility is required to have an emergency contingency plan in place. A simulated emergency drill scenario is witnessed and graded by the NRC and state inspectors, with full participation by the fire department and the local hospital. Radiation Safety Officer (RSO) is in charge of all radiological aspects of the facility, and reports to the plant manager directly. The RSO or any of his staff has the authority to stop a job if there is a radiological concern. The Radiation protection organization interfaces with Production, QA and Engineering and ensures there is no conflict with Industrial Safety, OSHA and FDA requirements. Any employee has the right to call the regulatory officials if he/she has a concern. Operational aspects of Radiation protection program such as radiological survey, contamination control and limits, air sample survey, radio active waste processing and record retention requirements are per plant procedures and regulatory requirements. Shielding and administrative requirements for designing a modification to an existing design or a new lab/hot cell is subject to in-depth review and approval by Radiation Safety Committee. Each department has a Dose Reduction Subcommittee which meets periodically to discuss if any changes in procedures or facility can be made to decrease the dose. The subcommittee also trends the dose to ensure it is trending downward. Even though 99 Mo/ 99m TC generators are manufactured at the facility, majority of the dose is from cyclotron maintenance

Phase II Investigation at the Former CCC/USDA Grain Storage Facility in Savannah, Missouri

Energy Technology Data Exchange (ETDEWEB)

LaFreniere, Lorraine M. [Argonne National Lab. (ANL), Argonne, IL (United States). Environmental Science Division. Applied Geosciences and Environmental Management Section

2012-05-01

contamination potentially associated with a number of former CCC/USDA grain storage facilities in Missouri. The site characterization at Savannah is being conducted on behalf of the CCC/USDA by the Environmental Science Division of Argonne National Laboratory. The investigation is being conducted in phases, so that information obtained and interpretations developed during each incremental stage can be used most effectively to guide subsequent phases of the program. Phase II objectives: Investigate the more detailed characteristics of groundwater flow in the vicinity of the former CCC/USDA facility and the contaminated Morgan and MoDOT private wells; Obtain additional information on the vertical and lateral distribution and concentrations of carbon tetrachloride in groundwater in the vicinity of the former CCC/USDA facility and the contaminated Morgan and MoDOT private wells; Investigate further for possible evidence of carbon tetrachloride in the subsurface (vadose zone) and deeper soils beneath the former CCC/USDA facility, as well as in the vicinity of the contaminated MoDOT private well.

Professional Development through Organizational Assessment: Using APPA's Facilities Management Evaluation Program

Science.gov (United States)

Medlin, E. Lander; Judd, R. Holly

2013-01-01

APPA's Facilities Management Evaluation Program (FMEP) provides an integrated system to optimize organizational performance. The criteria for evaluation not only provide a tool for organizational continuous improvement, they serve as a compelling leadership development tool essential for today's facilities management professional. The senior…

RCRA Facility Investigation/Remedial Investigation Report for the Grace Road Site (631-22G)

Energy Technology Data Exchange (ETDEWEB)

Palmer, E.

1998-10-02

This report summarizes the activities and documents the results of a Resource Conservation and Recovery Act Facility Investigation/Remedial Investigation conducted at Grace Road Site on the Savannah River Site near Aiken, South Carolina.

RCRA Facility Investigation/Remedial Investigation Report for the Grace Road Site (631-22G)

International Nuclear Information System (INIS)

Palmer, E.

1998-01-01

This report summarizes the activities and documents the results of a Resource Conservation and Recovery Act Facility Investigation/Remedial Investigation conducted at Grace Road Site on the Savannah River Site near Aiken, South Carolina

Horonobe Underground Research Laboratory project investigation program for the 2007 fiscal year (Translated document)

International Nuclear Information System (INIS)

Matsui, Hiroya; Nakayama, Masashi; Sanada, Hiroyuki; Yamaguchi, Takehiro

2008-09-01

As past of the research and development program on the geological disposal of high-level radioactive waste (HLW), the Horonobe Underground Research Center, a division of the Japan Atomic Energy Agency (JAEA), is implementing the Horonobe Underground Research Laboratory Project (Horonobe URL Project) with the aim at investigating sedimentary rock formations. According to the research plan described in the Midterm Plan of JAEA, geological investigations are to be carried out during the drilling of a shaft down to intermediate depth, while research and development in the areas of engineering technology and safety assessment are to be promoted by collaboration with other research organizations. The results of the R and D activities will be systematized as a 'knowledge base' that supports a wide range of arguments related to the safety of geological disposal. The Horonobe URL Project is planned to extend over a period of 20 years. The investigations will be conducted in three phases, namely 'Phase 1: Surface-based investigations', 'Phase 2: Construction phase' (investigations during construction of the underground facilities) and 'Phase 3: Operation phase' (research in the underground facilities). This report summarizes the investigation program for the 2007 fiscal year (2007/2008), the third year of the Phase 2 investigations. In the 2007 fiscal year, investigations in geoscientific research', including 'development of techniques for investigating the geological environment', 'development of techniques for use in the deep underground environment' and 'studies on the long-term stability of the geological environment', is continuously carried out. Investigations in 'research and development on geological disposal technology', including improving the reliability of disposal technologies' and 'enhancement of safety assessment methodologies' are also continuously carried out. Construction of the underground facilities is ongoing at the Ventilation Shaft and the East Shaft

Older Adult Participation in Health Promotion Programs: Perspectives of Facility Administrators

Science.gov (United States)

Wright, Tim; Hyner, Gerald C.

2011-01-01

Administrators of older adult-centered facilities must identify barriers to the planning and implementation of health promotion programs. In this qualitative research those barriers were identified through in-depth interviews with administrators of older adult-centered facilities. As identified by administrators, the predominant barriers to the…

200 area liquid effluent facility quality assurance program plan. Revision 1

International Nuclear Information System (INIS)

Sullivan, N.J.

1995-01-01

Direct revision of Supporting Document WHC-SD-LEF-QAPP-001, Rev. 0. 200 Area Liquid Effluent Facilities Quality Assurance Program Plan. Incorporates changes to references in tables. Revises test to incorporate WHC-SD-LEF-CSCM-001, Computer Software Configuration Management Plan for 200 East/West Liquid Effluent Facilities

200 Areas Remedial Investigation/Feasibility Study Implementation Plan - Environmental Restoration Program

International Nuclear Information System (INIS)

Knepp, A. J.

1999-01-01

The 200 Areas Remedial Investigation/Feasibility Study Implementation Plan - Environmental Restoration Program (Implementation Plan) addresses approximately 700 soil waste sites (and associated structures such as pipelines) resulting from the discharge of liquids and solids from processing facilities to the ground (e.g., ponds, ditches, cribs,burial grounds) in the 200 Areas and assigned to the Environmental Restoration Program. The Implementation Plan outlines the framework for implementing assessment activities in the 200 Areas to ensure consistency in documentation, level of characterization, and decision making. The Implementation Plan also consolidates background information and other typical work plan materials, to serve as a single referenceable source for this type of information

FAIR - Facility, Research Program and Status of the Project

International Nuclear Information System (INIS)

Majka, Z.

2011-01-01

The international Facility for Antiproton and Ion Research (FAIR) in Europe will provide a worldwide science community with a unique and technically innovative accelerator system to perform forefront research in the sciences concerned with the basic structure of matter, and in intersections with other fields. The facility will deliver an extensive range of primary and secondary particle beams from protons and their antimatter partners, antiprotons, to ion beams of all chemical elements up to the heaviest, uranium, with in many respects unique properties and intensities. The paper will include overview of the new facility design and research programs to be carried out there. The current status of the FAIR project will be also presented. (author)

Status of site investigation for L/ILW facilities in the Philippines - 59262

International Nuclear Information System (INIS)

Palattao, Maria V.; Nohay, Carl; Reyes, Rolando; Singayan, Alfonso; Mallants, Dirk

2012-01-01

Document available in abstract form only. Full text of publication follows: Radioactive waste in the Philippines is generated from the various applications of radioactive materials in medicine, industries and research. The Philippine Nuclear Research Institute (PNRI) currently manages these wastes through its centralized treatment and storage facilities on site. Radioactive wastes that are received at the Institute are of different types ranging from contaminated solid and liquid materials to spent sealed sources, including radium. Treated and conditioned wastes are temporarily stored in simple roofed above ground concrete bunkers. The Philippine government through the Inter-agency Subcommittee on Radioactive Waste Management is committed to the development of a national repository for the country's radioactive waste. This policy has been recognized in spite of the relatively small volume of radioactive waste compared with countries that have a nuclear power program. To date, a potential site has been identified for detailed investigation with the assistance of the International Atomic Energy Agency (IAEA). The site is located in the northern part of the Philippine archipelago and has about 34 hectares for potential development. A drilling program that aimed to investigate the geologic, hydrogeologic and hydrologic properties of the site has been implemented

Use of the UFTR facilities for precollege nuclear education programs

International Nuclear Information System (INIS)

Vernetson, W.G.

1992-01-01

The University of Florida Training Reactor (UFTR) is a 100-kW light water-cooled, graphite- and light water-moderated modified Argonaut-type reactor, which currently utilizes high enriched (93%) fuel. Since first being licensed to operate at 10 kW in 1959, this facility has had major involvement in college and university level education and research programs both at the University of Florida and at other post-secondary schools around the state of Florida. Utility operator training programs were also a major facility involvement until recent years when the advent of site-specific simulators reduced UFTR usage for such training. Although sometimes not user friendly for innovative research and maintenance programs, the UFTR is an excellent educational and training tool. Service work for outside vendors representing a full spectrum of the nuclear industry has also been significant, especially in the last 15 yr. In contrast, there was little UFTR involvement in precollege education programs prior to 1984. Since that time, the US Dept. of Energy's University Reactor Sharing Program has been a catalyst for developing diverse utilization of the UFTR by both outside educational institutions throughout the state of Florida and faculty members within the University of Florida. With a decline in usage in the early 1980s, the UFTR was in danger of going the way of so many university reactor facilities. The availability of the Reactor Sharing Program has contributed significantly to educational and research opportunities at all levels around the state. Initially, those uses were almost exclusively at the college level. However, the synergistic effects of the internal and external user communities are primarily responsible for the resurgence in usage of the UFTR over the past 8 yr, despite a steady decline in utility operator training

Environmental, economic, and energy impacts of material recovery facilities. A MITE Program evaluation

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-10-01

This report documents an evaluation of the environmental, economic, and energy impacts of material recovery facilities (MRFs) conducted under the Municipal Solid Waste Innovative Technology Evaluation (MITE) Program. The MITE Program is sponsored by the US Environmental Protection Agency to foster the demonstration and development of innovative technologies for the management of municipal solid waste (MSW). This project was also funded by the National Renewable Energy Laboratory (NREL). Material recovery facilities are increasingly being used as one option for managing a significant portion of municipal solid waste (MSW). The owners and operators of these facilities employ a combination of manual and mechanical techniques to separate and sort the recyclable fraction of MSW and to transport the separated materials to recycling facilities.

LBM program at the LOTUS facility

International Nuclear Information System (INIS)

File, J.; Haldy, P.A.; Jassby, D.L.; Leo, W.R.; Tsang, F.Y.

1986-01-01

The Ecole Polytechnique Federale de Lausanne's (EPFL's) LOTUS facility in Lausanne, Switzerland, consists of a point-neutron deuterium-tritium (D-T) source in a shielded room designed specifically for neutronics experiments with fusion blanket modules. In 1985 the Electric Power Research Institute and EPFL initiated an experimental neutron transport program using irradiation of the Lithium Blanket Module (LBM) by the LOTUS neutron source. The principal objectives of this program are: (a) to test the capability of present-day neutron transport codes to predict the neutronic performance, including tritium breeding, of a reactor-representative blanket module in a relatively simple fast-neutron field and (b) to develop and verify the measurement and data processing procedures that will be used eventually with the LBM experiments at the Tokamak Fusion Test Reactor (TFTR) at Princeton Plasma Physics Lab. (PPPL)

Training and research reactor facility longevity extension program

International Nuclear Information System (INIS)

Carriveau, G.W.

1991-01-01

Since 1943, over 550 training and research reactors have been in operation. According to statistics from the International Atomic Energy Agency, ∼325 training and research reactors are currently in service. This total includes a wide variety of designs covering a range of power and research capabilities located virtually around the world. A program has been established at General Atomics (GA) that is dedicated to the support of extended longevity of training and research reactor facilities. Aspects of this program include the following: (1) new instrumentation and control systems; (2) improved and upgraded nuclear monitoring and control channels; (3) facility testing, repair and upgrade services that include (a) pool or tank integrity, (b) cooling system, and (c) water purification system; (4) fuel element testing procedures and replacement; (5) control rod drive rebuilding and upgrades; (6) control and monitoring system calibration and repair service; (7) training services, including reactor operations, maintenance, instrumentation calibration, and repair; and (8) expanded or new uses such as neutron radiography and autoradiography, isotope production, nuclear medicine, activation analysis, and material properties modification

Intense neutron source facility for the fusion energy program

International Nuclear Information System (INIS)

Armstrong, D.D.; Emigh, C.R.; Meier, K.L.; Meyer, E.A.; Schneider, J.D.

1975-01-01

The intense neutron source is based on the ability of a supersonic flow of gas to dissipate an enormous quantity of heat generated in the neutron-producing target by multiple Coulomb collisions. A description is given of the principles involved in forming the supersonic jet, in forming the intense tritium-ion beam, in the vacuum systems, and in the tritium handling systems. An overview of the entire facility is included. It is believed that the facility can be operated with high reliability, ensuring a productive radiation damage program. (U.S.)

Working program for deep borehole investigations. HDB-6,7,8, borehole

International Nuclear Information System (INIS)

Hama, Katsuhiro; Takahashi, Kazuharu; Ishii, Eiichi; Takeuchi, Ryuji; Sasaki, Manabu; Kunimaru, Takanori; Eki, Nobuhiro; Matsui, Hiroya

2003-08-01

In the Horonobe Underground Research Laboratory project, a wide range of geoscientific research and development activities are planned to be performed in three phases, Surface-based Investigations (Phase I), Construction (Phase II) and Operations (Phase III), over period of 20 years. Surface-based investigations have been conducted since 2000. Main goals of the Horonobe project are; To establish comprehensive techniques for investigating the geological environment, and To develop a range of engineering techniques for deep underground applications. The specific goals of the surface-based investigations are, To construct geological models of the geological environment based on the surface-based investigations and develop an understanding of the deep geological environment (undisturbed, initial conditions) before excavation of the shaft and experimental drifts To formulate detailed design and plans for the construction of the shaft and experimental drifts, and To plan scientific investigations during the construction phase. Field investigations during the surface-based investigations phase are planned for completion by the end of 2005, with excavation of the main shaft, Phase 2 construction, planned to start in 2005. The diameter of the main shafts has provisionally been set at 6.5 meters and the proposed depth is 500 meters. Details of the geometry and depth of specific underground facilities, including the main shaft, the ventilation shaft and the drifts, will be defined using data on the geological environment obtained during the surface-based investigation phase. As part of the surface-based investigations, geological, geophysical, hydrogeological, hydrochemical and rock mechanical investigations were carried out. Deep borehole investigations started in 2000 in order to characterize the sedimentary rocks. Taking into account the status of the investigations as of April 2003 and the remaining time (i.e., three year) for the surface-based investigations, an

Full-scale mark II CRT program facility description report

International Nuclear Information System (INIS)

Namatame, Ken; Kukita, Yutaka; Ito, Hideo; Yamamoto, Nobuo; Shiba, Masayoshi

1980-03-01

Started in fiscal year 1977, the Full-Scale Mark II CRT (Containment Response Test) Program is proceeding for the period of five years. The primary objective of the CRT Program is to provide a data base for evaluation of the pressure suppression pool hydrodynamic loads associated with a postulated loss-of-coolant accident in the BWR Mark II containment system. The test facility was designed and constructed from fiscal year 1977 to 1978, and completed in March 1979. It is 1/18 in volume and has a wetwell which is a full-scale replica of one 20 0 -sector of that of a reference Mark II. This report describes design concepts, dimensions and constructions of the test facility, as well as specifications, locations and installation schemes of the measuring equipments. Results of soil structure inspection, vacuum breaker test and shaker test of the containment shell are given in the appendices. (author)

Canadian development program for off-gas management in nuclear facilities

International Nuclear Information System (INIS)

Sridhar, T.S.

1983-01-01

The Canadian program for the development and evaluation of processes and technology for the separation and containment of radioactive species in off-gases is directed towards the following specific aspects: 1) assessment of available treatment technology and evaluation of future clean-up requirements; 2) development and engineering evaluation, under realistic conditions, of promising new processes that would be inherently simpler and safer; and 3) specification of off-gas emission control systems for future nuclear facilities based on the most favourable technology. The program is being carried out by Atomic Energy of Canada Limited in collaboration with the electrical utility, Ontario Hydro, and selected Canadian universities. A brief description is presented of methods for removing tritium and carbon-14 from the moderator systems of CANDU power reactors, methods for removing iodine from the off-gases of a molybdenum-99 production facility at the Chalk River Nuclear Laboratories, and procedures for monitoring the off-gas effluent composition in the Thorium Fuel Reprocessing Experiment (TFRE) facility at the Whiteshell Nuclear Research Establishment

Design and first integral test of MUSE facility in ALPHA program

Energy Technology Data Exchange (ETDEWEB)

Park, Hyun-sun; Yamano, Norihiro; Maruyama, Yu; Moriyama, Kiyofumi; Kudo, Tamotsu; Yang, Yanhua; Sugimoto, Jun [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

1998-03-01

Vapor explosion (Steam explosion or energetic Fuel-Coolant Interaction) is a phenomenon in which a hot liquid rapidly releases its internal energy into a surrounding colder and more volatile liquid when these liquids come into a sudden contact. This rapid energy release leads to rapid vapor production within a timescale short compared to vapor expansion causes local pressurization similar to an explosion and eventually threatens the surroundings by dynamic pressures and the subsequent expansion. It has been recognized that the energetics of vapor explosions strongly depend on the initial mixing geometry established by the contact of hot and cold liquids. Therefore, a new program has been initiated to investigate the energetics of vapor explosions in various contact geometries; i.e., pouring, stratified, coolant and melt injection modes in a facility which is able to measure the energy conversion ratio and eventually to provide data to evaluate the mechanistic analytical models. In the report, this new facility, called MUSE (MUlti-configuration in Steam Explosions), and the results of the first integral test are described in detail. (author)

BROOKHAVEN NATIONAL LABORATORY INSTRUMENTATION DIVISION, R AND D PROGRAMS, FACILITIES, STAFF

International Nuclear Information System (INIS)

INSTRUMENTATION DIVISION STAFF

1999-01-01

To develop state-of-the-art instrumentation required for experimental research programs at BNL, and to maintain the expertise and facilities in specialized high technology areas essential for this work. Development of facilities is motivated by present BNL research programs and anticipated future directions of BNL research. The Division's research efforts also have a significant impact on programs throughout the world that rely on state-of-the-art radiation detectors and readout electronics. Our staff scientists are encouraged to: Become involved in challenging problems in collaborations with other scientists; Offer unique expertise in solving problems; and Develop new devices and instruments when not commercially available. Scientists from other BNL Departments are encouraged to bring problems and ideas directly to the Division staff members with the appropriate expertise. Division staff is encouraged to become involved with research problems in other Departments to advance the application of new ideas in instrumentation. The Division Head integrates these efforts when they evolve into larger projects, within available staff and budget resources, and defines the priorities and direction with concurrence of appropriate Laboratory program leaders. The Division Head also ensures that these efforts are accompanied by strict adherence to all ES and H regulatory mandates and policies of the Laboratory. The responsibility for safety and environmental protection is integrated with supervision of particular facilities and conduct of operations

BROOKHAVEN NATIONAL LABORATORY INSTRUMENTATION DIVISION, R AND D PROGRAMS, FACILITIES, STAFF.

Energy Technology Data Exchange (ETDEWEB)

INSTRUMENTATION DIVISION STAFF

1999-06-01

To develop state-of-the-art instrumentation required for experimental research programs at BNL, and to maintain the expertise and facilities in specialized high technology areas essential for this work. Development of facilities is motivated by present BNL research programs and anticipated future directions of BNL research. The Division's research efforts also have a significant impact on programs throughout the world that rely on state-of-the-art radiation detectors and readout electronics. Our staff scientists are encouraged to: Become involved in challenging problems in collaborations with other scientists; Offer unique expertise in solving problems; and Develop new devices and instruments when not commercially available. Scientists from other BNL Departments are encouraged to bring problems and ideas directly to the Division staff members with the appropriate expertise. Division staff is encouraged to become involved with research problems in other Departments to advance the application of new ideas in instrumentation. The Division Head integrates these efforts when they evolve into larger projects, within available staff and budget resources, and defines the priorities and direction with concurrence of appropriate Laboratory program leaders. The Division Head also ensures that these efforts are accompanied by strict adherence to all ES and H regulatory mandates and policies of the Laboratory. The responsibility for safety and environmental protection is integrated with supervision of particular facilities and conduct of operations.

Atomics International fuel fabrication facility and low enrichment program [contributed by T.A. Moss, AI

International Nuclear Information System (INIS)

Moss, T.A.

1993-01-01

The AI facility is approximately 30,000 square feet in area and consists of four general areas. One area is devoted to the production of UAl x powder. It consists of a series of arc melting furnaces, crushing lines, glove boxes, and compacting presses. The second area is used for the rolling of fuel plates. The third area is used for the machining of the plates to final size and also the machining of the fuel elements. In the fourth area the fuel plates are swaged into assemblies, and all welding and inspection operations are performed. As part of the lower enrichment program we are scheduled to put a second UAl x powder line into operation and we have had to expand some of our storage area. Under the low enrichment program the AI fuel facility will be modified to accommodate a separate low enrichment Al x production line and compacting line. This facility modification should be done by the end of the fiscal year. We anticipate producing fuel with an enrichment slightly less than 20% We anticipate powder being available for plate production shortly after the facility is completed. Atomics International is scheduled to conduct plate LEU verification work using fully enriched material in the June-July time period, at which time we will investigate what level of uranium loadings we can go to using the current process. It is anticipated that 55 volume percent uranium compound in our fuel form can be achieved

Program of radiological monitoring environmental a nuclear facility in latency

International Nuclear Information System (INIS)

Blas, A. de; Riego, A.; Batalla, E.; Tapia, C.; Garcia, R.; Sanchez, J.; Toral, J.

2013-01-01

This paper presents the Radiological Environmental Monitoring program of the Vandellos I nuclear power plant in the latency period. This facility was dismantled to level 2, as defined by the International Atomic Energy Agency. The program is an adaptation of the implanted one during the dismantling, taking into account the isotopes that may be present, as well as the main transfer routes. Along with the description of the program the results obtained in the latent period from 2005 until 2012 are presented.

Status of the Tau-Charm Facility and highlights of its physics program

International Nuclear Information System (INIS)

Schindler, R.H.

1990-02-01

In this paper I will first discuss the history and current status of the Tau-Charm Facility. I will then focus on the unique aspects of the heavy meson and tau physics program of such a facility, which motivates its construction and operation in the mid-1090's

Review of the Advanced Toroidal Facility program

International Nuclear Information System (INIS)

Lyon, J.F.; Murakami, M.

1987-01-01

This report summarizes the history and design goals of the Advanced Toroidal Facility (ATF). The ATF is nearing completion at ORNL with device completion expected in May 1987 and first useful plasma operation in June/July 1987. ATF is a moderate-aspect-ratio torsatron, the world's largest stellarator facility with R = 2.1 m, α bar = 0.3 m and B = 2 T (5-s pulse) or 1 T (steady-state capability). It has been specifically designed to support the US tokamak program by studying important toroidal confinement issues in a similar magnetic geometry that allows external control of the magnetic configuration properties and their radial profiles: transform, shear, well depth, shaping, axis topology, etc. ATF will operate in a current-free model which allows separation of current-driven and pressure-driven plasma behavior. It also complements the world stellarator program in its magnetic configuration (between Heliotron-E and W VII-AS) and its capabilities (large size, good access, steady state capability, second stability access, etc.). For both roles ATF will require high-power long-pulse heating to carry out its physics goals since the high power NBI pulse is limited to 0.3 s. The ATF program focuses on demonstrating the principles of high-beta, steady-state operation in toroidal geometry through its study of: (1) scaling of beta limits with magnetic configuration properties and the plasma behavior in the second stability regime; (2) transport scaling at low collisionality and the role/control of electric field; (3) control of plasma density and impurities using divertors; (4) plasma heating with NBI, ECH, ICH, and plasma fueling with gas puffing and pellet injection; and (5) optimization of the magnetic configuration

Safety Assessment for LILW Near-Surface Disposal Facility Using the IAEA Reference Model and MASCOT Program

International Nuclear Information System (INIS)

Kim, Hyun Joo; Park, Joo Wan; Kim, Chang Lak

2002-01-01

A reference scenario of vault safety case prepared by the IAEA for the near-surface disposal facility of low-and intermediate-level radioactive wastes is assessed with the MASCOT program. The appropriate conceptual models for the MASCOT implementation is developed. An assessment of groundwater pathway through a drinking well as a geosphere-biosphere interface is performed first, then biosphere pathway is analysed to estimate the radiological consequences of the disposed radionuclides based on compartment modeling approach. The validity of conceptual modeling for the reference scenario is investigated where possible comparing to the results generated by the other assessment. The result of this study shows that the typical conceptual model for groundwater pathway represented by the compartment model can be satisfactorily used for safety assessment of the entire disposal system in a consistent way. It is also shown that safety assessment of a disposal facility considering complex and various pathways would be possible by the MASCOT program

25 CFR Appendix A to Subpart G - List of Activities Eligible for Funding Under BIA Transportation Facility Maintenance Program

Science.gov (United States)

2010-04-01

... Transportation Facility Maintenance Program A Appendix A to Subpart G Indians BUREAU OF INDIAN AFFAIRS, DEPARTMENT OF THE INTERIOR LAND AND WATER INDIAN RESERVATION ROADS PROGRAM BIA Road Maintenance Pt. 170... Transportation Facility Maintenance Program The following activities are eligible for BIA Transportation Facility...

PWR blowdown heat transfer separate-effects program: thermal-hydraulic test facility experimental data report for test 104

International Nuclear Information System (INIS)

Leon, D.M.; White, M.D.; Moore, P.A.; Hedrick, R.A.

1978-01-01

Reduced instrument responses are presented for Thermal-Hydraulic Test Facility (THTF) test 104, which is part of the ORNL Pressurized-Water Reactor (PWR) Blowdown Heat Transfer Separate-Effects Program. The objective of the program is to investigate the thermal-hydraulic phenomenon governing the energy transfer and transport processes that occur during a loss-of-coolant accident in the PWR system. Test 104 was conducted to obtain CHF in bundle 1 under blowdown conditions. The primary purpose of this report is to make the reduced instrument responses during test 104 available

Gas storage facilities. Investigation of their social value

International Nuclear Information System (INIS)

1997-02-01

The socio-economic factors resulting from location of gas storage facilities are evaluated. Various alternatives to the existing projects are estimated, for instance 11 new pipelines, in some cases combined with new production capacity, LNG facilities, differentiated tariffs, reconstruction of decentralized heat/power plants etc. Theoretical considerations and models, among others involving gas storage abroad, are presented. Seasonal storage, emergency storage, storage controlled by economic optimization (profitable purchases, sales at highest market) are described for various types of facilities, like aquifers, caverns and LNG-stores. Natural gas supplies in Europe, infrastructure and resources are compared to the Danish conditions. Sensitivity of the Danish heating market for natural gas consumption is investigated. Reduction in energy use for space heating by 2005 will change the needs of storage of 740 Mm 3 gas to 650 Mm 3 . Extra consumption by the decentralized power/heat plants is not accounted for in this estimation. Dynamic models of the future gas consumption are based on the EU 'European Energy 2020'. (EG)

Radiation safety program in a high dose rate brachytherapy facility

International Nuclear Information System (INIS)

Rodriguez, L.V.; Hermoso, T.M.; Solis, R.C.

2001-01-01

The use of remote afterloading equipment has been developed to improve radiation safety in the delivery of treatment in brachytherapy. Several accidents, however, have been reported involving high dose-rate brachytherapy system. These events, together with the desire to address the concerns of radiation workers, and the anticipated adoption of the International Basic Safety Standards for Protection Against Ionizing Radiation (IAEA, 1996), led to the development of the radiation safety program at the Department of Radiotherapy, Jose R. Reyes Memorial Medical Center and at the Division of Radiation Oncology, St. Luke's Medical Center. The radiation safety program covers five major aspects: quality control/quality assurance, radiation monitoring, preventive maintenance, administrative measures and quality audit. Measures for evaluation of effectiveness of the program include decreased unnecessary exposures of patients and staff, improved accuracy in treatment delivery and increased department efficiency due to the development of staff vigilance and decreased anxiety. The success in the implementation required the participation and cooperation of all the personnel involved in the procedures and strong management support. This paper will discuss the radiation safety program for a high dose rate brachytherapy facility developed at these two institutes which may serve as a guideline for other hospitals intending to install a similar facility. (author)

Dosimetry program for characterization of the FMIT facility

International Nuclear Information System (INIS)

Gold, R.; McElroy, W.N.; Fuller, J.L.; Sheen, E.M.; Dierckx, R.

1979-01-01

The environmental characterization program for the Fusion Materials Irradiaton Test (FMIT) facility is presented. Requirements for the development and testing of Magnetic Fusion Energy (MFE) materials together with the complexity of the FMIT (d,Li) generated radiation field warrant a multifaceted dosimetric approach. Specific passive, active and calculational dosimetry efforts comprising this multifaceted approach are described. Special emphasis is given to those dosimetry capabilities uniquely required to characterize FMIT

Sandia National Laboratories support of the Iraq Nuclear Facility Dismantlement and Disposal Program.

Energy Technology Data Exchange (ETDEWEB)

Cochran, John Russell; Danneels, Jeffrey John

2009-03-01

Because of past military operations, lack of upkeep and looting there are now enormous radioactive waste problems in Iraq. These waste problems include destroyed nuclear facilities, uncharacterized radioactive wastes, liquid radioactive waste in underground tanks, wastes related to the production of yellow cake, sealed radioactive sources, activated metals and contaminated metals that must be constantly guarded. Iraq currently lacks the trained personnel, regulatory and physical infrastructure to safely and securely manage these facilities and wastes. In 2005 the International Atomic Energy Agency (IAEA) agreed to organize an international cooperative program to assist Iraq with these issues. Soon after, the Iraq Nuclear Facility Dismantlement and Disposal Program (the NDs Program) was initiated by the U.S. Department of State (DOS) to support the IAEA and assist the Government of Iraq (GOI) in eliminating the threats from poorly controlled radioactive materials. The Iraq NDs Program is providing support for the IAEA plus training, consultation and limited equipment to the GOI. The GOI owns the problems and will be responsible for implementation of the Iraq NDs Program. Sandia National Laboratories (Sandia) is a part of the DOS's team implementing the Iraq NDs Program. This report documents Sandia's support of the Iraq NDs Program, which has developed into three principal work streams: (1) training and technical consultation; (2) introducing Iraqis to modern decommissioning and waste management practices; and (3) supporting the IAEA, as they assist the GOI. Examples of each of these work streams include: (1) presentation of a three-day training workshop on 'Practical Concepts for Safe Disposal of Low-Level Radioactive Waste in Arid Settings;' (2) leading GOI representatives on a tour of two operating low level radioactive waste disposal facilities in the U.S.; and (3) supporting the IAEA's Technical Meeting with the GOI from April 21

Joint Assessment of ETRR-2 Research Reactor Operations Program, Capabilities, and Facilities

International Nuclear Information System (INIS)

Bissani, M; O'Kelly, D S

2006-01-01

A joint assessment meeting was conducted at the Egyptian Atomic Energy Agency (EAEA) followed by a tour of Egyptian Second Research Reactor (ETRR-2) on March 22 and 23, 2006. The purpose of the visit was to evaluate the capabilities of the new research reactor and its operations under Action Sheet 4 between the U.S. DOE and the EAEA, ''Research Reactor Operation'', and Action Sheet 6, ''Technical assistance in The Production of Radioisotopes''. Preliminary Recommendations of the joint assessment are as follows: (1) ETRR-2 utilization should be increased by encouraging frequent and sustained operations. This can be accomplished in part by (a) Improving the supply-chain management for fresh reactor fuel and alleviating the perception that the existing fuel inventory should be conserved due to unreliable fuel supply; and (b) Promulgating a policy for sample irradiation priority that encourages the use of the reactor and does not leave the decision of when to operate entirely at the discretion of reactor operations staff. (2) Each experimental facility in operation or built for a single purpose should be reevaluated to focus on those that most meet the goals of the EAEA strategic business plan. Temporary or long-term elimination of some experimental programs might be necessary to provide more focused utilization. There may be instances of emerging reactor applications for which no experimental facility is yet designed or envisioned. In some cases, an experimental facility may have a more beneficial use than the purpose for which it was originally designed. For example, (a) An effective Boron Neutron Capture Therapy (BNCT) program requires nearby high quality medical facilities. These facilities are not available and are unlikely to be constructed near the Inshas site. Further, the BNCT facility is not correctly designed for advanced research and therapy programs using epithermal neutrons. (b) The ETRR-2 is frequently operated to provide color-enhanced gemstones but is

Joint Assessment of ETRR-2 Research Reactor Operations Program, Capabilities, and Facilities

Energy Technology Data Exchange (ETDEWEB)

Bissani, M; O' Kelly, D S

2006-05-08

A joint assessment meeting was conducted at the Egyptian Atomic Energy Agency (EAEA) followed by a tour of Egyptian Second Research Reactor (ETRR-2) on March 22 and 23, 2006. The purpose of the visit was to evaluate the capabilities of the new research reactor and its operations under Action Sheet 4 between the U.S. DOE and the EAEA, ''Research Reactor Operation'', and Action Sheet 6, ''Technical assistance in The Production of Radioisotopes''. Preliminary Recommendations of the joint assessment are as follows: (1) ETRR-2 utilization should be increased by encouraging frequent and sustained operations. This can be accomplished in part by (a) Improving the supply-chain management for fresh reactor fuel and alleviating the perception that the existing fuel inventory should be conserved due to unreliable fuel supply; and (b) Promulgating a policy for sample irradiation priority that encourages the use of the reactor and does not leave the decision of when to operate entirely at the discretion of reactor operations staff. (2) Each experimental facility in operation or built for a single purpose should be reevaluated to focus on those that most meet the goals of the EAEA strategic business plan. Temporary or long-term elimination of some experimental programs might be necessary to provide more focused utilization. There may be instances of emerging reactor applications for which no experimental facility is yet designed or envisioned. In some cases, an experimental facility may have a more beneficial use than the purpose for which it was originally designed. For example, (a) An effective Boron Neutron Capture Therapy (BNCT) program requires nearby high quality medical facilities. These facilities are not available and are unlikely to be constructed near the Inshas site. Further, the BNCT facility is not correctly designed for advanced research and therapy programs using epithermal neutrons. (b) The ETRR-2 is frequently operated to

Thermohydraulic investigations of nuclear power facilities (to the 60-th anniversary of the First NPP start)

International Nuclear Information System (INIS)

Rachkov, V.I.; Efanov, A.D.; Zhukov, A.V.; Kalyakin, S.G.; Sorokin, A.P.

2014-01-01

The investigations conducting in SSC RF - IPPE are aimed to develop theory and create calculational programs which allow to obtain the detailed description of coolant velocity fields and temperatures in any channels and equipment units of nuclear power facilities. Specially developed sensors for measuring various parameters are used in the experiments. Mathematical models and numerical methods are generalized for description and numerical solution of compressible fluids, multiphase and multifluid systems. The programs which allow to determine hydrodynamic and thermotechnical characteristics with account for melting, solidification, boiling processes are established. The obtained data is the base for creating the two-phase media flow theory. The study of the processes of impurity formation, transport and precipitation in liquid metal coolants has been allowed to develop the methods of impurity mass transfer simulation in circuits. For solving the fast reactor safety problem the series of investigations on liquid metals physics, boiling and condensation have been carried out [ru

Shared use of school facilities with community organizations and afterschool physical activity program participation: a cost-benefit assessment.

Science.gov (United States)

Kanters, Michael A; Bocarro, Jason N; Filardo, Mary; Edwards, Michael B; McKenzie, Thomas L; Floyd, Myron F

2014-05-01

Partnerships between school districts and community-based organizations to share school facilities during afterschool hours can be an effective strategy for increasing physical activity. However, the perceived cost of shared use has been noted as an important reason for restricting community access to schools. This study examined shared use of middle school facilities, the amount and type of afterschool physical activity programs provided at middle schools together with the costs of operating the facilities. Afterschool programs were assessed for frequency, duration, and type of structured physical activity programs provided and the number of boys and girls in each program. School operating costs were used to calculate a cost per student and cost per building square foot measure. Data were collected at all 30 middle schools in a large school district over 12 months in 2010-2011. Policies that permitted more use of school facilities for community-sponsored programs increased participation in afterschool programs without a significant increase in operating expenses. These results suggest partnerships between schools and other community agencies to share facilities and create new opportunities for afterschool physical activity programs are a promising health promotion strategy. © 2014, American School Health Association.

Investigation of s stressed-strained state and optimization of the T-15 facility electromagnetic system design

International Nuclear Information System (INIS)

Vaulina, I.G.; Gusev, S.V.; Monoszon, N.A.; Sivkova, G.N.; Spirchenko, Yu.V.; Chvartatskij, R.V.; Churakov, G.F.

1982-01-01

The results of investigation of a stressed-strained state (SSS) of superconducting coils of toroidal field (TFSC) of the T-15 facility are presented. The TFSC SSS dependence on the forces acting in the coil plane is reduced to solving the plane problem of the elasticity theory. The problem is solved by the finite element method according to a specially developed program. The TFSC SSS dependence on the action of tilting forces is studied by the structural mechanics method. A refined rod theory taking into account shear strain of the rod cross-section in the direction perpendicular to its axis is used. A comparative analysis of different versions of the TFSC design is carried out. A TFSC design optimized over the SSS is chosen. It is used in constructing the electromagnetic system of the T-15 facility

Safety analysis report upgrade program at the Plutonium Facility, Los Alamos National Laboratory

International Nuclear Information System (INIS)

Pan, P.Y.

1993-01-01

Plutonium research and development activities have resided at the Los Alamos National Laboratory (LANL) since 1943. The function of the Plutonium Facility (PF-4) has been to perform basic special nuclear materials research and development and to support national defense and energy programs. The original Final Safety Analysis Report (FSAR) for PF-4 was approved by DOE in 1978. This FSAR analyzed design-basis and bounding accidents. In 1986, DOE/AL published DOE/AL Order 5481.1B, ''Safety Analysis and Review System'', as a requirement for preparation and review of safety analyses. To meet the new DOE requirements, the Facilities Management Group of the Nuclear Material Technology Division submitted a draft FSAR to DOE for approval in April 1991. This draft FSAR analyzed the new configurations and used a limited-scope probabilistic risk analysis for accident analysis. During the DOE review of the draft FSAR, DOE Order 5480.23 ''Nuclear Safety Analysis Reports'', was promulgated and was later officially released in April 1992. The new order significantly expands the scope, preparation, and maintenance efforts beyond those required in DOE/AL Order 5481.1B by requiring: description of institutional and human-factor safety programs; clear definitions of all facility-specific safety commitments; more comprehensive and detailed hazard assessment; use of new safety analysis methods; and annual updates of FSARs. This paper describes the safety analysis report (SAR) upgrade program at the Plutonium Facility in LANL. The SAR upgrade program is established to meet the requirements in DOE Order 5480.23. Described in this paper are the SAR background, authorization basis for operations, hazard classification, and technical program elements

Radiologic safety program for ionizing radiation facilities in Parana, Brazil

International Nuclear Information System (INIS)

Schmidt, M.F.S.; Tilly Junior, J.G.

1997-01-01

A radiologic safety program for inspection, licensing and control of the use of ionizing radiation in medical, industrial and research facilities in Parana, Brazil is presented. The program includes stages such as: 1- division into implementation phases considering the activity development for each area; 2-use of the existing structure to implement and to improve services. The development of the program will permit to evaluate the improvement reached and to correct operational strategic. As a result, a quality enhancement at the services performed, a reduction for radiation dose exposure and a faster response for emergency situations will be expected

Decommissioning high-level waste surface facilities

International Nuclear Information System (INIS)

1978-04-01

The protective storage, entombment and dismantlement options of decommissioning a High-Level Waste Surface Facility (HLWSF) was investigated. A reference conceptual design for the facility was developed based on the designs of similar facilities. State-of-the-art decommissioning technologies were identified. Program plans and cost estimates for decommissioning the reference conceptual designs were developed. Good engineering design concepts were on the basis of this work identified

Spent Fuel Handling and Packaging Program: a survey of hot cell facilities

International Nuclear Information System (INIS)

Menon, M.N.

1978-07-01

Hot cell facilities in the United States were surveyed to determine their capabilities for conducting integral fuel assembly and individual fuel rod examinations that are required in support of the Spent Fuel Handling and Packaging Program. The ability to receive, handle, disassemble and reconstitute full-length light water reactor spent fuel assemblies, and the ability to conduct nondestructive and destructive examinations on full-length fuel rods were of particular interest. Three DOE-supported facilities and three commercial facilities were included in the survey. This report provides a summary of the findings

Forensic investigation of suicide cases in major Greek correctional facilities.

Science.gov (United States)

Sakelliadis, E I; Vlachodimitropoulos, D G; Goutas, N D; Panousi, P I; Logiopoulou, A-P I; Delicha, E M; Spiliopoulou, C A

2013-11-01

According to Greek legislation the medico-legal investigation of deaths occurring in prisons is mandatory. Furthermore, in cases of suicide or of suspected suicide the contribution of medico-legal investigation is of grave importance. The current paper addresses the medico-legal investigation of suicide cases in Greek correctional facilities and aims to describe the current situation. Our study consists of the meticulous research in the data records of major Greek correctional facilities, for the time period 1999-2010. Official permission was obtained by the Hellenic Ministry of Justice, which provided us the access to the records. Data was also collected from the Piraeus Forensic Service, from the Department of Pathological Anatomy of the University of Athens and finally from our own records. Measures were taken to respect the anonymity of the cases. Data was collected for the social, penal, medical history as well as for the medico-legal investigation. It appears that 85.7% of suicide cases were transferred to the Prisoner's Hospital (p < 0.0001), the forensic pathologist who conducted the PME did not perform scene investigation in none of the 70 suicide cases. In a total of 70 cases, histopathological examination, was requested only in 30 cases (42.9%). Hanging was the preferred method for those who committed suicide, followed by the poisoning due to psychoactive substances. Understanding the mistakes made during the forensic investigation of suicide cases inside correctional facilities is necessary, in order to prevent them from occurring again in the future, by implementing appropriate new policies and guidelines. Crown Copyright © 2013. Published by Elsevier Ltd. All rights reserved.

Practical approaches to implementing facility wide equipment strengthening programs

International Nuclear Information System (INIS)

Kincaid, R.H.; Smietana, E.A.

1989-01-01

Equipment strengthening programs typically focus on components required to ensure operability of safety related equipment or to prevent the release of toxic substances. Survival of non-safety related equipment may also be crucial to ensure rapid recovery and minimize business interruption losses. Implementing a strengthening program for non-safety related equipment can be difficult due to the large amounts of equipment involved and limited budget availability. EQE has successfully implemented comprehensive equipment strengthening programs for a number of California corporations. Many of the lessons learned from these projects are applicable to DOE facilities. These include techniques for prioritizing equipment and three general methodologies for anchoring equipment. Pros and cons of each anchorage approach are presented along with typical equipment strengthening costs

Medicare Program; Prospective Payment System and Consolidated Billing for Skilled Nursing Facilities for FY 2018, SNF Value-Based Purchasing Program, SNF Quality Reporting Program, Survey Team Composition, and Correction of the Performance Period for the NHSN HCP Influenza Vaccination Immunization Reporting

Science.gov (United States)

2017-08-04

This final rule updates the payment rates used under the prospective payment system (PPS) for skilled nursing facilities (SNFs) for fiscal year (FY) 2018. It also revises and rebases the market basket index by updating the base year from 2010 to 2014, and by adding a new cost category for Installation, Maintenance, and Repair Services. The rule also finalizes revisions to the SNF Quality Reporting Program (QRP), including measure and standardized resident assessment data policies and policies related to public display. In addition, it finalizes policies for the Skilled Nursing Facility Value-Based Purchasing Program that will affect Medicare payment to SNFs beginning in FY 2019. The final rule also clarifies the regulatory requirements for team composition for surveys conducted for investigating a complaint and aligns regulatory provisions for investigation of complaints with the statutory requirements. The final rule also finalizes the performance period for the National Healthcare Safety Network (NHSN) Healthcare Personnel (HCP) Influenza Vaccination Reporting Measure included in the End-Stage Renal Disease (ESRD) Quality Incentive Program (QIP) for Payment Year 2020.

75 FR 70013 - Medicare Program; Inpatient Rehabilitation Facility Prospective Payment System for Federal Fiscal...

Science.gov (United States)

2010-11-16

... 0938-AP89 Medicare Program; Inpatient Rehabilitation Facility Prospective Payment System for Federal... the July 22, 2010 Federal Register entitled, ``Inpatient Rehabilitation Facility Prospective Payment System for Federal Fiscal Year 2011.'' DATES: Effective Date. This correction is effective for IRF...

Quadrant I RCRA Facility Investigation Work Plan

International Nuclear Information System (INIS)

1990-01-01

The objective of this Facility Investigation (FRI) at the Portsmouth Gaseous Diffusion Plant (PORTS) is to acquire, analyze and interpret data which will: (1) characterize the environmental setting including ground water, surface water and sediment, soil and air; (2) define and characterize sources of contamination; (3) characterize the vertical and horizontal extent and degree of contamination of the environment; (4) assess the risk to human health and the environment resulting from possible exposure to contaminants; and, (5) support the Corrective Measures Study (CMS) which will follow the RFI. Investigations to characterize the environmental setting, sources of contamination, and vertical and horizontal extent and degree of contamination will be conducted relative to individual potential sources which have been identified in the Quadrant I Description of Current Conditions. These unit investigations will follow the systematic approach which is outlined below

A research program to reduce interior noise in general aviation airplanes: Investigation of the characteristics of an acoustic panel test facility

Science.gov (United States)

Grosveld, F.; Vanaken, J.

1978-01-01

Sound pressure levels in the test facility were studied that are caused by varying: (1) microphone positions; (2) equalizer setting; and (3) panel clamping forces. Measurements were done by using a Beranek tube or this Beranek tube in combinations with an extension tube and a special test section. In all configurations tests were executed with and without a test panel installed. The influence of the speaker back panel and the back panel of the Beranek tube on the sound pressure levels inside the test tube were also investigated. It is shown that the definition of noise reduction is more useful in relation to this test facility than transmission loss.

Accounting for variations in ART program sustainability outcomes in health facilities in Uganda: a comparative case study analysis.

Science.gov (United States)

Zakumumpa, Henry; Bennett, Sara; Ssengooba, Freddie

2016-10-18

Uganda implemented a national ART scale-up program at public and private health facilities between 2004 and 2009. Little is known about how and why some health facilities have sustained ART programs and why others have not sustained these interventions. The objective of the study was to identify facilitators and barriers to the long-term sustainability of ART programs at six health facilities in Uganda which received donor support to commence ART between 2004 and 2009. A case-study approach was adopted. Six health facilities were purposively selected for in-depth study from a national sample of 195 health facilities across Uganda which participated in an earlier study phase. The six health facilities were placed in three categories of sustainability; High Sustainers (2), Low Sustainers (2) and Non- Sustainers (2). Semi-structured interviews with ART Clinic managers (N = 18) were conducted. Questionnaire data were analyzed (N = 12). Document review augmented respondent data. Based on the data generated, across-case comparative analyses were performed. Data were collected between February and June 2015. Several distinguishing features were found between High Sustainers, and Low and Non-Sustainers' ART program characteristics. High Sustainers had larger ART programs with higher staffing and patient volumes, a broader 'menu' of ART services and more stable program leadership compared to the other cases. High Sustainers associated sustained ART programs with multiple funding streams, robust ART program evaluation systems and having internal and external program champions. Low and Non Sustainers reported similar barriers of shortage and attrition of ART-proficient staff, low capacity for ART program reporting, irregular and insufficient supply of ARV drugs and a lack of alignment between ART scale-up and their for-profit orientation in three of the cases. We found that ART program sustainability was embedded in a complex system involving dynamic interactions

Establishing cyber security programs for I and C systems at nuclear facilities

International Nuclear Information System (INIS)

Waedt, Karl

2012-01-01

In recent years, across the international nuclear community, cyber security issues have quickly gained significant attention from safety authorities and plant designers alike. This increased attention was accelerated by news of the Stuxnet virus, which impaired control systems at Iranian nuclear facilities in 2010, but is also fueled by regular news about cyber security breaches of data systems at large business corporations. This paper discusses key aspects of establishing a cyber security program for Instrumentation and Control (I and C) systems at a nuclear facility, and identifies inherent aspects of nuclear power plant (NPP) design, that differentiate the needs of such a cyber security program from those of typical corporate data systems. (orig.)

Establishing cyber security programs for I and C systems at nuclear facilities

Energy Technology Data Exchange (ETDEWEB)

Waedt, Karl [AREVA NP GmbH (Germany)

2012-11-01

In recent years, across the international nuclear community, cyber security issues have quickly gained significant attention from safety authorities and plant designers alike. This increased attention was accelerated by news of the Stuxnet virus, which impaired control systems at Iranian nuclear facilities in 2010, but is also fueled by regular news about cyber security breaches of data systems at large business corporations. This paper discusses key aspects of establishing a cyber security program for Instrumentation and Control (I and C) systems at a nuclear facility, and identifies inherent aspects of nuclear power plant (NPP) design, that differentiate the needs of such a cyber security program from those of typical corporate data systems. (orig.)

Implementation of Best Practices in Obesity Prevention in Child Care Facilities: The Arizona Empower Program, 2013-2015.

Science.gov (United States)

Papa, Jillian; Agostinelli, Joan; Rodriguez, Gertrudes; Robinson, Deborah

2017-09-07

Obesity is a major health concern in every US age group. Approximately one in 4 children in Arizona's Special Supplemental Nutrition Program for Women, Infants, and Children is overweight or obese. The Arizona Department of Health Services developed the Empower program to promote healthy environments in licensed child care facilities. The program consists of 10 standards, including one standard for each of these 5 areas: physical activity and screen time, breastfeeding, fruit juice and water, family-style meals, and staff training. The objective of this evaluation was to determine the level of implementation of these 5 Empower standards. A self-assessment survey was completed from July 2013 through June 2015 by 1,850 facilities to evaluate the level of implementation of 5 Empower standards. We calculated the percentage of facilities that reported the degree to which they implemented each standard and identified common themes in comments recorded in the survey. All facilities reported either full or partial implementation of the 5 standards. Of 1,678 facilities, 21.7% (n = 364) reported full implementation of all standards, and 78.3% (n = 1,314) reported at least partial implementation. Staff training, which has only one component, had the highest level of implementation: 77.4% (n = 1,299) reported full implementation. Only 44.0% (n = 738) reported full implementation of the standard on a breastfeeding-friendly environment. Arizona child care facilities have begun to implement the Empower program, but facilities will need more education, technical assistance, and support in some areas to fully implement the program.

Development programs on decommissioning technology for reactors and fuel cycle facilities in Japan

International Nuclear Information System (INIS)

Fujiki, K.

1992-01-01

The Science and Technology Agency (STA) of Japan is promoting technology development for decommissioning of nuclear facilities by entrusting various research programs to concerned research organisations: JAERI, PNC and RANDEC, including first full scale reactor decommissioning of JPDR. According to the results of these programs, significant improvement on dismantling techniques, decontamination, measurement etc. has been achieved. Further development of advanced decommissioning technology has been started in order to achieve reduction of duration of decommissioning work and occupational exposures in consideration of the decommissioning of reactors and fuel cycle facilities. (author) 5 refs.; 7 figs.; 1 tab

Status and future program of reactor physics experiments in JAERI Critical facilities, FCA and TCA

International Nuclear Information System (INIS)

Okajima, Shigeaki; Osugi, Toshitaka; Nakajima, Ken; Suzaki, Takenori; Miyoshi, Yoshinori

1999-01-01

The critical facilities in JAERI, FCA (Fast Critical Assembly) and TCA (Tank-type Critical Assembly), have been used to provide integral data for evaluation of nuclear data as well as for development of various types of reactor since they went critical in 1960's. In this paper a review is presented on the experimental programs in both facilities. And the experimental programs in next 5 years are also shown. (author)

76 FR 59256 - Medicare Program; Inpatient Rehabilitation Facility Prospective Payment System for Federal Fiscal...

Science.gov (United States)

2011-09-26

...; Inpatient Rehabilitation Facility Prospective Payment System for Federal Fiscal Year 2012; Changes in Size... [CMS-1349-CN] RIN 0938-AQ28 Medicare Program; Inpatient Rehabilitation Facility Prospective Payment System for Federal Fiscal Year 2012; Changes in Size and Square Footage of Inpatient Rehabilitation Units...

76 FR 32085 - Medicare Program; Inpatient Psychiatric Facilities Prospective Payment System-Update for Rate...

Science.gov (United States)

2011-06-03

..., ``Inpatient Psychiatric Facilities Prospective Payment System--Update for Rate Year Beginning July 1, 2011 (RY... [CMS-1346-CN] RIN 0938-AQ23 Medicare Program; Inpatient Psychiatric Facilities Prospective Payment System--Update for Rate Year Beginning July 1, 2011 (RY 2012); Correction AGENCY: Centers for Medicare...

`Climate wise` program at the Cosmair, Inc. Clark Manufacturing Facility

Energy Technology Data Exchange (ETDEWEB)

Kraly, K.

1997-12-31

Viewgraphs from the conference presentation are reproduced in this paper, which outlines energy efficiency improvements and emissions reductions at a hair care products manufacturing facility. Program management focuses on employee involvement in internal audits, utility tracking, public relations, and preventative maintenance. Energy savings, cost savings, and emission reductions are presented for 1996 and projected to the year 2000. Other program aspects outlined include a summary of utility costs; solid waste; chilled water system modifications; lighting modifications; boiler upgrades; and heating, ventilating, and air conditioning improvements.

Evaluation of Nuclear Facility Decommissioning Projects program

International Nuclear Information System (INIS)

Baumann, B.L.

1983-01-01

The objective of the Evaluation of Nuclear Facility Decommissioning Projects (ENFDP) program is to provide the NRC licensing staff with data which will allow an assessment of radiation exposure during decommissioning and the implementation of ALARA techniques. The data will also provide information to determine the funding level necessary to ensure timely and safe decommissioning operations. Actual decommissioning costs, methods and radiation exposures are compared with those estimated by the Battelle-PNL and ORNL NUREGs on decommissioning. Exposure reduction techniques applied to decommissioning activities to meet ALARA objectives are described. The lessons learned concerning various decommissioning methods are evaluated

Emission Facilities - Erosion & Sediment Control Facilities

Data.gov (United States)

NSGIC Education | GIS Inventory — An Erosion and Sediment Control Facility is a DEP primary facility type related to the Water Pollution Control program. The following sub-facility types related to...

National Ignition Facility Project Site Safety Program

International Nuclear Information System (INIS)

Dun, C

2003-01-01

This Safety Program for the National Ignition Facility (NIF) presents safety protocols and requirements that management and workers shall follow to assure a safe and healthful work environment during activities performed on the NIF Project site. The NIF Project Site Safety Program (NPSSP) requires that activities at the NIF Project site be performed in accordance with the ''LLNL ES and H Manual'' and the augmented set of controls and processes described in this NIF Project Site Safety Program. Specifically, this document: (1) Defines the fundamental NIF site safety philosophy. (2) Defines the areas covered by this safety program (see Appendix B). (3) Identifies management roles and responsibilities. (4) Defines core safety management processes. (5) Identifies NIF site-specific safety requirements. This NPSSP sets forth the responsibilities, requirements, rules, policies, and regulations for workers involved in work activities performed on the NIF Project site. Workers are required to implement measures to create a universal awareness that promotes safe practice at the work site and will achieve NIF management objectives in preventing accidents and illnesses. ES and H requirements are consistent with the ''LLNL ES and H Manual''. This NPSSP and implementing procedures (e.g., Management Walkabout, special work procedures, etc.,) are a comprehensive safety program that applies to NIF workers on the NIF Project site. The NIF Project site includes the B581/B681 site and support areas shown in Appendix B

An investigation of high-temperature irradiation test program of new ceramic materials

International Nuclear Information System (INIS)

Ishino, Shiori; Terai, Takayuki; Oku, Tatsuo

1999-08-01

The Japan Atomic Energy Research Institute entrusted the Atomic Energy Society of Japan with an investigation into the trend of irradiation processing/damage research on new ceramic materials. The present report describes the result of the investigation, which was aimed at effective execution of irradiation programs using the High Temperature Engineering Test Reactor (HTTR) by examining preferential research subjects and their concrete research methods. Objects of the investigation were currently on-going preliminary tests of functional materials (high-temperature oxide superconductor and high-temperature semiconductor) and structural materials (carbon/carbon and SiC/SiC composite materials), together with newly proposed subjects of, e.g., radiation effects on ceramics-coated materials and super-plastic ceramic materials as well as microscopic computer simulation of deformation and fracture of ceramics. These works have revealed 1) the background of each research subject, 2) its objective and significance from viewpoints of science and engineering, 3) research methodology in stages from preliminary tests to real HTTR irradiation, and 4) concrete HTTR-irradiation methods which include main specifications of test specimens, irradiation facilities and post-irradiation examination facilities and apparatuses. The present efforts have constructed the important fundamentals in the new ceramic materials field for further planning and execution of the innovative basic research on high-temperature engineering. (author)

Gas storage facilities. Investigation of their social value. Supplement

International Nuclear Information System (INIS)

1997-02-01

The socio-economic factors resulting from location of gas storage facilities are evaluated. Various alternatives to the existing projects are estimated, for instance 11 new pipelines, in some cases combined with new production capacity, LNG facilities, differentiated tariffs, reconstruction of decentralized heat/power plants etc. Theoretical considerations and models, among others involving gas storage abroad, are presented. Seasonal storage, emergency storage, storage controlled by economic optimization (profitable purchases, sales at highest market) are described for various types of facilities, like aquifers, caverns and LNG-stores. Natural gas supplies in Europe, infrastructure and resources are compared to the Danish conditions. Sensitivity of the Danish heating market for natural gas consumption is investigated. Reduction in energy use for space heating by 2005 will change the needs of storage of 740 Mm 3 gas to 650 Mm 3 . Extra consumption by the decentralized power/heat plants is not accounted for in this estimation. Dynamic models of the future gas consumption are based on the EU 'European Energy 2020'. (EG)

Investigation on calibration parameter of mammography calibration facilities at MINT

International Nuclear Information System (INIS)

Asmaliza Hashim; Wan Hazlinda Ismail; Md Saion Salikin; Muhammad Jamal Md Isa; Azuhar Ripin; Norriza Mohd Isa

2004-01-01

A mammography calibration facility has been established in the Medical Physics Laboratory, Malaysian Institute for Nuclear Technology Research (MINT). The calibration facility is established at the national level mainly to provide calibration services for radiation measuring test instruments or test tools used in quality assurance programme in mammography, which is being implemented in Malaysia. One of the accepted parameters that determine the quality of a radiation beam is the homogeneity coefficient. It is determined from the values of the 1 st and 2 nd Half Value Layer (HVL). In this paper, the consistency of the mammography machine beam qualities that is available in MINT, is investigated and presented. For calibration purposes, five radiation qualities namely 23, 25, 28, 30 and 35 kV, selectable from the control panel of the X-ray machine is used. Important parameters that are set for this calibration facility are exposure time, tube current, focal spot to detector distance (FDD) and beam size at specific distance. The values of homogeneity coefficient of this laboratory for the past few years tip to now be presented in this paper. Backscatter radiations are also considered in this investigation. (Author)

PWR blowdown heat transfer separate-effects program: Thermal-Hydraulic Test Facility experimental data report for test 100

International Nuclear Information System (INIS)

White, M.D.; Hedrick, R.A.

1977-01-01

Reduced instrument responses are presented for Thermal-Hydraulic Test Facility (THTF) test 100, which is part of the ORNL Pressurized-Water-Reactor (PWR) Blowdown Heat Transfer Separate-Effects Program. The objective of the program is to investigate the thermal-hydraulic phenomenon governing the energy transfer and transport processes that occur during a loss-of-coolant accident in a PWR system. Test 100 was conducted to investigate the response of heater rod bundle 1 and instrumented spool pieces with flow homogenizing screens to a double-ended rupture with equal break areas at the test section inlet and outlet. The primary purpose of this report is to make the reduced instrument responses during test 100 available. The responses are presented in graphical form in engineering units and have been analyzed only to the extent necessary to assure reasonableness and consistency

Multi-Function Waste Tank Facility Quality Assurance Program Plan, Project W-236A. Revision 2

Energy Technology Data Exchange (ETDEWEB)

Hall, L.R.

1995-05-30

This document describes the Quality Assurance (QA) program for the Multi-Function Waste Tank Facility (MWTF) Project. The purpose of this QA program is to control project activities in such a manner as to achieve the mission of the MWTF Project in a safe and reliable manner. The QA program for the MWTF Project is founded on DOE Order 5700.6C, Quality Assurance, and implemented through the use of ASME NQA-1, Quality Assurance Program Requirements for Nuclear Facilities (ASME 1989 with addenda la-1989, lb-1991 and lc-1992). This document describes the program and planned actions which the Westinghouse Hanford Company (WHC) will implement to demonstrate and ensure that the project meets the requirements of DOE Order 5700.6C through the interpretive guidance of ASME NQA-1.

Multi-Function Waste Tank Facility Quality Assurance Program Plan, Project W-236A. Revision 2

International Nuclear Information System (INIS)

Hall, L.R.

1995-01-01

This document describes the Quality Assurance (QA) program for the Multi-Function Waste Tank Facility (MWTF) Project. The purpose of this QA program is to control project activities in such a manner as to achieve the mission of the MWTF Project in a safe and reliable manner. The QA program for the MWTF Project is founded on DOE Order 5700.6C, Quality Assurance, and implemented through the use of ASME NQA-1, Quality Assurance Program Requirements for Nuclear Facilities (ASME 1989 with addenda la-1989, lb-1991 and lc-1992). This document describes the program and planned actions which the Westinghouse Hanford Company (WHC) will implement to demonstrate and ensure that the project meets the requirements of DOE Order 5700.6C through the interpretive guidance of ASME NQA-1

Nuclear facility decommissioning and site remedial actions: A selected bibliography, Volume 12. Environmental Restoration Program

Energy Technology Data Exchange (ETDEWEB)

1991-09-01

The 664 abstracted references on environmental restoration, nuclear facility decommissioning, uranium mill tailings management, and site remedial actions constitute the twelfth in a series of reports prepared annually for the US Department of Energy Remedial Action Programs. Citations to foreign and domestic literature of all types -- technical reports, progress reports, journal articles, symposia proceedings, theses, books, patents, legislation, and research project descriptions -- have been included. The bibliography contains scientific, technical, economic, regulatory, and legal information pertinent to the US Department of Energy Remedial Action Programs. Major sections are (1) Decontamination and Decommissioning Program, (2) Nuclear Facilities Decommissioning, (3) Formerly Utilized Sites Remedial Action Program, (4) Facilities Contaminated with Naturally Occurring Radionuclides, (5) Uranium Mill Tailings Remedial Action Program, (6) Uranium Mill Tailings Management, (7) Technical Measurements Center, and (8) Environmental Restoration Program. Within these categories, references are arranged alphabetically by first author. Those references having no individual author are listed by corporate affiliation or by publication title. Indexes are provided for author, corporate affiliation, title word, publication description, geographic location, subject category, and key word. This report is a product of the Remedial Action Program Information Center (RAPIC), which selects, analyzes, and disseminates information on environmental restoration and remedial actions. RAPIC staff and resources are available to meet a variety of information needs. Contact the center at FTS 624-7764 or (615) 574-7764.

Management of radioactive material safety programs at medical facilities. Final report

International Nuclear Information System (INIS)

Camper, L.W.; Schlueter, J.; Woods, S.

1997-05-01

A Task Force, comprising eight US Nuclear Regulatory Commission and two Agreement State program staff members, developed the guidance contained in this report. This report describes a systematic approach for effectively managing radiation safety programs at medical facilities. This is accomplished by defining and emphasizing the roles of an institution's executive management, radiation safety committee, and radiation safety officer. Various aspects of program management are discussed and guidance is offered on selecting the radiation safety officer, determining adequate resources for the program, using such contractual services as consultants and service companies, conducting audits, and establishing the roles of authorized users and supervised individuals; NRC's reporting and notification requirements are discussed, and a general description is given of how NRC's licensing, inspection and enforcement programs work

Development and implementation of the waste diversion program at MDS Nordion's Cobalt Operations Facility

International Nuclear Information System (INIS)

Wasiak, T.

2004-01-01

Historically, the MDS Nordion (MDSN) Cobalt Operations Facility sent solid waste for disposal to Atomic Energy of Canada Ltd.'s Chalk River Laboratories (AECL-CRL). A large portion of this waste was not contaminated. Because this non-contaminated waste originated in the 'active area' of the MDSN facility, it was routinely disposed of as low-level active waste. In 2002, MDSN undertook an initiative to develop and implement a more sophisticated and more economical waste management program. The Waste Diversion Program (WDP) ensures continued environmental and public protection, and reduces the demand on Canada's limited capacity for storage of radioactive material and the associated operating costs. The goal of the WDP is to reduce the volume of waste currently being shipped to AECL-CRL's Waste Management Operation as low-level active waste. The presentation discusses key elements of both the development and the implementation of WDP. It focuses on the following areas: the regulatory environment surrounding the waste disposal issues in Canada and abroad. Methods used by MDSN for determination of radionuclides, which could be present in the facility. Choice of equipment and calculation of individual alarm levels for each identified radionuclide. Key elements of the practical implementation of the program. CNSC Regulatory approval process. The bottom line - dollars and cents. The primary objective of the WDP is to ensure that only waste, which meets regulatory requirements, is diverted from the solid active waste stream. This has been successfully accomplished in MDSN's Cobalt Operations Facility. The objective of the presentation is to share the knowledge and experience obtained in the development process, and thus provide a guideline for other nuclear facilities interested in establishing similar proactive and cost effective programs. (author)

Occupational dose reduction at Department of Energy contractor facilities: Study of ALARA programs

International Nuclear Information System (INIS)

Dionne, B.J.; Meinhold, C.B.; Khan, T.A.; Baum, J.W.

1992-03-01

This report provides the US Department of Energy (DOE) and its contractors with information that will be useful for reducing occupational radiation doses at DOE's nuclear facilities. In 1989 and 1990, health physicists from the Brookhaven National Laboratory's (BNL) ALARA Center visited twelve DOE contractor facilities with annual collective dose equivalents greater than 100 person-rem (100 person-cSv). The health physicists interviewed radiological safety staff, engineers, and training personnel who were responsible for dose control. The status of ALARA practices at the major contractor facilities was compared with the requirements and recommendation in DOE Order 5480.11 ''Radiation Protection for Occupational Workers'' and PNL-6577 ''Health Physics Manual of Good Practices for Reducing Radiation Exposure to Levels that are as Low as Reasonably Achievable.'' The information and data collected are described and examples of successful practices are presented. The findings on the status of the DOE Contractor ALARA Programs are summarized and evaluated. In addition, the supplement to this report contains examples of good-practice documents associated with implementing the major elements of a formally documented ALARA program for a major DOE contractor facility

An independent investigation into the deployment of the federal communications commissions' rural health care pilot program.

Science.gov (United States)

Whitten, Pamela; Holtz, Bree; Laplante, Carolyn; Alverson, Dale; Krupinski, Elizabeth

2010-12-01

the goal of this study was to provide an independent and objective evaluation of the implementation of the Federal Communications Commission's Rural Health Care Pilot Program. thirty-nine of the programs that were provided funding through this program were interviewed and asked about their project deployment, network planning, and the involvement of their state in implementation. RESULTS showed that programs recruited project team members from a variety of fields to fulfill different roles. Network partners were often chosen because they were stakeholders in the outcome of the project and because they had a past working relationship with the grant-receiving programs. In terms of deployment, many programs had made progress in filling out necessary paperwork and were tracking milestones, but had experienced changes since first receiving funding, such as losing participants. Additionally, many encountered challenges that inhibited deployment, such as coping with rule fluctuations. Many of the programs received support from their respective state governments in project development, often through matching funds, but few states were involved in the actual management of projects. as rural healthcare facilities often lack the information technology infrastructure compared with many urban facilities, it is important to understand the implementation process for programs such as the Rural Health Care Pilot Program and to examine what contributes to progress, stagnation, or disintegration. Although the programs reported some success, almost all had encountered challenges that inhibited implementation. A follow-up study is planned to further investigate deployment and determine the implications of Federal Communications Commission funding.

The LEU target development and conversion program for the MAPLE reactors and new processing facility

International Nuclear Information System (INIS)

Malkoske, G.R.

2003-01-01

The availability of isotope grade, Highly Enriched Uranium (HEU), from the United States for use in the manufacture of targets for molybdenum-99 production in AECL's NRU research reactor has been a key factor to enable MDS Nordion to develop a reliable, secure supply of medical isotopes for the international nuclear medicine community. The molybdenum extraction process from HEU targets is a proven and established method that has reliably produced medical isotopes for several decades. The HEU process provides predictable, consistent yields for our high-volume, molybdenum-99 production. Other medical isotopes such as I-131 and Xe-133, which play an important role in nuclear medicine applications, are also produced from irradiated HEU targets as a by-product of the molybdenum-99 process. To ensure a continued reliable and timely supply of medical isotopes, MDS Nordion is completing the commissioning of two MAPLE reactors and an associated isotope processing facility (the New Processing Facility). The new MAPLE facilities, which will be dedicated exclusively to medical isotope production, will provide an essential contribution to a secure, robust global healthcare system. Design and construction of these facilities has been based on a life cycle management philosophy for the isotope production process. This includes target irradiation, isotope extraction and waste management. The MAPLE reactors will operate with Low Enriched Uranium (LEU) fuel, a significant contribution to the objectives of the RERTR program. The design of the isotope production process in the MAPLE facilities is based on an established process - extraction of isotopes from HEU target material. This is a proven technology that has been demonstrated over more than three decades of operation. However, in support of the RERTR program and in compliance with U.S. legislation, MDS Nordion has undertaken a LEU Target Development and Conversion Program for the MAPLE facilities. This paper will provide an

From home deliveries to health care facilities: establishing a traditional birth attendant referral program in Kenya.

Science.gov (United States)

Tomedi, Angelo; Stroud, Sophia R; Maya, Tania Ruiz; Plaman, Christopher R; Mwanthi, Mutuku A

2015-07-16

To assess the effectiveness of a traditional birth attendant (TBA) referral program on increasing the number of deliveries overseen by skilled birth attendants (SBA) in rural Kenyan health facilities before and after the implementation of a free maternity care policy. In a rural region of Kenya, TBAs were recruited to educate pregnant women about the importance of delivering in healthcare facilities and were offered a stipend for every pregnant woman whom they brought to the healthcare facility. We evaluated the percentage of prenatal care (PNC) patients who delivered at the intervention site compared with the percentage of PNC patients who delivered at rural control facilities, before and after the referral program was implemented, and before and after the Kenya government implemented a policy of free maternity care. The window period of the study was from July of 2011 through September 2013, with a TBA referral intervention conducted from March to September 2013. The absolute increases from the pre-intervention period to the TBA referral intervention period in SBA deliveries were 5.7 and 24.0% in the control and intervention groups, respectively (p facility significantly increased compared to control health facilities when TBAs educated women about the need to deliver with a SBA and when TBAs received a stipend for bringing women to local health facilities to deliver. Furthermore, this TBA referral program proved to be far more effective in the target region of Kenya than a policy change to provide free obstetric care.

Status of the US inertial fusion program and the National Ignition Facility

International Nuclear Information System (INIS)

Crandall, D.H.

1997-01-01

Research programs supported by the United States Office of Inertial Fusion and the NIF are summarized. The US inertial fusion program has developed an approach to high energy density physics and fusion ignition in the laboratory relying on the current physics basis of capsule drive by lasers and on the National Ignition Facility which is under construction. (AIP) copyright 1997 American Institute of Physics

DOE standard: Filter test facility quality program plan

International Nuclear Information System (INIS)

1999-02-01

This standard was developed primarily for application in US Department of Energy programs. It contains specific direction for HEPA filter testing performed at a DOE-accepted HEPA Filter Test Facility (FTF). Beneficial comments (recommendations, additions, deletions) and any pertinent data that may improve this document should be sent to the Office of Nuclear Safety Policy and Standards (EH-31), US Department of Energy, Washington, DC 20585, by letter or by using the self-addressed Document Improvement Proposal form (DOE F 1300.3) appearing at the end of this document

Management of radioactive material safety programs at medical facilities. Final report

Energy Technology Data Exchange (ETDEWEB)

Camper, L.W.; Schlueter, J.; Woods, S. [and others

1997-05-01

A Task Force, comprising eight US Nuclear Regulatory Commission and two Agreement State program staff members, developed the guidance contained in this report. This report describes a systematic approach for effectively managing radiation safety programs at medical facilities. This is accomplished by defining and emphasizing the roles of an institution`s executive management, radiation safety committee, and radiation safety officer. Various aspects of program management are discussed and guidance is offered on selecting the radiation safety officer, determining adequate resources for the program, using such contractual services as consultants and service companies, conducting audits, and establishing the roles of authorized users and supervised individuals; NRC`s reporting and notification requirements are discussed, and a general description is given of how NRC`s licensing, inspection and enforcement programs work.

NIST Accelerator Facilities And Programs In Support Of Industrial Radiation Research

International Nuclear Information System (INIS)

Bateman, F.B.; Desrosiers, M.F.; Hudson, L.T.; Coursey, B.M.; Bergstrom, P.M. Jr.; Seltzer, S.M.

2003-01-01

NIST's Ionizing Radiation Division maintains and operates three electron accelerators used in a number of applications including waste treatment and sterilization, radiation hardness testing, detector calibrations and materials modification studies. These facilities serve a large number of governmental, academic and industrial users as well as an active intramural research program. They include a 500 kV cascaded-rectifier accelerator, a 2.5 MV electron Van de Graaff accelerator and a 7 to 32 MeV electron linac, supplying beams ranging in energy from a few keV up to 32 MeV. In response to the recent anthrax incident, NIST along with the US Postal Service and the Armed Forces Radiobiology Research Institute (AFRRI) are working to develop protocols and testing procedures for the USPS mail sanitization program. NIST facilities and personnel are being employed in a series of quality-assurance measurements for both electron- and photon-beam sanitization. These include computational modeling, dose verification and VOC (volatile organic compounds) testing using megavoltage electron and photon sources

75 FR 1755 - Public Telecommunications Facilities Program: Notice of Availability of Funds

Science.gov (United States)

2010-01-13

... DEPARTMENT OF COMMERCE National Telecommunications and Information Administration [Docket No. 0911201414-0010-02] Public Telecommunications Facilities Program: Notice of Availability of Funds AGENCY: National Telecommunications and Information Administration, U.S. Department of Commerce. ACTION: Notice of...

An overview of the PIREX Proton Irradiation facility and its research program

Energy Technology Data Exchange (ETDEWEB)

Victoria, M.; Gavillet, D. [Association EURATOM, Villigen (Switzerland)

1995-10-01

The main design characteristics of PIREX (Proton Irradiation Experiment) are described. The facility is installed in the 590 MeV proton beam of the PSI accelerator system. Its main task is the irradiation and testing of fusion reactor candidate materials. Protons of this energy produce simultaneously in the target material displacement damage and impurities, amongst them helium. They can therefore simulate possible synergistic effects between helium and damage that would result from irradiations with the fusion neutrons. The research program being developed includes studies on both materials of technological interest, such as martensitic stainless steels and Mo - based alloys and basic radiation damage research on pure metals. The facility is also being used for actinide transmutation studies, in the so called ATHENA experiment. The main directions of the research program are described and examples of present results are given.

Identification of potential recovery facilities for designing a reverse supply chain network using physical programming

Science.gov (United States)

Pochampally, Kishore K.; Gupta, Surendra M.; Kamarthi, Sagar V.

2004-02-01

Although there are many quantitative models in the literature to design a reverse supply chain, every model assumes that all the recovery facilities that are engaged in the supply chain have enough potential to efficiently re-process the incoming used products. Motivated by the risk of re-processing used products in facilities of insufficient potentiality, this paper proposes a method to identify potential facilities in a set of candidate recovery facilities operating in a region where a reverse supply chain is to be established. In this paper, the problem is solved using a newly developed method called physical programming. The most significant advantage of using physical programming is that it allows a decision maker to express his preferences for values of criteria (for comparing the alternatives), not in the traditional form of weights but in terms of ranges of different degrees of desirability, such as ideal range, desirable range, highly desirable range, undesirable range, and unacceptable range. A numerical example is considered to illustrate the proposed method.

Facility Design and Health Management Program at the Sinnhuber Aquatic Research Laboratory.

Science.gov (United States)

Barton, Carrie L; Johnson, Eric W; Tanguay, Robert L

2016-07-01

The number of researchers and institutions moving to the utilization of zebrafish for biomedical research continues to increase because of the recognized advantages of this model. Numerous factors should be considered before building a new or retooling an existing facility. Design decisions will directly impact the management and maintenance costs. We and others have advocated for more rigorous approaches to zebrafish health management to support and protect an increasingly diverse portfolio of important research. The Sinnhuber Aquatic Research Laboratory (SARL) is located ∼3 miles from the main Oregon State University campus in Corvallis, Oregon. This facility supports several research programs that depend heavily on the use of adult, larval, and embryonic zebrafish. The new zebrafish facility of the SARL began operation in 2007 with a commitment to build and manage an efficient facility that diligently protects human and fish health. An important goal was to ensure that the facility was free of Pseudoloma neurophilia (Microsporidia), which is very common in zebrafish research facilities. We recognize that there are certain limitations in space, resources, and financial support that are institution dependent, but in this article, we describe the steps taken to build and manage an efficient specific pathogen-free facility.

Final work plan : investigation of potential contamination at the former CCC/USDA grain storage facility in Hanover, Kansas.

Energy Technology Data Exchange (ETDEWEB)

LaFreniere, L. M.; Environmental Science Division

2008-11-19

The Commodity Credit Corporation (CCC), an agency of the U.S. Department of Agriculture (USDA), operated a grain storage facility at the northeastern edge of the city of Hanover, Kansas, from 1950 until the early 1970s. During this time, commercial grain fumigants containing carbon tetrachloride were in common use by the grain storage industry to preserve grain in their facilities. In February 1998, trace to low levels of carbon tetrachloride (below the maximum contaminant level [MCL] of 5.0 {micro}g/L) were detected in two private wells near the former grain storage facility at Hanover, as part of a statewide USDA private well sampling program that was implemented by the Kansas Department of Health and Environment (KDHE) near former CCC/USDA facilities. In April 2007, the CCC/USDA collected near-surface soil samples at 1.8-2 ft BGL (below ground level) at 61 locations across the former CCC/USDA facility. All soil samples were analyzed by the rigorous gas chromatograph-mass spectrometer analytical method (purge-and-trap method). No contamination was found in soil samples above the reporting limit of 10 {micro}g/kg. In July 2007, the CCC/USDA sampled indoor air at nine residences on or adjacent to its former facility to address the residents concerns regarding vapor intrusion. Low levels of carbon tetrachloride were detected at four of the nine homes. Because carbon tetrachloride found in private wells and indoor air at the site might be linked to historical use of fumigants containing carbon tetrachloride at its former grain storage facility, the CCC/USDA is proposing to conduct an investigation to determine the source and extent of the carbon tetrachloride contamination associated with the former facility. This investigation will be conducted in accordance with the intergovernmental agreement between the KDHE and the Farm Service Agency (FSA) of the USDA. The investigation at Hanover will be performed, on behalf of the CCC/USDA, by the Environmental Science

Investigating the Importance of Sports Facilities & Staff for Football Fans

Directory of Open Access Journals (Sweden)

Pinelopi Athanasopoulou

2012-01-01

Full Text Available (a Purpose: This study seeks to investigate the importance of facilities and staff for football fans in Greece. (b Design/methodology/approach: A survey was carried out during two matches of Superleague games with a convenience sample of 312 spectators. A structured questionnaire was used with scales based on previous research. (c Findings: Factor analysis revealed four reliable factor dimensions: facilities design; staff; facilities maintenance, and quick & easy access. Staff and quick & easy access are shown to be the most important dimensions for respondents followed by the other two. Results also indicated that there are significant differences in the importance assigned to these 4 factor dimensions among different levels of age; education; income, and marital status. (d Research limitations/implications: This study is limited to one sport and on a convenience sample of football fans. Future research can validate further these findings and increase their generalisability. (e Practical implications: The results of this study challenge sport managers to manage effectively the design of the stadium; the processes of entry and exit of fans; the environment of the game; and the quality of stadium facilities.

Preliminary siting characterization Salt Disposition Facility - Site B

International Nuclear Information System (INIS)

Wyatt, D.

2000-01-01

A siting and reconnaissance geotechnical program has been completed in S-Area at the Savannah River Site in South Carolina. This program investigated the subsurface conditions for the area known as ''Salt Disposition Facility (SDF), Site B'' located northeast of H-Area and within the S-Area. Data acquired from the Site B investigation includes both field exploration and laboratory test data

The LBM program at the EPFL/LOTUS Facility

International Nuclear Information System (INIS)

File, J.; Jassby, D.L.; Tsang, F.Y.; Haldy, P.A.; Leo, W.R.; Woodruff, G.

1986-01-01

An experimental program of neutron transport studies of the Lithium Blanket Module (LBM) is being carried out with the LOTUS point-neutron source facility at Ecole Polytechnique Federale de Lausanne (EPFL), Switzerland. Preliminary experiments use passive neutron dosimetry within the fuel rods in the LBM central zone, as well as, both thermal extraction and dissolution methods to assay tritium bred in Li/sub 2/O diagnostic wafers and LBM pellets. These measurements are being compared and reconciled with each other and with the predictions of two-dimensional discrete-ordinates and continuous-energy Monte-Carlo analyses of the Lotus/LBM system

SSC string test facility for superconducting magnets: Testing capabilities and program for collider magnets

International Nuclear Information System (INIS)

Kraushaar, P.; Burgett, W.; Dombeck, T.; McInturff, A.; Robinson, W.; Saladin, V.

1993-05-01

The Accelerator Systems String Test (ASST) R ampersand D Testing Facility has been established at the SSC Laboratory to test Collider and High Energy Booster (HEB) superconducting magnet strings. The facility is operational and has had two testing periods utilizing a half cell of collider prototypical magnets with the associated spool pieces and support systems. This paper presents a description of the testing capabilities of the facility with respect to components and supporting subsystems (cryogenic, power, quench protection, controls and instrumentation), the planned testing program for the collider magnets

Investigation - Derived Waste Program

International Nuclear Information System (INIS)

Beardsley, C.; Anderson, R.

1998-06-01

The Investigation-Derived Waste Program is a software application that was developed to identify the groundwater monitoring wells at the Savannah River Site that require containerization and treatment for purge water generated during sampling

Final work plan : Phase I investigation of potential contamination at the former CCC/USDA grain storage facility in Savannah, Missouri.

Energy Technology Data Exchange (ETDEWEB)

LaFreniere, L. M.; Environmental Science Division

2007-10-12

. This work will be performed in accord with the Intergovernmental Agreement established between the Farm Service Agency of the USDA and MoDNR, to address carbon tetrachloride contamination potentially associated with a number of former CCC/USDA grain storage facilities in Missouri. The investigative activities at Savannah will be conducted on behalf of the CCC/USDA by the Environmental Science Division of Argonne National Laboratory. Argonne is a nonprofit, multidisciplinary research center operated by UChicago Argonne, LLC, for the U.S. Department of Energy (DOE). The CCC/USDA has entered into an agreement with the DOE, under which Argonne provides technical assistance to the CCC/USDA with environmental site characterization and remediation at its former grain storage facilities. The site characterization at Savannah will take place in phases. This approach is recommended by the CCC/USDA and Argonne, so that information obtained and interpretations developed during each incremental stage of the investigation can be used most effectively to guide subsequent phases of the program. This site-specific Work Plan outlines the specific technical objectives and scope of work proposed for Phase I of the Savannah investigation. This Work Plan also includes the community relations plan to be followed throughout the CCC/USDA program at the Savannah site. Argonne is developing a Master Work Plan specific to operations in the state of Missouri. In the meantime, Argonne will issue a Provisional Master Work Plan (PMWP; Argonne 2007) that will be submitted to the MoDNR for review and approval. The agency has already reviewed and approved (with minor changes) the present Master Work Plan (Argonne 2002) under which Argonne currently operates in Kansas. The PMWP (Argonne 2007) will provide detailed information and guidance on the investigative technologies, analytical methodologies, quality assurance-quality control measures, and general health and safety policies to be employed by

Laser programs facility management plan for environment, safety, and health

International Nuclear Information System (INIS)

Cruz, G.E.

1996-01-01

The Lawrence Livermore National Laboratory's (LLNL) Laser Programs ES ampersand H policy is established by the Associate Director for Laser Programs. This FMP is one component of that policy. Laser Programs personnel design, construct and operate research and development equipment located in various Livermore and Site 300 buildings. The Programs include a variety of activities, primarily laser research and development, inertial confinement fusion, isotope separation, and an increasing emphasis on materials processing, imaging systems, and signal analysis. This FMP is a formal statement of responsibilities and controls to assure operational activities are conducted without harm to employees, the general public, or the environment. This plan identifies the hazards associated with operating a large research and development facility and is a vehicle to control and mitigate those hazards. Hazards include, but are not limited to: laser beams, hazardous and radioactive materials, criticality, ionizing radiation or x rays, high-voltage electrical equipment, chemicals, and powered machinery

Investigating an Intervention Program Linking Writing and Vocabulary Development for Homeless Children

Directory of Open Access Journals (Sweden)

Richard Sinatra

2010-03-01

Full Text Available The presented study investigated the effects of a four-week academic and activity – enriched summer program on vocabulary development and writing achievement of homeless children residing in traditional shelter facilities. When compared to controls the experimental students did not reveal gains in vocabulary and spelling as measured by two norm referenced tests. They did however demonstrate highly significant gains in writing ability based on the New York State standards criteria, reflecting five qualities of writing. On two project-developed instruments designed to measure improvement in book vocabulary and tennis skills, they showed significant increases based on analyses of their pre- and posttest scores. The program closed achievement gaps, fulfilled standards criteria, and may be the first of its kind in the homeless literature whereby students’ writing development was compared to matched controls as vocabulary development occurred based on literary readings.

Experimental Program for the CLIC test facility 3 test beam line

CERN Document Server

Adli, E; Dobert, S; Olvegaard, M; Schulte, D; Syratchev, I; Lillestol, Reidar

2010-01-01

The CLIC Test Facility 3 Test Beam Line is the first prototype for the CLIC drive beam decelerator. Stable transport of the drive beam under deceleration is a mandatory component in the CLIC two-beam scheme. In the Test Beam Line more than 50% of the total energy will be extracted from a 150 MeV, 28 A electron drive beam, by the use of 16 power extraction and transfer structures. A number of experiments are foreseen to investigate the drive beam characteristics under deceleration in the Test Beam Line, including beam stability, beam blow up and the efficiency of the power extraction. General benchmarking of decelerator simulation and theory studies will also be performed. Specially designed instrumentation including precision BPMs, loss monitors and a time-resolved spectrometer dump will be used for the experiments. This paper describes the experimental program foreseen for the Test Beam Line, including the relevance of the results for the CLIC decelerator studies.

Experimental programs and facilities for ASTRID development related to the Severe Accident Issue

International Nuclear Information System (INIS)

Journeau, C.; Suteau, C.; Trotignon, L.; Willermoz, G.; Ducros, G.; Courouau, J.L.; Ruggieri, J.M.; Serre, F.

2013-01-01

A comprehensive experimental program has been launched in order to gain new data in support of the severe accident studies related to the ASTRID demonstrator. The main new issues with respect to the historic experimental database are mainly related to new design options: heterogeneous core with thick pins; new materials; new severe accident mitigation systems such as - corium discharge channels; - core-catcher with sacrificial materials; - some issues remaining open as Fuel Coolant Interaction. Experiments are needed both in-pile and out of pile: - Depending on the objectives, the out of pile experiments can be conducted - with simulant; - with prototypic corium; - or with irradiated fuel. A new large scale corium facility, FOURNAISE, must be built to fulfill this program. Already, experimental R&D started in existing facilities, such as VITI or CORRONA

235U Holdup Measurement Program in support of facility shutdown

International Nuclear Information System (INIS)

Thomason, R.S.; Griffin, J.C.; Lien, O.G.; McElroy, R.D.

1991-01-01

In 1989, the Department of Energy directed shutdown of an enriched uranium processing facility at Savannah River Site. As part of the shutdown requirements, deinventory and cleanout of process equipment and nondestructive measurement of the remaining 235 U holdup were required. The holdup measurements had safeguards, accountability, and nuclear criticality safety significance; therefore, a technically defensible and well-documented holdup measurement program was needed. Appropriate standards were fabricated, measurement techniques were selected, and an aggressive schedule was followed. Early in the program, offsite experts reviewed the measurement program, and their recommendations were adopted. Contact and far-field methods were used for most measurements, but some process equipment required special attention. All holdup measurements were documented, and each report was subjected to internal peer review. Some measured values were checked against values obtained by other methods; agreement was generally good

Experimental program at the LOTUS facility

International Nuclear Information System (INIS)

Azam, S.; Haldy, P.A.; Kumar, A.; Leo, W.R.; Sahraoui, C.; Schneeberger, J.P.; Tsang, F.; Green, L.

1986-01-01

The objectives of the LOTUS experimental program are to study, from a neutronics point of view, blanket modules having features representative of conceptual fusion reactor blanket designs. Such small-scale generic experiments should help to eliminate possible blind alleys, and thus save much time and money later when commercial-size devices will be constructed. At present, two different types of blanket designs are being studied at the LOTUS facility. The first one represents a hybrid fission-suppressed blanket developed at IGA. It is a parallelepiped-shaped assembly, with a fissile breeding zone made of aluminum-clad thorium oxide rods, and a tritium breeding zone simulated by lithium carbonate compressed powder in aluminum boxes. The second blanket that is currently being tested at IGA is the Lithium Blanket Module (LBM) developed by PPPL under the sponsorship of the Electric Power Research Institute. Essentially, the same kind of experiments will be carried out in all the blanket modules. Measurement of foil activities as well as tritium production in the blanket are the primary diagnostic means in the current LOTUS experimental program. Preanalyses of the experimental data have been carried out at IGA with the help of the two-dimensional discrete ordinates transport code DOT3.5 coupled to the GRTUNCL first collision routine. For the experiments described above, the agreement between experimental and computed results is generally fair

Performance Assessment Program for the Savannah River Site Liquid Waste Facilities - 13610

Energy Technology Data Exchange (ETDEWEB)

Rosenberger, Kent H. [Savannah River Remediation LLC, Building 705-1C, Aiken, SC 29808 (United States)

2013-07-01

The Liquid Waste facilities at the U.S. Department of Energy's (DOE) Savannah River Site (SRS) are operated by Liquid Waste Operations contractor Savannah River Remediation LLC (SRR). A separate Performance Assessment (PA) is prepared to support disposal operations at the Saltstone Disposal Facility and closure evaluations for the two liquid waste tank farm facilities at SRS, F-Tank Farm and H-Tank Farm. A PA provides the technical basis and results to be used in subsequent documents to demonstrate compliance with the pertinent requirements identified in operations and closure regulatory guidance. The Saltstone Disposal Facility is subject to a State of South Carolina industrial solid waste landfill permit and the tank farms are subject to a state industrial waste water permit. The three Liquid Waste facilities are also subject to a Federal Facility Agreement approved by the State, DOE and the Environmental Protection Agency (EPA). Due to the regulatory structure, a PA is a key technical document reviewed by the DOE, the State of South Carolina and the EPA. As the waste material disposed of in the Saltstone Disposal Facility and the residual material in the closed tank farms is also subject to reclassification prior to closure via a waste determination pursuant to Section 3116 of the Ronald W. Reagan National Defense Authorization Act of Fiscal Year 2005, the U.S. Nuclear Regulatory Commission (NRC) is also a reviewing agency for the PAs. Pursuant to the Act, the NRC also has a continuing role to monitor disposal actions to assess compliance with stated performance objectives. The Liquid Waste PA program at SRS represents a continual process over the life of the disposal and closure operations. When the need for a PA or PA revision is identified, the first step is to develop a conceptual model to best represent the facility conditions. The conceptual model will include physical dimensions of the closed system, both the engineered and natural system, and

Performance Assessment Program for the Savannah River Site Liquid Waste Facilities - 13610

International Nuclear Information System (INIS)

Rosenberger, Kent H.

2013-01-01

The Liquid Waste facilities at the U.S. Department of Energy's (DOE) Savannah River Site (SRS) are operated by Liquid Waste Operations contractor Savannah River Remediation LLC (SRR). A separate Performance Assessment (PA) is prepared to support disposal operations at the Saltstone Disposal Facility and closure evaluations for the two liquid waste tank farm facilities at SRS, F-Tank Farm and H-Tank Farm. A PA provides the technical basis and results to be used in subsequent documents to demonstrate compliance with the pertinent requirements identified in operations and closure regulatory guidance. The Saltstone Disposal Facility is subject to a State of South Carolina industrial solid waste landfill permit and the tank farms are subject to a state industrial waste water permit. The three Liquid Waste facilities are also subject to a Federal Facility Agreement approved by the State, DOE and the Environmental Protection Agency (EPA). Due to the regulatory structure, a PA is a key technical document reviewed by the DOE, the State of South Carolina and the EPA. As the waste material disposed of in the Saltstone Disposal Facility and the residual material in the closed tank farms is also subject to reclassification prior to closure via a waste determination pursuant to Section 3116 of the Ronald W. Reagan National Defense Authorization Act of Fiscal Year 2005, the U.S. Nuclear Regulatory Commission (NRC) is also a reviewing agency for the PAs. Pursuant to the Act, the NRC also has a continuing role to monitor disposal actions to assess compliance with stated performance objectives. The Liquid Waste PA program at SRS represents a continual process over the life of the disposal and closure operations. When the need for a PA or PA revision is identified, the first step is to develop a conceptual model to best represent the facility conditions. The conceptual model will include physical dimensions of the closed system, both the engineered and natural system, and modeling

Site investigations for the disposal of spent fuel - investigation program

International Nuclear Information System (INIS)

Aeikaes, Timo

1985-11-01

The Industrial Power Company Ltd (TVO) is making preparations for the final disposal of spent nuclear fuel into the Finnish bedrock. The revised site investigation program for the years 1986-2010 is presented in this report. The objectives and activities in the near future are described in more detail. The main objectives and frame programs for the investigations in the more distant future are described. The program planning of these investigations are being developed in the preceding site investigations. The investigations for the site selection are divided into four phases: 1983-1985 selection of the investigation areas, preparations for the field investigations, drilling and investigations in a deep test borehole; 1986-1992 preliminary site investigations in 5-10 investigation areas; 1993-2000 detailed site investigations in 2-3 investigation areas. Site selection in the year 2000; 2001-2010 complementary investigations on the selected site. The first investigation phase will be carried out as planned. In this phase a 1001 m deep test borehole was drilled at Lavia in western Finland. With the investigations in the borehole and related development work, preparations were made for the future field investigations. The equipment and investigation methods are being developed during the site investigations. The equipment for taking groundwater samples and the unit for hydraulic testing have been developed. In the future the emphasis in the work will be in developing equipment for monitoring of the hydraulic head and measuring the volumetric flow. In groundwater sampling the present procedure can be improved by adding the test for the in-situ measurements. The results of the field investigations will be stored and processed in a centralized data base. The data base will transmit the results for the interpretation and then the interpreted results transmitted for model calculations and reporting. The cost estimate for the investigations in 1986-2010 is 110-125 million

MGR COMPLIANCE PROGRAM GUIDANCE PACKAGE FOR RADIATION PROTECTION EQUIPMENT, INSTRUMENTATION, AND FACILITIES

International Nuclear Information System (INIS)

2000-01-01

This Compliance Program Guidance Package identifies the regulatory guidance and industry codes and standards addressing radiation protection equipment, instrumentation, and support facilities considered to be appropriate for radiation protection at the Monitored Geologic Repository (MGR). Included are considerations relevant to radiation monitoring instruments, calibration, contamination control and decontamination, respiratory protection equipment, and general radiation protection facilities. The scope of this Guidance Package does not include design guidance relevant to criticality monitoring, area radiation monitoring, effluent monitoring, and airborne radioactivity monitoring systems since they are considered to be the topics of specific design and construction requirements (i.e., ''fixed'' or ''built-in'' systems). This Guidance Package does not address radiation protection design issues; it addresses the selection and calibration of radiation monitoring instrumentation to the extent that the guidance is relevant to the operational radiation protection program. Radon and radon progeny monitoring instrumentation is not included in the Guidance Package since such naturally occurring radioactive materials do not fall within the NRC's jurisdiction at the MGR

LLE 1998 annual report, October 1997 -September 1998. Inertial fusion program and National Laser Users' Facility program

International Nuclear Information System (INIS)

1999-01-01

This report summarizes research at the Laboratory for Laser Energetics (LLE), the operation of the National Laser Users' Facility (NLUF), and programs involving the education of high school, undergraduate, and graduate students for FY98. Research summaries cover: progress in laser fusion; diagnostic development; laser and optical technology; and advanced technology for laser targets

LLE 1998 annual report, October 1997--September 1998. Inertial fusion program and National Laser Users` Facility program

Energy Technology Data Exchange (ETDEWEB)

NONE

1999-01-01

This report summarizes research at the Laboratory for Laser Energetics (LLE), the operation of the National Laser Users` Facility (NLUF), and programs involving the education of high school, undergraduate, and graduate students for FY98. Research summaries cover: progress in laser fusion; diagnostic development; laser and optical technology; and advanced technology for laser targets.

Simulations of the Response of the Cluster Detector/Scintillator Wall for the 4π facility at SIS/ESR using the GEANT Detector program

International Nuclear Information System (INIS)

Herrmann, N.; Maguire, C.F.; Cerruti, C.; Coffin, J.P.; Fintz, P.; Guillaume, G.; Jundt, F.; Rami, F.; Tezkratt, R.; Wagner, P.

1990-01-01

The expected response of the cluster detector/scintillator wall of the SIS/ESR 4π facility has been investigated with the use of the GEANT detector program and the FREESCO event generator code. Results are presented and discussed. It is shown in particular that the efficiency of the track reconstruction method should be acceptable

The Abbott School Construction Program: NJ Department of Education Proposed Facilities Regulations. Analysis of Preschool Issues

Science.gov (United States)

Ponessa, Joan; Boylan, Ellen

2004-01-01

This report on preschool facilities analyzes regulations proposed by the New Jersey Department of Education (NJDOE) to implement the Educational Facilities Construction and Financing Act. (EFCFA). EFCFA, which authorizes and governs New Jersey's public school construction program, was enacted in July 2000 to implement the State Supreme Court's…

System aspects of the Indian MST radar facility

Science.gov (United States)

Viswanathan, G.

1986-01-01

One of the major objectives of the Indian Middle Atmosphere Program is to investigate the motions of the middle atmosphere on temporal and spatial scales and the interaction between the three height regions of the middle atmosphere. Realizing the fact that radar technique has proven to be a very powerful tool for the study of Earth atmosphere, the Indian Middle Atmosphere Program has recommended establishing a mesosphere-stratosphere-troposphere (MST) radar as a national facility for atmospheric research. The major landmarks in this attempt to setup the MST radar as a national facility are described.

Physics Division Argonne National Laboratory description of the programs and facilities.

Energy Technology Data Exchange (ETDEWEB)

Thayer, K.J. [ed.

1999-05-24

The ANL Physics Division traces its roots to nuclear physics research at the University of Chicago around the time of the second world war. Following the move from the University of Chicago out to the present Argonne site and the formation of Argonne National Laboratory: the Physics Division has had a tradition of research into fundamental aspects of nuclear and atomic physics. Initially, the emphasis was on areas such as neutron physics, mass spectrometry, and theoretical studies of the nuclear shell model. Maria Goeppert Maier was an employee in the Physics Division during the time she did her Nobel-Prize-winning work on the nuclear shell model. These interests diversified and at the present time the research addresses a wide range of current problems in nuclear and atomic physics. The major emphasis of the current experimental nuclear physics research is in heavy-ion physics, centered around the ATLAS facility (Argonne Tandem-Linac Accelerator System) with its new injector providing intense, energetic ion beams over the fill mass range up to uranium. ATLAS is a designated National User Facility and is based on superconducting radio-frequency technology developed in the Physics Division. A small program continues in accelerator development. In addition, the Division has a strong program in medium-energy nuclear physics carried out at a variety of major national and international facilities. The nuclear theory research in the Division spans a wide range of interests including nuclear dynamics with subnucleonic degrees of freedom, dynamics of many-nucleon systems, nuclear structure, and heavy-ion interactions. This research makes contact with experimental research programs in intermediate-energy and heavy-ion physics, both within the Division and on the national and international scale. The Physics Division traditionally has strong connections with the nation's universities. We have many visiting faculty members and we encourage students to participate in our

Final work plan : phase I investigation of potential contamination at the former CCC/USDA grain storage facility in Montgomery City, Missouri.

Energy Technology Data Exchange (ETDEWEB)

LaFreniere, L. M.; Environmental Science Division

2010-08-16

former grain storage facility, the CCC/USDA will conduct investigations to (1) characterize the source(s), extent, and factors controlling the possible subsurface distribution and movement of carbon tetrachloride at the Montgomery City site and (2) evaluate the health and environmental threats potentially represented by the contamination. This work will be performed in accord with the Intergovernmental Agreement established between the Farm Service Agency of the USDA and the MoDNR, to address carbon tetrachloride contamination potentially associated with a number of former CCC/USDA grain storage facilities in Missouri. The investigations at Montgomery City will be conducted on behalf of the CCC/USDA by the Environmental Science Division of Argonne National Laboratory. Argonne is a nonprofit, multidisciplinary research center operated by UChicago Argonne, LLC, for the U.S. Department of Energy (DOE). The CCC/USDA has entered into an agreement with DOE, under which Argonne provides technical assistance to the CCC/USDA with environmental site characterization and remediation at its former grain storage facilities. The site characterization at Montgomery City will take place in phases. This approach is recommended by the CCC/USDA and Argonne, so that information obtained and interpretations developed during each incremental stage of the investigation can be used most effectively to guide subsequent phases of the program. This site-specific Work Plan outlines the specific technical objectives and scope of work proposed for Phase I of the Montgomery City investigation. This Work Plan also includes the community relations plan to be followed throughout the CCC/USDA program at the Montgomery City site. Argonne is developing a Master Work Plan specific to operations in the state of Missouri. In the meantime, Argonne has issued a Provisional Master Work Plan (PMWP; Argonne 2007) that has been reviewed and approved by the MoDNR for current use. The PMWP (Argonne 2007) provides

Investigation on proper materials of a liner system for trench type disposal facilities of radioactive wastes from research, industrial and medical facilities

International Nuclear Information System (INIS)

Nakata, Hisakazu; Amazawa, Hiroya; Sakai, Akihiro; Arikawa, Masanobu; Sakamoto, Yoshiaki

2011-08-01

The Low-level Radioactive Waste Disposal Project Center of Japan Atomic Energy Agency will settle on near surface disposal facilities with and without engineered barriers for radioactive wastes from research, industrial and medical facilities. Both of them are so called 'concrete pit type' and 'trench type', respectively. The technical standard of constructing and operating a disposal facility based on 'Law for the Regulations of Nuclear Source Material, Nuclear Fuel Material and Reactors' have been regulated partly by referring to that of 'Waste Management and Public Cleansing Law'. This means that the concrete pit type and the trench type disposal facility resemble an isolated type for specified industrial wastes and a non leachate controlled type final disposal site for stable industrial wastes, respectively. On the other, We plan to design a disposal facility with a liner system corresponding to a leachate controlled type final disposal site on a crucial assumption that radioactive wastes other than stable industrial wastes to be disposed into the trench type disposal facility is generated. By current nuclear related regulations in Japan, There are no technical standard of constructing the disposal facility with the liner system referring to that of 'Waste Management and Public Cleansing Law'. We investigate the function of the liner system in order to design a proper liner system for the trench type disposal facility. In this report, We investigated liner materials currently in use by actual leachate controlled type final disposal sites in Japan. Thereby important items such as tensile strength, durability from a view point of selecting proper liner materials were studied. The items were classified into three categories according to importance. We ranked proper liner materials for the trench type disposal facility by evaluating the important items per material. As a result, high density polyethylene(HDPE) of high elasticity type polymetric sheet was selected

The outline of investigation on integrity of JMTR concrete structures, cooling system and utility facilities

International Nuclear Information System (INIS)

Ebisawa, Hiroyuki; Hanakawa, Hiroki; Asano, Norikazu; Kusunoki, Hidehiko; Yanai, Tomohiro; Sato, Shinichi; Miyauchi, Masaru; Ohto, Tsutomu; Kimura, Tadashi; Kawamata, Takanori; Nemoto, Nobuaki; Watahiki, Shunsuke; Hanawa, Yoshio; Tsuboi, Kazuaki; Ogasawara, Yasushi; Nemoto, Hiroyoshi; Echigoya, Shinichi; Ohtsuka, Kaoru; Onoue, Ryuji; Koike, Sumio; Gorai, Shigeru; Nishiyama, Yutaka; Kurosawa, Akihiko; Hanawa, Nobuhiro; Tobita, Kenji; Tabata, Shuzo; Fukasaku, Akitomi; Isozaki, Takanori; Akashi, Kazutomo; Takahashi, Kunihiro; Tsuji, Tomoyuki

2009-07-01

The condition of facilities and machinery used continuously were investigated before the renewal work of JMTR on FY 2007. The subjects of investigation were reactor building, primary cooling system tanks, secondary cooling system piping and tower, emergency generator and so on. As the result, it was confirmed that some facilities and machinery were necessary to repair and others were used continuously for long term by maintaining on the long-term maintenance plan. JMTR is planed to renew by the result of this investigation. (author)

PWR Blowdown Heat Transfer Separate-Effects Program. Thermal-Hydraulic Test Facility experimental data report for test 166S

International Nuclear Information System (INIS)

Clemons, V.D.; White, M.D.; Hedrick, R.A.

1978-01-01

Reduced instrument responses are presented for Thermal-Hydraulic Test Facility (THTF) test 166S, which is part of the ORNL Pressurized-Water Reactor (PWR) Blowdown Heat Transfer Separate-Effects Program. The objective of the program is to investigate the thermal-hydraulic phenomenon governing the energy transfer and transport processes that occur during a loss-of-coolant accident in a PWR system. Test 166S was conducted to obtain thermal-hydraulic and CHF information in THTF bundle 1 with an intact hot leg. The primary purpose of this report is to make the reduced instrument responses during tests 166S available. These are presented in graphical form in engineering units and have been analyzed only to the extent necessary to ensure reasonableness and consistency

The Idaho Power Burst Facility/Boron Neutron Capture Therapy (PBF/BNCT) Program overview

International Nuclear Information System (INIS)

Dorn, R.V. III; Griebenow, M.L.; Ackermann, A.L.; Miller, L.G.; Miller, D.L.; Wheeler, F.J.; Bradshaw, K.M.; Wessol, D.E.; Harker, Y.D.; Nigg, D.W.; Randolph, P.D.; Bauer, W.F.; Gavin, P.R.; Richards, T.L.

1992-01-01

The Power Burst Facility/Boron Neutron Capture Therapy (PBF/BNCT) Program has been funded since 1988 to evaluate brain tumor treatment using Na 2 B 12 H 11 SH (borocaptate sodium or BSH) and epithermal neutrons. The PBF/BNCT Program pursues this goal as a comprehensive, multidisciplinary, multiorganizational endeavor applying modern program management techniques. The initial focus was to: (1) establish a representative large animal model and (2) develop the generic analytical and measurement capabilities require to control treatment repeatability and determine critical treatment parameters independent of tumor type and body location. This paper will identify the PBF/BNCT Program elements and summarize the status of some of the developed capabilities

Sanford Underground Research Facility - The United State's Deep Underground Research Facility

Science.gov (United States)

Vardiman, D.

2012-12-01

The 2.5 km deep Sanford Underground Research Facility (SURF) is managed by the South Dakota Science and Technology Authority (SDSTA) at the former Homestake Mine site in Lead, South Dakota. The US Department of Energy currently supports the development of the facility using a phased approach for underground deployment of experiments as they obtain an advanced design stage. The geology of the Sanford Laboratory site has been studied during the 125 years of operations at the Homestake Mine and more recently as part of the preliminary geotechnical site investigations for the NSF's Deep Underground Science and Engineering Laboratory project. The overall geology at DUSEL is a well-defined stratigraphic sequence of schist and phyllites. The three major Proterozoic units encountered in the underground consist of interbedded schist, metasediments, and amphibolite schist which are crosscut by Tertiary rhyolite dikes. Preliminary geotechnical site investigations included drift mapping, borehole drilling, borehole televiewing, in-situ stress analysis, laboratory analysis of core, mapping and laser scanning of new excavations, modeling and analysis of all geotechnical information. The investigation was focused upon the determination if the proposed site rock mass could support the world's largest (66 meter diameter) deep underground excavation. While the DUSEL project has subsequently been significantly modified, these data are still available to provide a baseline of the ground conditions which may be judiciously extrapolated throughout the entire Proterozoic rock assemblage for future excavations. Recommendations for facility instrumentation and monitoring were included in the preliminary design of the DUSEL project design and include; single and multiple point extensometers, tape extensometers and convergence measurements (pins), load cells and pressure cells, smart cables, inclinometers/Tiltmeters, Piezometers, thermistors, seismographs and accelerometers, scanners (laser

Centrifuge Facility for the International Space Station Alpha

Science.gov (United States)

Johnson, Catherine C.; Hargens, Alan R.

1994-01-01

The Centrifuge Facility planned for the International Space Station Alpha has under-one considerable redesign over the past year, primarily because the Station is now viewed as a 10 year mission rather than a 30 year mission and because of the need to simply the design to meet budget constraints and a 2000 launch date. The basic elements of the Centrifuge Facility remain the same, i.e., a 2.5 m diameter centrifuge, a micro-g holding unit, plant and animal habitats, a glovebox and a service unit. The centrifuge will still provide the full range of artificial gravity from 0.01 a to 2 - as originally planned; however, the extractor to permit withdrawal of habitats from the centrifuge without stopping the centrifuge has been eliminated. The specimen habitats have also been simplified and are derived from other NASA programs. The Plant Research Unit being developed by the Gravitational Biology Facility will be used to house plants in the Centrifuge Facility. Although not as ambitious as the Centrifuge Facility plant habitat, it will provide much better environmental control and lighting than the current Shuttle based Plant Growth Facility. Similarly, rodents will be housed in the Advanced Animal Habitat being developed for the Shuttle program. The Centrifuge Facility and ISSA will provide the opportunity to perform repeatable, high quality science. The long duration increments available on the Station will permit multigeneration studies on both plants and animals which have not previously been possible. The Centrifuge Facility will accommodate sufficient number of specimens to permit statistically significant sampling of specimens to investigate the time course of adaptation to altered gravity environments. The centrifuge will for the first time permit investigators to use gravity itself as a tool to investigate fundamental processes, to investigate the intensity and duration of gravity to maintain normal structure and function, to separate the effects of micro-g from

Investigating walking environments in and around assisted living facilities: a facility visit study.

Science.gov (United States)

Lu, Zhipeng

2010-01-01

This study explores assisted living residents' walking behaviors, locations where residents prefer to walk, and walking environments in and around assisted living facilities. Regular walking is beneficial to older adults' physical and psychological health. Yet frail older residents in assisted living are usually too sedentary to achieve these benefits. The physical environment plays an important role in promoting physical activity. However, there is little research exploring this relationship in assisted living settings. The researcher visited 34 assisted living facilities in a major Texas city. Methods included walk-through observation with the Assisted Living Facility Walking Environment Checklist, and interviews with administrators by open- and close-ended questions. The data from 26 facilities were analyzed using descriptive statistics (for quantitative data) and content analysis (for qualitative data). The results indicate that (a) residents were walking both indoors and outdoors for exercise or other purposes (e.g., going to destinations); (b) assisted living facility planning and design details-such as neighborhood sidewalk conditions, facility site selection, availability of seating, walking path configuration (e.g., looped/nonlooped path), amount of shading along the path, presence of handrails, existence of signage, etc.-may influence residents' walking behaviors; and (c) current assisted living facilities need improvement in all aspects to make their environments more walkable for residents. Findings of the study provide recommendations for assisted living facilities to improve the walkability of environments and to create environmental interventions to promote regular walking among their residents. This study also implies several directions for future research.

Integrating incident investigation into the management system

International Nuclear Information System (INIS)

Peterson, E.E.

1992-01-01

In the last 10 yr, the size and frequency of incidents affecting the communities and environment surrounding chemical processing facilities has increased. The chemical process industry, which has always concerned itself with the safety of its facilities, has responded by committing to stricter standards of operation and management. A critical element of these management practices is the use of a structured incident investigation program. Many facilities have implemented and disciplined themselves to perform good investigation of incidents. However, most of these facilities maintain incident investigation as part of their safety management programs. This allows the process to be disconnected from the management system that deals with the day-to-day business of the facility. The first step of integration is understanding the objectives and functions of the management system into which the integration is to occur. To begin, a common definition of management is needed. Management, for the purposes of this discussion, is defined as the system of activities used to control, coordinate, and improve the flow of work within a facility or organization. This definition refers to several concepts that need further development in order to understand how incident investigation can be integrated into a management system, including (a) flow of work, (b) control, and (c) improvement. Application can be made to the nuclear industry

Clinical Investigation Program Annual Progress Report

Science.gov (United States)

1993-09-30

The assigned staff of the Molecular Biology Service are Dr. Anthony G. Gutierrez , Chef , GSl3, Ph. D. in Molecular Genetics, and Ms. Judith O’Brien...Node-Negative Breast Cancer Patients Using a Panel of Prognostic Factors. A Companion Protocol to SWOG 8897 ................................ . 103 91...of Prog- nostic Factors. A companion protocol to 8897 (5) Start Date: 1991 (6) Est Compl Date: (7) Principal Investigator: (8) Facility: FAMC Thomas

Radiation safety program in high dose rate brachytherapy facility at INHS Asvini

Directory of Open Access Journals (Sweden)

Kirti Tyagi

2014-01-01

Full Text Available Brachytherapy concerns primarily the use of radioactive sealed sources which are inserted into catheters or applicators and placed directly into tissue either inside or very close to the target volume. The use of radiation in treatment of patients involves both benefits and risks. It has been reported that early radiation workers had developed radiation induced cancers. These incidents lead to continuous work for the improvement of radiation safety of patients and personnel The use of remote afterloading equipment has been developed to improve radiation safety in the delivery of treatment in brachytherapy. The widespread adoption of high dose rate brachytherapy needs appropriate quality assurance measures to minimize the risks to both patients and medical staff. The radiation safety program covers five major aspects: quality control, quality assurance, radiation monitoring, preventive maintenance, administrative measures and quality audit. This paper will discuss the radiation safety program developedfor a high dose rate brachytherapy facility at our centre which may serve as a guideline for other centres intending to install a similar facility.

Annual summary report on surveillance and maintenance activities of the surplus contaminated facilities program at Oak Ridge National Laboratory for period ending September 30, 1991

International Nuclear Information System (INIS)

Cannon, T.R.; Ford, M.K.; Holder, L. Jr.

1991-09-01

The Surplus Contaminated Facilities Program (SCFP) was established at the Oak Ridge National Laboratory (ORNL) in 1985 to provide support for inactive contaminated facilities that were largely abandoned by the programs which they formerly served. This support provides for routine surveillance and maintenance (S ampersand M) and special projects beyond a routine nature when such actions are needed to ensure adequate protection of personnel or the environment. The facilities included in the program had been used for research, technology development, isotope production and processing, and waste management. Support for facilities in the SCFP has previously been provided by the Department of Energy's (DOE's) Office of Energy Research: Multiprogram Energy Laboratories -- Facilities Support (ERKG) because of multiprogram use of the facilities or because of the landlord responsibility of Energy Research. Recently, an integrated Decontamination and Decommissioning (D ampersand D) program within the DOE Office of Environmental Restoration and Waste Management has been established to collectively manage the former Surplus Facilities Management Program, Defense D ampersand D Program, and the KG-funded, ORNL-originated SCFP. This report gives an overview of the S ampersand M planning, routine S ampersand M, and special maintenance project activities which have occurred at the SCFP facilities during the 1991 Fiscal Year

Technical critique on radiation test facilities for the CTR surface and materials program

International Nuclear Information System (INIS)

Persiani, P.J.

1975-02-01

Major radiation test facilities will be necessary in the near-term (5 years) and long-term (greater than 10 years) future for the timely development and understanding of fusion confinement systems and of prototype fusion power reactors. The study includes the technical justifications and requirements for CTR Neutron and Plasma Radiation Test Facilities. The initial technical critique covers the feasibility and design problems: in upgrading the performance of the accelerator-rotating (solid TiT) target systems, and in transforming the accelerator-supersonic jet target concept into a radiation testing facility. A scoping assessment on the potential of a pulsed high-beta plasma device (dense plasma focus) is introduced to explore plasma concepts as near-term neutron and plasma radiation sources for the CTR Surface and Materials Program. (U.S.)

25 CFR 170.808 - Can BIA Road Maintenance Program funds be used to improve IRR transportation facilities?

Science.gov (United States)

2010-04-01

... 25 Indians 1 2010-04-01 2010-04-01 false Can BIA Road Maintenance Program funds be used to improve... THE INTERIOR LAND AND WATER INDIAN RESERVATION ROADS PROGRAM BIA Road Maintenance § 170.808 Can BIA Road Maintenance Program funds be used to improve IRR transportation facilities? No. BIA Road...

Optimal control of hydroelectric facilities

Science.gov (United States)

Zhao, Guangzhi

This thesis considers a simple yet realistic model of pump-assisted hydroelectric facilities operating in a market with time-varying but deterministic power prices. Both deterministic and stochastic water inflows are considered. The fluid mechanical and engineering details of the facility are described by a model containing several parameters. We present a dynamic programming algorithm for optimizing either the total energy produced or the total cash generated by these plants. The algorithm allows us to give the optimal control strategy as a function of time and to see how this strategy, and the associated plant value, varies with water inflow and electricity price. We investigate various cases. For a single pumped storage facility experiencing deterministic power prices and water inflows, we investigate the varying behaviour for an oversimplified constant turbine- and pump-efficiency model with simple reservoir geometries. We then generalize this simple model to include more realistic turbine efficiencies, situations with more complicated reservoir geometry, and the introduction of dissipative switching costs between various control states. We find many results which reinforce our physical intuition about this complicated system as well as results which initially challenge, though later deepen, this intuition. One major lesson of this work is that the optimal control strategy does not differ much between two differing objectives of maximizing energy production and maximizing its cash value. We then turn our attention to the case of stochastic water inflows. We present a stochastic dynamic programming algorithm which can find an on-average optimal control in the face of this randomness. As the operator of a facility must be more cautious when inflows are random, the randomness destroys facility value. Following this insight we quantify exactly how much a perfect hydrological inflow forecast would be worth to a dam operator. In our final chapter we discuss the

Facility accident considerations in the US Department of Energy Waste Management Program

International Nuclear Information System (INIS)

Mueller, C.

1994-01-01

A principal consideration in developing waste management strategies is the relative importance of Potential radiological and hazardous releases to the environment during postulated facility accidents with respect to protection of human health and the environment. The Office of Environmental Management (EM) within the US Department of Energy (DOE) is currently formulating an integrated national program to manage the treatment, storage, and disposal of existing and future wastes at DOE sites. As part of this process, a Programmatic Environmental impact Statement (PEIS) is being prepared to evaluate different waste management alternatives. This paper reviews analyses that have been Performed to characterize, screen, and develop source terms for accidents that may occur in facilities used to store and treat the waste streams considered in these alternatives. Preliminary results of these analyses are discussed with respect to the comparative potential for significant releases due to accidents affecting various treatment processes and facility configurations. Key assumptions and sensitivities are described

Advanced Test Reactor National Scientific User Facility 2010 Annual Report

Energy Technology Data Exchange (ETDEWEB)

Mary Catherine Thelen; Todd R. Allen

2011-05-01

This is the 2010 ATR National Scientific User Facility Annual Report. This report provides an overview of the program for 2010, along with individual project reports from each of the university principal investigators. The report also describes the capabilities offered to university researchers here at INL and at the ATR NSUF partner facilities.

An Innovative Approach for Decreasing Fall Trauma Admissions from Geriatric Living Facilities: Preliminary Investigation.

Science.gov (United States)

Evans, Tracy; Gross, Brian; Rittenhouse, Katelyn; Harnish, Carissa; Vellucci, Ashley; Bupp, Katherine; Horst, Michael; Miller, Jo Ann; Baier, Ron; Chandler, Roxanne; Rogers, Frederick B

2015-12-01

Geriatric living facilities have been associated with a high rate of falls. We sought to develop an innovative intervention approach targeting geriatric living facilities that would reduce geriatric fall admissions to our Level II trauma center. In 2011, a Trauma Prevention Taskforce visited 5 of 28 local geriatric living facilities to present a fall prevention protocol composed of three sections: fall education, risk factor identification, and fall prevention strategies. To determine the impact of the intervention, the trauma registry was queried for all geriatric fall admissions attributed to patients living at local geriatric living facilities. The fall admission rate (total fall admissions/total beds) of the pre-intervention period (2010-2011) was compared with that of the postintervention period (2012-2013) at the 5 intervention and 23 control facilities. A P value fall admissions attributed to local geriatric living facilities (intervention: 179 fall admissions; control: 308 fall admissions). The unadjusted fall rate decreased at intervention facilities from 8.9 fall admissions/bed pre-intervention to 8.1 fall admissions/bed postintervention, whereas fall admission rates increased at control sites from 5.9 to 7.7 fall admissions/bed during the same period [control/intervention odds ratio (OR), 95% confidence interval (CI) = 1.32, 1.05-1.67; period OR, 95%CI = 1.55, 1.18-2.04, P = 0.002; interaction of control/intervention group and period OR 95% CI = 0.68, 0.46-1.00, P = 0.047]. An aggressive intervention program targeting high-risk geriatric living facilities resulted in a statistically significant decrease in geriatric fall admissions to our Level II trauma center.

21 CFR 1000.55 - Recommendation for quality assurance programs in diagnostic radiology facilities.

Science.gov (United States)

2010-04-01

... facilities where more than one department operates x-ray equipment, to the chief medical officer of the..., improved image quality, and/or financial savings will compensate for the resources required for the program... generally be delegated a basic quality assurance role by the practitioner in charge. Responsibility for...

Ocean Thermal Energy Converstion (OTEC) test facilities study program. Final report. Volume II. Part B

Energy Technology Data Exchange (ETDEWEB)

None

1977-01-17

Results are presented of an 8-month study to develop alternative non-site-specific OTEC facilities/platform requirements for an integrated OTEC test program which may include land and floating test facilities. Volume II--Appendixes is bound in three parts (A, B, and C) which together comprise a compendium of the most significant detailed data developed during the study. Part B provides an annotated test list and describes component tests and system tests.

Test program element II blanket and shield thermal-hydraulic and thermomechanical testing, experimental facility survey

Energy Technology Data Exchange (ETDEWEB)

Ware, A.G.; Longhurst, G.R.

1981-12-01

This report presents results of a survey conducted by EG and G Idaho to determine facilities available to conduct thermal-hydraulic and thermomechanical testing for the Department of Energy Office of Fusion Energy First Wall/Blanket/Shield Engineering Test Program. In response to EG and G queries, twelve organizations (in addition to EG and G and General Atomic) expressed interest in providing experimental facilities. A variety of methods of supplying heat is available.

Test program element II blanket and shield thermal-hydraulic and thermomechanical testing, experimental facility survey

International Nuclear Information System (INIS)

Ware, A.G.; Longhurst, G.R.

1981-12-01

This report presents results of a survey conducted by EG and G Idaho to determine facilities available to conduct thermal-hydraulic and thermomechanical testing for the Department of Energy Office of Fusion Energy First Wall/Blanket/Shield Engineering Test Program. In response to EG and G queries, twelve organizations (in addition to EG and G and General Atomic) expressed interest in providing experimental facilities. A variety of methods of supplying heat is available

The RIB facility EXOTIC and its experimental program at INFN-LNL

Science.gov (United States)

Parascandolo, Concetta

2018-05-01

In this contribution, I will present a review about the EXOTIC facility and the research field accessible by using its Radioactive Ion Beams. The EXOTIC facility, installed at the INFN-Laboratori Nazionali di Legnaro, is devoted to the in-flight production of light Radioactive Ion Beams in the energy range between 3-5 MeV/nucleon. The scientific activity performed at EXOTIC concerns different aspects of nuclear physics and nuclear astrophysics, such as, the investigation of reaction mechanisms and nuclear structure, resonant scattering experiments and measurements of nuclear reaction cross sections of astrophysical interest.

Structural Integrity Program for the Calcined Solids Storage Facilities at the Idaho Nuclear Technology and Engineering Center

International Nuclear Information System (INIS)

Bryant, J.W.; Nenni, J.A.

2003-01-01

This report documents the activities of the structural integrity program at the Idaho Nuclear Technology and Engineering Center relevant to the high-level waste Calcined Solids Storage Facilities and associated equipment, as required by DOE M 435.1-1, ''Radioactive Waste Management Manual.'' Based on the evaluation documented in this report, the Calcined Solids Storage Facilities are not leaking and are structurally sound for continued service. Recommendations are provided for continued monitoring of the Calcined Solids Storage Facilities

Structural Integrity Program for the Calcined Solids Storage Facilities at the Idaho Nuclear Technology and Engineering Center

International Nuclear Information System (INIS)

Jeffrey Bryant

2008-01-01

This report documents the activities of the structural integrity program at the Idaho Nuclear Technology and Engineering Center relevant to the high-level waste Calcined Solids Storage Facilities and associated equipment, as required by DOE M 435.1-1, 'Radioactive Waste Management Manual'. Based on the evaluation documented in this report, the Calcined Solids Storage Facilities are not leaking and are structurally sound for continued service. Recommendations are provided for continued monitoring of the Calcined Solids Storage Facilities

Joint Assessment of Renewable Energy and Water Desalination Research Center (REWDC) Program Capabilities and Facilities In Radioactive Waste Management

International Nuclear Information System (INIS)

Bissani, M; Fischer, R; Kidd, S; Merrigan, J

2006-01-01

The primary goal of this visit was to perform a joint assessment of the Renewable Energy and Water Desalination Center's (REWDC) program in radioactive waste management. The visit represented the fourth technical and scientific interaction with Libya under the DOE/NNSA Sister Laboratory Arrangement. Specific topics addressed during the visit focused on Action Sheet P-05-5, ''Radioactive Waste Management''. The Team, comprised of Mo Bissani (Team Lead), Robert Fischer, Scott Kidd, and Jim Merrigan, consulted with REWDC management and staff. The team collected information, discussed particulars of the technical collaboration and toured the Tajura facility. The tour included the waste treatment facility, waste storage/disposal facility, research reactor facility, hot cells and analytical labs. The assessment team conducted the first phase of Task A for Action Sheet 5, which involved a joint assessment of the Radioactive Waste Management Program. The assessment included review of the facilities dedicated to the management of radioactive waste at the Tourja site, the waste management practices, proposed projects for the facility and potential impacts on waste generation and management

Standby status report Hot Semiworks facility

Energy Technology Data Exchange (ETDEWEB)

Cooley, C.R.

1957-09-01

This report is written to provide information concerning the status of the Hot Semiworks facility as it is placed in stand-by on July 1, 1957. The plant was constructed in 1951 and early 1952. It vas operated on Redox type investigations until the last of 1953. The plant was then converted to the Purex flowsheet under Project CA 513 D. Operations on the Purex type investigations were started in early 1955 and continued until early in 1956. At that time a maintenance program for plant improvement and repair was initiated. This program was completed on July 1, 1957. Statements are contained in this report which pertain to the present status of physical equipment and facilities and the adequacy, operating experience, recommendations for improvement, previous work, and future considerations of the plant. However, the primary intent of the report is to provide pertinent information to personnel associated with a future start-up. For this reason, certain parts of the report are quite detailed. Only statements concerning the existing or previous state of the facility and equipment are factual. Others are opinions or experiences of plant operating personnel. Emphasis has also been placed on the faults encountered rather than the good features of the plant, in order that these faults might be corrected in the future.

Facility certification program for coal miners pneumoconiosis

International Nuclear Information System (INIS)

Trout, E.D.; Kelley, J.P.; Larson, V.L.; Herbert, G.L.

1976-01-01

Public Law 91-173, often referred to as the Black Lung Law, called for a chest radiograph of all active coal miners at stated intervals. The National Institute for Occupational Safety and Health was responsible for carrying out the provisions of the law. Among other requirements was a provision for certification of radiological facilities where radiological examinations would be provide. A test object to be radiographed by each such facility was designed and sent to those facilities applying for certification. To date, 284 facilities have applied for certification of which 215 have been approved. A record has been kept of the number of times any approved facility submitted radiographs before approval. A complete listing of the types of equipment used, personnel qualifications and other pertinent data will be reported

Mound facility physical characterization

Energy Technology Data Exchange (ETDEWEB)

Tonne, W.R.; Alexander, B.M.; Cage, M.R.; Hase, E.H.; Schmidt, M.J.; Schneider, J.E.; Slusher, W.; Todd, J.E.

1993-12-01

The purpose of this report is to provide a baseline physical characterization of Mound`s facilities as of September 1993. The baseline characterizations are to be used in the development of long-term future use strategy development for the Mound site. This document describes the current missions and alternative future use scenarios for each building. Current mission descriptions cover facility capabilities, physical resources required to support operations, current safety envelope and current status of facilities. Future use scenarios identify potential alternative future uses, facility modifications required for likely use, facility modifications of other uses, changes to safety envelope for the likely use, cleanup criteria for each future use scenario, and disposition of surplus equipment. This Introductory Chapter includes an Executive Summary that contains narrative on the Functional Unit Material Condition, Current Facility Status, Listing of Buildings, Space Plans, Summary of Maintenance Program and Repair Backlog, Environmental Restoration, and Decontamination and Decommissioning Programs. Under Section B, Site Description, is a brief listing of the Site PS Development, as well as Current Utility Sources. Section C contains Site Assumptions. A Maintenance Program Overview, as well as Current Deficiencies, is contained within the Maintenance Program Chapter.

SU-F-T-169: A Periodic Quality Assurance Program for a Spot-Scanning Proton Treatment Facility

International Nuclear Information System (INIS)

Mundy, D; Tryggestad, E; Beltran, C; Furutani, K; Gilson, G; Ito, S; Johnson, J; Kruse, J; Remmes, N; Tasson, A; Whitaker, T; Herman, M

2016-01-01

Purpose: To develop daily and monthly quality assurance (QA) programs in support of a new spot-scanning proton treatment facility using a combination of commercial and custom equipment and software. Emphasis was placed on efficiency and evaluation of key quality parameters. Methods: The daily QA program was developed to test output, spot size and position, proton beam energy, and image guidance using the Sun Nuclear Corporation rf-DQA™3 device and Atlas QA software. The program utilizes standard Atlas linear accelerator tests repurposed for proton measurements and a custom jig for indexing the device to the treatment couch. The monthly QA program was designed to test mechanical performance, image quality, radiation quality, isocenter coincidence, and safety features. Many of these tests are similar to linear accelerator QA counterparts, but many require customized test design and equipment. Coincidence of imaging, laser marker, mechanical, and radiation isocenters, for instance, is verified using a custom film-based device devised and manufactured at our facility. Proton spot size and position as a function of energy are verified using a custom spot pattern incident on film and analysis software developed in-house. More details concerning the equipment and software developed for monthly QA are included in the supporting document. Thresholds for daily and monthly tests were established via perturbation analysis, early experience, and/or proton system specifications and associated acceptance test results. Results: The periodic QA program described here has been in effect for approximately 9 months and has proven efficient and sensitive to sub-clinical variations in treatment delivery characteristics. Conclusion: Tools and professional guidelines for periodic proton system QA are not as well developed as their photon and electron counterparts. The program described here efficiently evaluates key quality parameters and, while specific to the needs of our facility

SU-F-T-169: A Periodic Quality Assurance Program for a Spot-Scanning Proton Treatment Facility

Energy Technology Data Exchange (ETDEWEB)

Mundy, D; Tryggestad, E; Beltran, C; Furutani, K; Gilson, G; Ito, S; Johnson, J; Kruse, J; Remmes, N; Tasson, A; Whitaker, T; Herman, M [Mayo Clinic, Rochester, MN (United States)

2016-06-15

Purpose: To develop daily and monthly quality assurance (QA) programs in support of a new spot-scanning proton treatment facility using a combination of commercial and custom equipment and software. Emphasis was placed on efficiency and evaluation of key quality parameters. Methods: The daily QA program was developed to test output, spot size and position, proton beam energy, and image guidance using the Sun Nuclear Corporation rf-DQA™3 device and Atlas QA software. The program utilizes standard Atlas linear accelerator tests repurposed for proton measurements and a custom jig for indexing the device to the treatment couch. The monthly QA program was designed to test mechanical performance, image quality, radiation quality, isocenter coincidence, and safety features. Many of these tests are similar to linear accelerator QA counterparts, but many require customized test design and equipment. Coincidence of imaging, laser marker, mechanical, and radiation isocenters, for instance, is verified using a custom film-based device devised and manufactured at our facility. Proton spot size and position as a function of energy are verified using a custom spot pattern incident on film and analysis software developed in-house. More details concerning the equipment and software developed for monthly QA are included in the supporting document. Thresholds for daily and monthly tests were established via perturbation analysis, early experience, and/or proton system specifications and associated acceptance test results. Results: The periodic QA program described here has been in effect for approximately 9 months and has proven efficient and sensitive to sub-clinical variations in treatment delivery characteristics. Conclusion: Tools and professional guidelines for periodic proton system QA are not as well developed as their photon and electron counterparts. The program described here efficiently evaluates key quality parameters and, while specific to the needs of our facility

Qualification requirements and training programs for nonreactor nuclear facility personnel in the Operations Division of the Oak Ridge National Laboratory

Energy Technology Data Exchange (ETDEWEB)

Preston, E.L.; Culbert, W.H.; Baldwin, M.E.; McCormack, K.E.; Rivera, A.L.; Setaro, J.A.

1985-11-01

This document describes the program for training, retraining, and qualification of nonreactor nuclear operators in the Operations Division of the Oak Ridge National Laboratory. The objective of the program is to provide the Operators and Supervisors of nuclear facilities the knowledge and skills needed to perform assigned duties in a safe and efficient manner and to comply with US Department of Energy Order 5480.1A Chapter V. This order requires DOE nuclear facilities to maintain formal training programs for their operating staff and documentation of that training.

Qualification requirements and training programs for nonreactor nuclear facility personnel in the Operations Division of the Oak Ridge National Laboratory

International Nuclear Information System (INIS)

Preston, E.L.; Culbert, W.H.; Baldwin, M.E.; McCormack, K.E.; Rivera, A.L.; Setaro, J.A.

1985-11-01

This document describes the program for training, retraining, and qualification of nonreactor nuclear operators in the Operations Division of the Oak Ridge National Laboratory. The objective of the program is to provide the Operators and Supervisors of nuclear facilities the knowledge and skills needed to perform assigned duties in a safe and efficient manner and to comply with US Department of Energy Order 5480.1A Chapter V. This order requires DOE nuclear facilities to maintain formal training programs for their operating staff and documentation of that training

40 CFR 122.24 - Concentrated aquatic animal production facilities (applicable to State NPDES programs, see § 123...

Science.gov (United States)

2010-07-01

... NATIONAL POLLUTANT DISCHARGE ELIMINATION SYSTEM Permit Application and Special NPDES Program Requirements... 40 Protection of Environment 21 2010-07-01 2010-07-01 false Concentrated aquatic animal production facilities (applicable to State NPDES programs, see § 123.25). 122.24 Section 122.24 Protection of...

A proposed emergency management program for acute care facilities in response to a highly virulent infectious disease.

Science.gov (United States)

Petinaux, Bruno; Ferguson, Brandy; Walker, Milena; Lee, Yeo-Jin; Little, Gary; Parenti, David; Simon, Gary

2016-01-01

To address the organizational complexities associated with a highly virulent infectious disease (HVID) hazard, such as Ebola Virus Disease (EVD), an acute care facility should institute an emergency management program rooted in the fundamentals of mitigation, preparedness, response, and recovery. This program must address all known facets of the care of a patient with HVID, from unannounced arrival to discharge. The implementation of such a program not only serves to mitigate the risks from an unrecognized exposure but also serves to prepare the organization and its staff to provide for a safe response, and ensure a full recovery. Much of this program is based on education, training, and infection control measures along with resourcing for appropriate personal protective equipment which is instrumental in ensuring an organized and safe response of the acute care facility in the service to the community. This emergency management program approach can serve as a model in the care of not only current HVIDs such as EVD but also future presentations in our healthcare setting.

LEU-HTR critical experiment program for the PROTEUS facility in Switzerland

International Nuclear Information System (INIS)

Brogli, R.; Bucher, K.H.; Chawla, R.; Foskolos, K.; Luchsinger, H.; Mathews, D.; Sarlos, G.; Seiler, R.

1990-01-01

New critical experiments in the framework of an IAEA Coordinated Research Program on 'Validation of Safety Related Reactor Physics Calculations for Low Enriched HTRs' are planned at the PSI PROTEUS facility. The experiments are designed to supplement the experimental data base and reduce the design and licensing uncertainties for small- and medium-sized helium-cooled reactors using low-enriched uranium (LEU) and graphite high temperature fuel. The main objectives of the new experiments are to provide first-of-a-kind high quality experimental data on: 1) The criticality of simple, easy to interpret, single core region LEU HTR systems for several moderator-to-fuel ratios and several lattice geometries; 2) the changes in reactivity, neutron balance components and control rod effectiveness caused by water ingress into this type of reactor, and 3) the effects of the boron and/or hafnium absorbers that are used to modify the reactivity and the power distributions in typical HTR systems. Work on the design and licensing of the modified PROTEUS critical facility is now in progress with the HTR experiments scheduled to begin early in 1991. Several international partners will be involved in the planning, execution and analysis of these experiments in order to insure that they are relevant and cost effective with respect to the various gas cooled reactor national programs. (author)

LEU-HTR critical experiment program for the PROTEUS facility in Switzerland

Energy Technology Data Exchange (ETDEWEB)

Brogli, R; Bucher, K H; Chawla, R; Foskolos, K; Luchsinger, H; Mathews, D; Sarlos, G; Seiler, R [Paul Scherrer Institute, Laboratory for Reactor Physics and System Technology Wuerenlingen and Villigen, Villigen PSI (Switzerland)

1990-07-01

New critical experiments in the framework of an IAEA Coordinated Research Program on 'Validation of Safety Related Reactor Physics Calculations for Low Enriched HTRs' are planned at the PSI PROTEUS facility. The experiments are designed to supplement the experimental data base and reduce the design and licensing uncertainties for small- and medium-sized helium-cooled reactors using low-enriched uranium (LEU) and graphite high temperature fuel. The main objectives of the new experiments are to provide first-of-a-kind high quality experimental data on: 1) The criticality of simple, easy to interpret, single core region LEU HTR systems for several moderator-to-fuel ratios and several lattice geometries; 2) the changes in reactivity, neutron balance components and control rod effectiveness caused by water ingress into this type of reactor, and 3) the effects of the boron and/or hafnium absorbers that are used to modify the reactivity and the power distributions in typical HTR systems. Work on the design and licensing of the modified PROTEUS critical facility is now in progress with the HTR experiments scheduled to begin early in 1991. Several international partners will be involved in the planning, execution and analysis of these experiments in order to insure that they are relevant and cost effective with respect to the various gas cooled reactor national programs. (author)

Near-facility environmental monitoring

Energy Technology Data Exchange (ETDEWEB)

Schmidt, J.W.; Johnson, A.R.; Markes, B.M.; McKinney, S.M.; Perkins, C.J.

1995-06-01

This section of the 1994 Hanford Site Environmental Report summarizes the routine near-facility environmental monitoring programs which are presently being conducted at the Hanford Site. Several types of environmental media are sampled near nuclear facilities to monitor the effectiveness of waste management and restoration activities, and effluent treatment and control practices. These media include air, surface water and springs, surface contamination, soil and vegetation, investigative sampling (which can include wildlife), and external radiation. Sampling and analysis information and analytical results for 1994 for each of these media are summarized in this section. Additional data and more detailed information may be found in Westinghouse Hanford Company Operational Environmental Monitoring Annual Report, Calendar Year 1994.

DOE LeRC photovoltaic systems test facility

Science.gov (United States)

Cull, R. C.; Forestieri, A. F.

1978-01-01

The facility was designed and built and is being operated as a national facility to serve the needs of the entire DOE National Photovoltaic Program. The object of the facility is to provide a place where photovoltaic systems may be assembled and electrically configured, without specific physical configuration, for operation and testing to evaluate their performance and characteristics. The facility as a breadboard system allows investigation of operational characteristics and checkout of components, subsystems and systems before they are mounted in field experiments or demonstrations. The facility as currently configured consist of 10 kW of solar arrays built from modules, two inverter test stations, a battery storage system, interface with local load and the utility grid, and instrumentation and control necessary to make a flexible operating facility. Expansion to 30 kW is planned for 1978. Test results and operating experience are summaried to show the variety of work that can be done with this facility.

Radiological environmental monitoring programs at Canadian nuclear facilities - a practical model for follow-up activities under the Canadian Environmental Assessment Act

International Nuclear Information System (INIS)

Tamm, J.A.; Zach, R.

2000-01-01

Under the Canadian Environmental Assessment Act (the Act), a federal authority, if it considers it appropriate, is to design a follow-up program for a project undergoing a federal environmental assessment and arrange for implementation of that program. Under the Act a follow-up program means a set of activities for verifying the accuracy of the environmental assessment (EA) of a project and for determining the effectiveness of any measures taken to mitigate any adverse environmental effects resulting from the project. The Act currently does not include regulations, guidelines, standards or procedures regarding the design, content and implementation requirements for follow-up programs (Canadian Environmental Assessment Agency [the Agency] 1999). Uncertainties also exist regarding the roles and responsibilities in designing, implementing, enforcing and auditing such activities. The Agency is presently specifying appropriate activities to address these issues. This paper considers the existing radiological environmental monitoring programs at nuclear facilities. Such programs consist of two types of monitoring-radioactivity releases from the facility via liquid and gaseous waste streams, and radioactivity in the environment at large, beyond the facility's immediate location. Such programs have been developed by AECL, Canadian nuclear utilities and uranium mining companies. Our analysis show that these programs can provide a good model for follow-up programs under the Act. (author)

78 FR 26879 - Medicare Program; Inpatient Rehabilitation Facility Prospective Payment System for Federal Fiscal...

Science.gov (United States)

2013-05-08

... Prospective Payment System for Federal Fiscal Year 2014; Proposed Rule #0;#0;Federal Register / Vol. 78, No... Program; Inpatient Rehabilitation Facility Prospective Payment System for Federal Fiscal Year 2014 AGENCY... IRF prospective payment system's (PPS) case-mix groups and a description of the methodology and data...

Design study of underground facility of the Underground Research Laboratory

International Nuclear Information System (INIS)

Hibiya, Keisuke; Akiyoshi, Kenji; Ishizuka, Mineo; Anezaki, Susumu

1998-03-01

Geoscientific research program to study deep geological environment has been performed by Power Reactor and Nuclear Fuel Development Corporation (PNC). This research is supported by 'Long-Term Program for Research, Development and Utilization of Nuclear Energy'. An Underground Research Laboratory is planned to be constructed at Shoma-sama Hora in the research area belonging to PNC. A wide range of geoscientific research and development activities which have been previously studied at the Tono Area is planned in the laboratory. The Underground Research Laboratory is consisted of Surface Laboratory and Underground Research Facility located from the surface down to depth between several hundreds and 1,000 meters. Based on the results of design study in last year, the design study performed in this year is to investigate the followings in advance of studies for basic design and practical design: concept, design procedure, design flow and total layout. As a study for the concept of the underground facility, items required for the facility are investigated and factors to design the primary form of the underground facility are extracted. Continuously, design methods for the vault and the underground facility are summarized. Furthermore, design procedures of the extracted factors are summarized and total layout is studied considering the results to be obtained from the laboratory. (author)

Benefits of a Dedicated Breastfeeding Facility and Support Program for Exclusive Breastfeeding among Workers in Indonesia.

Science.gov (United States)

Basrowi, Ray W; Sulistomo, Astrid B; Adi, Nuri Purwito; Vandenplas, Yvan

2015-06-01

A mother's working environment is believed to be a major determinant of exclusive breastfeeding (EBF) practice. We aimed to define the influence of a facility dedicated to breastfeeding and a breastfeeding support program at the workplace on breastfeeding practice. A cross-sectional study was performed in five workplaces. The inclusion criteria were female workers whose last child was between 6 and 36 months old. Observational data were obtained and a questionnaire was filled out. The World Health Organization definition for EBF was used. Data from 186 subjects (74 office workers and 112 factory workers) were collected. Just over half (52%) of the mothers were between 20 and 46 years old, 75.3% had graduated from high school and university, 12.9% had more than two children and 36.0% owned a house. The prevalence of EBF during the last 6 months was 32.3%. A proper dedicated breastfeeding facility was available for 21.5% of the mothers, but only 7.5% had been in contact with a breastfeeding support program. The presence of a dedicated breastfeeding facility increased EBF practice almost threefold, by an odds ratio (OR) of 2.74 and a 95% confidence interval (CI) of 1.34-5.64 (pdedicated breastfeeding facility at the workplace as these simple measures significantly increase EBF.

Status and update of the National Ignition Facility radiation effects testing program

International Nuclear Information System (INIS)

Davis, J F; Serduke, F J; Wuest, C R.

1998-01-01

We are progressing in our efforts to make the National Ignition Facility (NIF) available to the nation as a radiation effects simulator to support the Services needs for nuclear hardness and survivability testing and validation. Details of our program were summarized in a paper presented at the 1998 HEART Conference [1]. This paper describes recent activities and updates plans for NIF radiation effects testing. research. Radiation Effects Testing

Facilities evaluation report

International Nuclear Information System (INIS)

Sloan, P.A.; Edinborough, C.R.

1992-04-01

The Buried Waste Integrated Demonstration (BWID) is a program of the Department of Energy (DOE) Office of Technology Development whose mission is to evaluate different new and existing technologies and determine how well they address DOE community waste remediation problems. Twenty-three Technical Task Plans (TTPs) have been identified to support this mission during FY-92; 10 of these have identified some support requirements when demonstrations take place. Section 1 of this report describes the tasks supported by BWID, determines if a technical demonstration is proposed, and if so, identifies the support requirements requested by the TTP Principal Investigators. Section 2 of this report is an evaluation identifying facility characteristics of existing Idaho National Engineering Laboratory (INEL) facilities that may be considered for use in BWID technology demonstration activities

LWR fuel rod testing facilities in high flux reactor (HFT) Petten for investigation of power cycling and ramping behaviour

Energy Technology Data Exchange (ETDEWEB)

Markgraf, J; Perry, D; Oudaert, J [Commission of the European Communities, Joint Reserach Centre, Petten Establishment, Petten (Netherlands)

1983-06-01

LWR fuel rod irradiation experiments are being performed in HFR's Pool Side Facility (PSF) by means of pressurized boiling water capsules (BWFC). For more than 6 years the major application of these devices has been in performing irradiation programs to investigate the power ramp behaviour of PWR and BWR rods which have been pre-irradiated in power reactors. Irradiation devices with various types of monitoring instrumentation are available, e.g. for fuel rod length, fuel stack length, fuel rod internal pressure and fuel rod central temperature measurements. The application scope covers PWR and BWR fuel rods, with burn-up levels up to 45 MWd/kg(U), max. linear heat generation rates up to 700 W/cm and simulation of constant power change rates between 0.05 and 1000 W/cm.min. The paper describes the different designs of LWR fuel rod testing facilities and associated non-destructive testing devices in use at the HFR Petten. It also addresses the new test capabilities that will become available after exchange of the HFR vessel in 1983. Furthermore it shows some typical results. (author)

Quality Assurance of ARM Program Climate Research Facility Data

Energy Technology Data Exchange (ETDEWEB)

Peppler, RA; Kehoe, KE; Sonntag, KL; Bahrmann, CP; Richardson, SJ; Christensen, SW; McCord, RA; Doty, DJ; Wagener, Richard [BNL; Eagan, RC; Lijegren, JC; Orr, BW; Sisterson, DL; Halter, TD; Keck, NN; Long, CN; Macduff, MC; Mather, JH; Perez, RC; Voyles, JW; Ivey, MD; Moore, ST; Nitschke, DL; Perkins, BD; Turner, DD

2008-03-01

This report documents key aspects of the Atmospheric Radiation Measurement (ARM) Climate Research Facility (ACRF) data quality assurance program as it existed in 2008. The performance of ACRF instruments, sites, and data systems is measured in terms of the availability, usability, and accessibility of the data to a user. First, the data must be available to users; that is, the data must be collected by instrument systems, processed, and delivered to a central repository in a timely manner. Second, the data must be usable; that is, the data must be inspected and deemed of sufficient quality for scientific research purposes, and data users must be able to readily tell where there are known problems in the data. Finally, the data must be accessible; that is, data users must be able to easily find, obtain, and work with the data from the central repository. The processes described in this report include instrument deployment and calibration; instrument and facility maintenance; data collection and processing infrastructure; data stream inspection and assessment; the roles of value-added data processing and field campaigns in specifying data quality and haracterizing the basic measurement; data archival, display, and distribution; data stream reprocessing; and engineering and operations management processes and procedures. Future directions in ACRF data quality assurance also are presented.

Quality Assurance of ARM Program Climate Research Facility Data

International Nuclear Information System (INIS)

Peppler, R.A.; Kehoe, K.E.; Sonntag, K.L.; Bahramann, C.P.; Richardson, S.J.; Christensen, S.W.; McCord, R.A.; Doty, D.J.; Wagener, R.; Eagan, R.C.; Lijegren, J.C.; Orr, B.W.; Sisterson, D.L.; Halter, T.D.; Keck, N.N.; Long, C.N.; Macduff, M.C.; Mather, J.H.; Perez, R.C.; Voyles, J.W.; Ivey, M.D.; Moore, S.T.; Nitschke, D.L.; Perkins, B.D.; Turner, D.D.

2008-01-01

This report documents key aspects of the Atmospheric Radiation Measurement (ARM) Climate Research Facility (ACRF) data quality assurance program as it existed in 2008. The performance of ACRF instruments, sites, and data systems is measured in terms of the availability, usability, and accessibility of the data to a user. First, the data must be available to users; that is, the data must be collected by instrument systems, processed, and delivered to a central repository in a timely manner. Second, the data must be usable; that is, the data must be inspected and deemed of sufficient quality for scientific research purposes, and data users must be able to readily tell where there are known problems in the data. Finally, the data must be accessible; that is, data users must be able to easily find, obtain, and work with the data from the central repository. The processes described in this report include instrument deployment and calibration; instrument and facility maintenance; data collection and processing infrastructure; data stream inspection and assessment; the roles of value-added data processing and field campaigns in specifying data quality and characterizing the basic measurement; data archival, display, and distribution; data stream reprocessing; and engineering and operations management processes and procedures. Future directions in ACRF data quality assurance also are presented

CHANDA and ERINDA: Joint European programs for research on safety of nuclear facilities and waste reduction

Energy Technology Data Exchange (ETDEWEB)

Beyer, Roland; Hannaske, Roland; Koegler, Toni [Institut fuer Strahlenphysik, Helmholtz Zentrum DD-Rossendorf, 01328 Dresden (Germany); Institut fuer Kern- und Teilchenphysik, TU Dresden, 01069 Dresden (Germany); Grosse, Eckart [Institut fuer Kern- und Teilchenphysik, TU Dresden, 01069 Dresden (Germany); Junghans, Arnd R. [Institut fuer Strahlenphysik, Helmholtz Zentrum DD-Rossendorf, 01328 Dresden (Germany)

2014-07-01

In spite of the planned termination of the German nuclear power program neutron beam facilities in Germany can contribute considerably to research studies on the reduction of hazards due to nuclear waste. Transnational research programs support EU groups who want to carry out projects at the new tof set-up nELBE at HZDR, the calibrated n-flux at PTB and the FRANZ accelerator under construction at Frankfurt. Vice versa various facilities in the EU offer beams for transmutation and safety related studies with neutrons to German scientists under support by ERINDA (2011-2013) and CHANDA (2014-2017; solving challenges in nuclear data for the safety of European nuclear facilities). For work in that field scientific visits are also fostered to improve the exchange of experience between the partners (13 and in future about 35 from 18 countries). Plans for new projects as well as results obtained so far are discussed, and special emphasis is given to the present research performed at nELBE on neutron scattering and absorption.

Investigations concerning fire-induced accidents in nuclear facilities

International Nuclear Information System (INIS)

Lamuth, P.; Lernout, L.A.; Bonneval, F.; Cottaz, M.

1996-01-01

In the context of fire protection in technical buildings of French nuclear facilities, three principles have been adopted: prevention, detection and fire-fighting. Their implementation makes it possible on the one hand to limit the fire ignition and the fire growth, and on the other hand to prevent fire extent which would lead to unavailability of several safety related equipment. Although progress has been made in this direction, the fire risks have still not been eliminated. It is therefore essential to evaluate the fire effects and to assess their consequences. To this end, three main R and D programs have been conducted into fires. Part I sets out the fire PSA methodology used for a 900 MWe PWR. Part II gives an outline of two fire and ventilation computer codes useful for the fire PSA. Finally, part III gives an outline of the tests already performed and those currently under way in the two laboratories of the Institut de Protection et de Surete Nucleaire (IPSN) in order to qualify the codes and provide useful information for the safety assessment. (author)

Final work plan : supplemental upward vapor intrusion investigation at the former CCC/USDA grain storage facility in Hanover, Kansas.

Energy Technology Data Exchange (ETDEWEB)

LaFreniere, L. M.; Environmental Science Division

2008-12-15

The Commodity Credit Corporation (CCC), an agency of the U.S. Department of Agriculture (USDA), operated a grain storage facility at the northeastern edge of the city of Hanover, Kansas, from 1950 until the early 1970s. During this time, commercial grain fumigants containing carbon tetrachloride were in common use by the grain storage industry to preserve grain in their facilities. In February 1998, trace to low levels of carbon tetrachloride (below the maximum contaminant level [MCL] of 5.0 {micro}g/L) were detected in two private wells near the former grain storage facility at Hanover, as part of a statewide USDA private well sampling program that was implemented by the Kansas Department of Health and Environment (KDHE) near former CCC/USDA facilities. In 2007, the CCC/USDA conducted near-surface soil sampling at 61 locations and also sampled indoor air at nine residences on or adjacent to its former Hanover facility to address the residents concerns regarding vapor intrusion. Low levels of carbon tetrachloride were detected at four of the nine homes. The results were submitted to the KDHE in October 2007 (Argonne 2007). On the basis of the results, the KDHE requested sub-slab sampling and/or indoor air sampling (KDHE 2007). This Work Plan describes, in detail, the proposed additional scope of work requested by the KDHE and has been developed as a supplement to the comprehensive site investigation work plan that is pending (Argonne 2008). Indoor air samples collected previously from four homes at Hanover were shown to contain the carbon tetrachloride at low concentrations (Table 2.1). It cannot be concluded from these previous data that the source of the detected carbon tetrachloride is vapor intrusion attributable to former grain storage operations of the CCC/USDA at Hanover. The technical objective of the vapor intrusion investigation described here is to assess the risk to human health due to the potential for upward migration of carbon tetrachloride and

The LEU target development and conversion program for the MAPLE reactors and new processing facility

International Nuclear Information System (INIS)

Malkoske, G.R.

2002-01-01

Historically, the production of molybdenum-99 in the NRU research reactors at Chalk River, Canada has been extracted from reactor targets employing highly enriched uranium (HEU). A reliable supply of HEU metal from the United States used in the manufacture of targets for the NRU research reactor has been a key factor to enable MDS Nordion to develop a secure supply of medical isotopes for the international nuclear medicine community. The molybdenum extraction process from HEU targets provides predictable, consistent yields for our high-volume molybdenum production process. Each link of the isotope supply chain, from isotope production to ultimate use by the physician, has been established using this proven and established method of HEU target irradiation and processing to extract molybdenum-99. To ensure a continued reliable and timely supply of medical isotopes, MDS Nordion is completing the construction of two MAPLE reactors and a New Processing Facility. The design of the MAPLE facilities was based on an established process developed by Atomic Energy of Canada Ltd. (AECL) - extraction of isotopes from HEU target material. However, in concert with the global trend to utilize low enriched uranium (LEU) in research reactors, MDS Nordion has launched a three phase LEU Target Development and Conversion Program for the MAPLE facilities. Phase 1, the Initial Feasibility Study, which identified the technical issues to convert the MAPLE reactor targets from HEU to LEU for large scale commercial production was reported on at the RERTR- 2000 conference. The second phase of the LEU Target Development and Conversion Program was developed with extensive consultation and involvement of experts knowledgeable in target development, process system design, enriched uranium conversion chemistry and commercial scale reactor operations and molybdenum production. This paper will provide an overview of the Phase 2 Conversion Development Program, report on progress to date, and further

Investigation on candidates of principal facilities for exposure dose to public for the facilities using nuclear material

International Nuclear Information System (INIS)

Shimazaki, Yosuke; Sawahata, Hiroaki; Takada, Shoji; Fujimoto, Nozomu

2015-01-01

HTTR holds the nuclear fuel material use facilities in its reactor facilities, for the purpose of study on the fracture behavior of fuel and release behavior of fission products, development of high-performance fuel, and measurement of neutron flux. Due to the revision of the 'Act on the regulation of nuclear source material, nuclear fuel material and reactor', the facilities having the 'Important safety-related facilities' among the facilities applicable to the Enforcement Ordinance Article 41 (Article 41 facilities) has come to need to conform to the 'Regulations concerning standards for the location, structure, and equipment of used facilities and others'. In this case, actions such as modification by all possible means are required. The nuclear fuel substance use facilities of HTTR correspond to Article 41 facilities. So, whether it is a candidate for the 'Important safety-related facilities' has been examined. As a result, it is confirmed that the facilities are not correspond to the 'Important safety-related facilities', and it has been concluded that modification measures for the purpose of conforming to this approval standard rule are not necessary as of the present. (A.O.)

Standards for psychological assessment of nuclear facility personnel. Technical report

International Nuclear Information System (INIS)

Frank, F.D.; Lindley, B.S.; Cohen, R.A.

1981-07-01

The subject of this study was the development of standards for the assessment of emotional instability in applicants for nuclear facility positions. The investigation covered all positions associated with a nuclear facility. Conclusions reached in this investigation focused on the ingredients of an integrated selection system including the use of personality tests, situational simulations, and the clinical interview; the need for professional standards to ensure quality control; the need for a uniform selection system as organizations vary considerably in terms of instruments presently used; and the need for an on-the-job behavioral observation program

Standard guide for establishing a quality assurance program for uranium conversion facilities

CERN Document Server

American Society for Testing and Materials. Philadelphia

2004-01-01

1.1 This guide provides guidance and recommended practices for establishing a comprehensive quality assurance program for uranium conversion facilities. 1.2 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate health and safety practices and determine the applicability of regulatory limitations prior to use. 1.3 The basic elements of a quality assurance program appear in the following order: FUNCTION SECTION Organization 5 Quality Assurance Program 6 Design Control 7 Instructions, Procedures & Drawings 8 Document Control 9 Procurement 10 Identification and Traceability 11 Processes 12 Inspection 13 Control of Measuring and Test Equipment 14 Handling, Storage and Shipping 15 Inspection, Test and Operating Status 16 Control of Nonconforming Items 17 Corrective Actions 18 Quality Assurance Records 19 Audits 20 TABLE 1 NQA-1 Basic Requirements Relat...

The Abbott School Construction Program: Report on the NJ Department of Education Proposed Regulations on Long-Range Facilities Plans

Science.gov (United States)

Ponessa, Joan

2004-01-01

This report on Long Range Facilities Plans (LRFPs) analyzes regulations proposed by the New Jersey Department of Education (NJDOE) to implement the Educational Facilities Construction and Financing Act. (EFCFA). EFCFA, which authorizes and governs New Jersey's public school construction program, was enacted in July 2000 to implement the State…

Facility effluent monitoring plan for the 324 Facility

International Nuclear Information System (INIS)

1994-11-01

The 324 Facility [Waste Technology Engineering Laboratory] in the 300 Area primarily supports the research and development of radioactive and nonradioactive waste vitrification technologies, biological waste remediation technologies, spent nuclear fuel studies, waste mixing and transport studies, and tritium development programs. All of the above-mentioned programs deal with, and have the potential to, release hazardous and/or radioactive material. The potential for discharge would primarily result from (1) conducting research activities using the hazardous materials, (2) storing radionuclides and hazardous chemicals, and (3) waste accumulation and storage. This report summarizes the airborne and liquid effluents, and the results of the Facility Effluent Monitoring Plan (FEMP) determination for the facility. The complete monitoring plan includes characterizing effluent streams, monitoring/sampling design criteria, a description of the monitoring systems and sample analysis, and quality assurance requirements

Programs for visualization, handling and quantification of PIXE maps at the AGLAE facility

Energy Technology Data Exchange (ETDEWEB)

Pichon, L., E-mail: laurent.pichon@culture.fr [Centre de recherche et de restauration des musées de France, C2RMF, Palais du Louvre – Porte des Lions, 14 Quai François Mitterrand, 75001 Paris (France); Fédération de recherche NewAGLAE, FR3506 CNRS, Ministère de la Culture et de la Communication, Chimie ParisTech, Palais du Louvre, 75001 Paris (France); Calligaro, T. [Centre de recherche et de restauration des musées de France, C2RMF, Palais du Louvre – Porte des Lions, 14 Quai François Mitterrand, 75001 Paris (France); Fédération de recherche NewAGLAE, FR3506 CNRS, Ministère de la Culture et de la Communication, Chimie ParisTech, Palais du Louvre, 75001 Paris (France); PSL Research University, Chimie ParisTech-CNRS, Institut de Recherche Chimie Paris, UMR8247, 75005 Paris (France); Lemasson, Q.; Moignard, B.; Pacheco, C. [Centre de recherche et de restauration des musées de France, C2RMF, Palais du Louvre – Porte des Lions, 14 Quai François Mitterrand, 75001 Paris (France); Fédération de recherche NewAGLAE, FR3506 CNRS, Ministère de la Culture et de la Communication, Chimie ParisTech, Palais du Louvre, 75001 Paris (France)

2015-11-15

The external beam setup of the AGLAE facility has been developed in order to combine PIXE with PIGE, EBS and recently IBIL for the analysis of cultural heritage artefacts. The upgraded external beam end-station integrates five large solid angle X-ray detectors either to reduce the risk of damage on sensitive artworks by decreasing the beam intensity or to routinely acquire elemental maps at various scales. While many programs are available to process PIXE maps acquired with nuclear microprobes, a software to process the major and trace elements PIXE maps point by point using GUPIX is not available. The present paper describes three programs developed for the AGLAE facility to process numerous maps obtained with multiple detectors. AGLAEMAP allows to handle maps and pixel groups within maps, TRAUPIXE to process quantitatively PIXE spectra of all pixels and DATAIMAGING to display the resulting quantitative elemental maps. The benefits of this software suite are demonstrated by processing a dataset acquired on a pellet of geostandard reference material and on a terre mêlée pottery shard sample created by the famous ceramist Bernard Palissy (1510–1589), highlighting chemical elements present in this polychrome ceramic.

Programs for visualization, handling and quantification of PIXE maps at the AGLAE facility

International Nuclear Information System (INIS)

Pichon, L.; Calligaro, T.; Lemasson, Q.; Moignard, B.; Pacheco, C.

2015-01-01

The external beam setup of the AGLAE facility has been developed in order to combine PIXE with PIGE, EBS and recently IBIL for the analysis of cultural heritage artefacts. The upgraded external beam end-station integrates five large solid angle X-ray detectors either to reduce the risk of damage on sensitive artworks by decreasing the beam intensity or to routinely acquire elemental maps at various scales. While many programs are available to process PIXE maps acquired with nuclear microprobes, a software to process the major and trace elements PIXE maps point by point using GUPIX is not available. The present paper describes three programs developed for the AGLAE facility to process numerous maps obtained with multiple detectors. AGLAEMAP allows to handle maps and pixel groups within maps, TRAUPIXE to process quantitatively PIXE spectra of all pixels and DATAIMAGING to display the resulting quantitative elemental maps. The benefits of this software suite are demonstrated by processing a dataset acquired on a pellet of geostandard reference material and on a terre mêlée pottery shard sample created by the famous ceramist Bernard Palissy (1510–1589), highlighting chemical elements present in this polychrome ceramic.

Safe shutdown of Defense Program facilities at the Mound Plant, Miamisburg, Ohio

International Nuclear Information System (INIS)

Anderson, H.F.; Bantz, P.D.; Luthy, D.F.

1996-01-01

The Mound Plant was one of several production sites in the US Department of Energy's Defense Programs (DP) Weapons Complex. As a result of the downsizing of the weapons program, certain operations at Mound are being transferred to other DOE sites and the DP buildings at Mound are being shutdown. The objectives of the program are to reduce the hazardous and financial liabilities to DOE and to foster the reuse of facilities for economic development. The overall program is described. The process began with the categorization of excess DP buildings into three groups depending on their anticipated future use. The draft DOE/EM-60 Acceptance Criteria were used to develop a detailed shutdown checklist as the foundation of the process. The overall program budget, schedule, ad options for disposition of materials and components is presented. Accomplishments in FY94 and FY95 are described. By the end of FY95, all excess energetic materials and components, all excess chemicals (from non-radiation areas) and significant amounts of radioactive materials have been removed from the site. By the end of FY95, 47 of the 72 buildings in the program have been taken through all ten of the draft EM-60 acceptance criteria. Lessons learned, based on experience at Mound to date, are summarized

Tetraphenylpyrimidine-Based AIEgens: Facile Preparation, Theoretical Investigation and Practical Application

Directory of Open Access Journals (Sweden)

Junkai Liu

2017-10-01

Full Text Available Aggregation-induced emission (AIE has become a hot research area and tremendous amounts of AIE-active luminogens (AIEgens have been generated. To further promote the development of AIE, new AIEgens are highly desirable. Herein, new AIEgens based on tetraphenylpyrimidine (TPPM are rationally designed according to the AIE mechanism of restriction of intramolecular motion, and facilely prepared under mild reaction conditions. The photophysical property of the generated TPPM, TPPM-4M and TPPM-4P are systematically investigated and the results show that they feature the aggregation-enhanced emission (AEE characteristics. Theoretical study shows the high-frequency bending vibrations in the central pyrimidine ring of TPPM derivatives dominate the nonradiative decay channels. Thanks to the AEE feature, their aggregates can be used to detect explosives with super-amplification quenching effects, and the sensing ability is higher than typical AIE-active tetraphenylethene. It is anticipated that TPPM derivatives could serve as a new type of widely used AIEgen based on their facile preparation and good thermo-, photo- and chemostabilities.

Decommissioning of surplus facilities at ORNL

International Nuclear Information System (INIS)

Myrick, T.E.; Coobs, J.H.

1985-01-01

The Surplus Facilities Management Program (SFMP) at Oak Ridge National Laboratory (ORNL) is part of the Department of Energy's (DOE) National SFMP, administered by the Richland Operations Office. This program was established to provide for the management of certain DOE surplus radioactively contaminated facilities from the end of their operating life until final facility disposition is completed. As part of this program, the ORNL SFMP oversees some 75 facilities, ranging in complexity from abandoned waste storage tanks to large experimental reactors. This paper describes the scope of the ORNL program and outlines the decommissioning activities currently underway, including a brief description of the decontamination techniques being utilized. 4 refs., 3 figs., 2 tabs

Minnesota's Nursing Facility Performance-Based Incentive Payment Program: An Innovative Model for Promoting Care Quality

Science.gov (United States)

Cooke, Valerie; Arling, Greg; Lewis, Teresa; Abrahamson, Kathleen A.; Mueller, Christine; Edstrom, Lisa

2010-01-01

Purpose: Minnesota's Nursing Facility Performance-Based Incentive Payment Program (PIPP) supports provider-initiated projects aimed at improving care quality and efficiency. PIPP moves beyond conventional pay for performance. It seeks to promote implementation of evidence-based practices, encourage innovation and risk taking, foster collaboration…

A new test facility for the E-ELT infrared detector program

Science.gov (United States)

Lizon, Jean Louis; Amico, Paola; Brinkmann, Martin; Delabre, Bernard; Finger, Gert; Guidolin, Ivan Maria; Guzman, Ronald; Hinterschuster, Renate; Ives, Derek; Klein, Barbara; Quattri, Marco

2016-08-01

During the development of the VLT instrumentation program, ESO acquired considerable expertise in the area of infrared detectors, their testing and optimizing their performance. This can mainly be attributed to a very competent team and most importantly to the availability of a very well suited test facility, namely, IRATEC. This test facility was designed more than 15 years ago, specifically for 1K × 1K detectors such as the Aladdin device, with a maximum field of only 30 mm square. Unfortunately, this facility is no longer suited for the testing of the new larger format detectors that are going to be used to equip the future E-ELT instruments. It is projected that over the next 20 years, there will be of the order of 50-100 very large format detectors to be procured and tested for use with E-ELT first and second generation instruments and VLT third generation instruments. For this reason ESO has initiated the in-house design and construction of a dedicated new IR detector arrays test facility: the Facility for Infrared Array Testing (FIAT). It will be possible to mount up to four 60 mm square detectors in the facility, as well as mosaics of smaller detectors. It is being designed to have a very low thermal background such that detectors with 5.3 μm cut-off material can routinely be tested. The paper introduces the most important use cases for which FIAT is designed: they range from performing routine performance measurements on acquired devices, optimization setups for custom applications (like spot scan intra-pixel response, persistence and surface reflectivity measurements), test of new complex operation modes (e.g. high speed subwindowing mode for low order sensing, flexure control, etc.) and the development of new tests and calibration procedures to support the scientific requirements of the E-ELT and to allow troubleshooting the unexpected challenges that arise when a new detector system is brought online. The facility is also being designed to minimize

The influences of Taiwan's National Health Insurance on women's choice of prenatal care facility: Investigation of differences between rural and non-rural areas

Directory of Open Access Journals (Sweden)

Chen Chi-Liang

2008-03-01

Full Text Available Abstract Background Taiwan's National Health Insurance (NHI, implemented in 1995, substantially increased the number of health care facilities that can deliver free prenatal care. Because of the increase in such facilities, it is usually assumed that women would have more choices regarding prenatal care facilities and thus experience reduction in travel cost. Nevertheless, there has been no research exploring these issues in the literature. This study compares how Taiwan's NHI program may have influenced choice of prenatal care facility and perception regarding convenience in transportation for obtaining such care for women in rural and non-rural areas in Taiwan. Methods Based on data collected by a national survey conducted by Taiwan's National Health Research Institutes (NHRI in 2000, we tried to compare how women chose prenatal care facility before and after Taiwan's National Health Insurance program was implemented. Basing our analysis on how women answered questionnaire items regarding "the type of major health care facility used and convenience of transportation to and from prenatal care facility," we investigated whether there were disparities in how women in rural and non-rural areas chose prenatal care facilities and felt about the transportation, and whether the NHI had different influences for the two groups of women. Results After NHI, women in rural areas were more likely than before to choose large hospitals for prenatal care services. For women in rural areas, the relative probability of choosing large hospitals to choosing non-hospital settings in 1998–1999 was about 6.54 times of that in 1990–1992. In contrast, no such change was found in women in non-rural areas. For a woman in a non-rural area, she was significantly more likely to perceive the transportation to and from prenatal care facilities to be very convenient between 1998 and 1999 than in the period between 1990 and 1992. No such improvement was found for women in

Investigating attitudes to hydrogen refuelling facilities and the social cost to local residents

International Nuclear Information System (INIS)

O'Garra, Tanya; Mourato, Susana; Pearson, Peter

2008-01-01

Vehicles fuelled by hydrogen (H 2 ) have attracted increasing attention because of their potentially enhanced environmental profiles. Their penetration into the vehicle stock will be influenced by the spread of refuelling facilities. This study investigates local attitudes towards the proposed installation of H 2 storage facilities at existing refuelling stations throughout London. Using multinomial logit analysis, we identify the determinants of attitudes. Results suggest that residents living very close to a proposed H 2 facility are less likely to be opposed than residents living 200-500 m away. Opposition appears to be determined by a lack of trust in safety regulations, non-environmental attitudes, and concerns about the existing local refuelling station. The social cost to local residents of a local H 2 storage facility was estimated using a method developed by Atkinson et al. [2004. 'Amenity' or 'eyesore'? Negative willingness to pay for options to replace electricity transmission towers. Applied Economics Letters 11(4), 203-208], which elicits the amount of time respondents are willing to commit to oppose a new facility development. Using the leisure rate of time, the social cost is estimated at just under Pounds 14 per local opposed resident. Add to this the WTP to support opposition efforts by a local group, and the value comes to just under Pounds 25 per opposed resident

Helios, a 20 TW CO2 laser fusion facility

International Nuclear Information System (INIS)

Ladish, J.S.

1979-01-01

Since June 1978 the Los Alamos Scientific Laboratory's Helios CO 2 laser fusion facility has been committed to an experimental target program to investigate the feasibility of laser produced inertial confinement fusion. This system is briefly described, and preliminary experimental results are reported

User Facilities: The Education of New Neutron Users

International Nuclear Information System (INIS)

Hernandez, Yamali; Brown, Craig M.

2009-01-01

Neutron scattering is a particularly useful tool enabling the study of compositional, structural and dynamical properties of materials down to the atomic scale. Due to the complexity of operating an intense source of neutrons, this technique is primarily practiced at large national facilities that cater to the research needs of chemists, biologists, physicists, engineers, and material scientists in general. In particular, these user facilities provide specialized instrumentation along with the scientific and technical support required to efficiently utilize it. Since neutron scattering experiments are performed at central facilities rather than in the home-laboratories of individual investigators, the facilities themselves must play a key role in the education and development of new users. The role of neutron scattering facilities in educating young scientists will be examined using examples from current programs at the National Institute of Standards and Technology Center for Neutron Research.

Energy management: a program of energy conservation for the community college facility. [Handbook

Energy Technology Data Exchange (ETDEWEB)

Various Authors

1978-01-01

This handbook developes helps for assessing and improving the energy efficiency of the community-college facility. The TEEM approach (Total Educational Energy Management) is a labor-intensive approach which requires the commitment and participation of all segments of the college community. The TEEM program presented here defines a series of tasks selected, ordered, and implemented in such a way as to achieve two basic objectives: (1) reducing campus energy requirements, and (2) meeting those reduced energy requirements more efficiently without adversely affecting the quality of educational programs. This guide to large-scale energy conservation on college campuses includes step-by-step procedures for establishing a program task force, defining specific tasks, and assigning responsibilities. Action plans are developed, energy consumption monitored, goals set, and conservation measures implemented. A series of appendices provides more detailed information, charts, and worksheets related to all aspects of energy use. The TEEM program provides the basic structure for achieving a significant reduction in campus energy costs.

Data gathering in support of phase O program for waste heat utilization from nuclear enrichment facilities, Ohio

International Nuclear Information System (INIS)

1978-01-01

The gathering of demographic, community development, and economic data for the region impacted by the Pikeville (Ohio) Nuclear Enrichment Facility is described. These data are to be used for establishing possible community uses, e.g., space heating, domestic water heating, and industrial uses, of waste heat from the facility. It was concluded that although the economic feasibility of such waste heat utilization remains to be proven, the community would cooperate in a feasibility demonstration program

Inpatient Psychiatric Facility Follow-Up After Hospitalization for Mental Illness (FUH) Quality Measure Data – by Facility

Data.gov (United States)

U.S. Department of Health & Human Services — Psychiatric facilities that are eligible for the Inpatient Psychiatric Facility Quality Reporting (IPFQR) program are required to meet all program requirements,...

340 Facility maintenance implementation plan

International Nuclear Information System (INIS)

1995-03-01

This Maintenance Implementation Plan (MIP) has been developed for maintenance functions associated with the 340 Facility. This plan is developed from the guidelines presented by Department of Energy (DOE) Order 4330.4B, Maintenance Management Program (DOE 1994), Chapter II. The objective of this plan is to provide baseline information for establishing and identifying Westinghouse Hanford Company (WHC) conformance programs and policies applicable to implementation of DOE order 4330.4B guidelines. In addition, this maintenance plan identifies the actions necessary to develop a cost-effective and efficient maintenance program at the 340 Facility. Primary responsibility for the performance and oversight of maintenance activities at the 340 Facility resides with Westinghouse Hanford Company (WHC). Maintenance at the 340 Facility is performed by ICF-Kaiser Hanford (ICF-KH) South Programmatic Services crafts persons. This 340 Facility MIP provides interface requirements and responsibilities as they apply specifically to the 340 Facility. This document provides an implementation schedule which has been developed for items considered to be deficient or in need of improvement. The discussion sections, as applied to implementation at the 340 Facility, have been developed from a review of programs and practices utilizing the graded approach. Biennial review and additional reviews are conducted as significant programmatic and mission changes are made. This document is revised as necessary to maintain compliance with DOE requirements

340 Facility maintenance implementation plan

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-03-01

This Maintenance Implementation Plan (MIP) has been developed for maintenance functions associated with the 340 Facility. This plan is developed from the guidelines presented by Department of Energy (DOE) Order 4330.4B, Maintenance Management Program (DOE 1994), Chapter II. The objective of this plan is to provide baseline information for establishing and identifying Westinghouse Hanford Company (WHC) conformance programs and policies applicable to implementation of DOE order 4330.4B guidelines. In addition, this maintenance plan identifies the actions necessary to develop a cost-effective and efficient maintenance program at the 340 Facility. Primary responsibility for the performance and oversight of maintenance activities at the 340 Facility resides with Westinghouse Hanford Company (WHC). Maintenance at the 340 Facility is performed by ICF-Kaiser Hanford (ICF-KH) South Programmatic Services crafts persons. This 340 Facility MIP provides interface requirements and responsibilities as they apply specifically to the 340 Facility. This document provides an implementation schedule which has been developed for items considered to be deficient or in need of improvement. The discussion sections, as applied to implementation at the 340 Facility, have been developed from a review of programs and practices utilizing the graded approach. Biennial review and additional reviews are conducted as significant programmatic and mission changes are made. This document is revised as necessary to maintain compliance with DOE requirements.

Report of an investigation into deterioration of the Plutonium Fuel Form Fabrication Facility (PuFF) at the DOE Savannah River Site

Energy Technology Data Exchange (ETDEWEB)

1991-10-01

This investigations of the Savannah River Site's Plutonium Fuel Form fabrication facility located in Building 235-F was initiated in April 1991. The purpose of the investigation was to determine whether, as has been alleged, operation of the facility's argon inert gas system was terminated with the knowledge that continued inoperability of the argon system would cause accelerated corrosion damage to the equipment in the plutonium 238 processing cells. The investigation quickly established that the decision to discontinue operation of the argon system, by not repairing it, was merely one of the measures, and not the most important one, which led to the current deteriorated state of the facility. As a result, the scope of the investigation was broadened to more identify and assess those factors which contributed to the facility's current condition. This document discusses the backgrounds, results, and recommendations of this investigation.

Report of an investigation into deterioration of the Plutonium Fuel Form Fabrication Facility (PuFF) at the DOE Savannah River Site

International Nuclear Information System (INIS)

1991-10-01

This investigations of the Savannah River Site's Plutonium Fuel Form fabrication facility located in Building 235-F was initiated in April 1991. The purpose of the investigation was to determine whether, as has been alleged, operation of the facility's argon inert gas system was terminated with the knowledge that continued inoperability of the argon system would cause accelerated corrosion damage to the equipment in the plutonium 238 processing cells. The investigation quickly established that the decision to discontinue operation of the argon system, by not repairing it, was merely one of the measures, and not the most important one, which led to the current deteriorated state of the facility. As a result, the scope of the investigation was broadened to more identify and assess those factors which contributed to the facility's current condition. This document discusses the backgrounds, results, and recommendations of this investigation

Nuclear criticality safety assessment of the Consolidated Edison Uranium-Solidification Program Facility

International Nuclear Information System (INIS)

Thomas, J.T.

1984-01-01

A nuclear criticality assessment of the Consolidated Edison Uranium-Solidification Program facility confirms that all operations involved in the process may be conducted with an acceptable margin of subcriticality. Normal operation presents no concern since subcriticality is maintained by design. Several recommendations are presented to prevent, or mitigate the consequences of, any abnormal events that might occur in the various portions of the process. These measures would also serve to reduce to a minimum the administrative controls required to prevent criticality

Final work plan : investigation of potential contamination at the former USDA facility in Powhattan, Kansas.

Energy Technology Data Exchange (ETDEWEB)

LaFreniere, L. M.; Environmental Science Division

2007-02-02

This Work Plan outlines the scope of work to be conducted to investigate the subsurface contaminant conditions at the property formerly leased by the Commodity Credit Corporation (CCC) in Powhattan, Kansas (Figure 1.1). Data obtained during this event will be used to (1) evaluate potential contaminant source areas on the property; (2) determine the vertical and horizontal extent of potential contamination; and (3) provide recommendations for future action, with the ultimate goal of assigning this site No Further Action status. The planned investigation includes groundwater monitoring requested by the Kansas Department of Health and Environment (KDHE), in accordance with Section V of the Intergovernmental Agreement between the KDHE and the Farm Service Agency of the U.S. Department of Agriculture (USDA). The work is being performed on behalf of the CCC/USDA by the Environmental Science Division of Argonne National Laboratory. A nonprofit, multidisciplinary research center operated by the University of Chicago for the U.S. Department of Energy, Argonne provides technical assistance to the CCC/USDA with environmental site characterization and remediation at former CCC/USDA grain storage facilities. Argonne issued a Master Work Plan (Argonne 2002) that has been approved by the KDHE. The Master Work Plan describes the general scope of all investigations at former CCC/USDA facilities in Kansas and provides guidance for these investigations. It should be consulted for the complete details of plans for work associated with the former CCC/USDA facility at Powhattan.

Project description: ORNL PWR blowdown heat transfer separate-effects program, Thermal-Hydraulic Test Facility (THTF)

International Nuclear Information System (INIS)

1976-02-01

The ORNL Pressurized-Water Reactor Blowdown Heat Transfer (PWR-BDHT) Program is an experimental separate-effects study of the relations among the principal variables that can alter the rate of blowdown, the presence of flow reversal and rereversal, time delay to critical heat flux, the rate at which dryout progresses, and similar time-related functions that are important to LOCA analysis. Primary test results will be obtained from the Thermal-Hydraulic Test Facility (THTF), a large nonnuclear pressurized-water loop that incorporates a 49-rod electrically heated bundle. Supporting experiments will be carried out in two additional test loops - the Forced Convection Test Facility (FCTF), a small high-pressure facility in which single heater rods can be tested in annular geometry; and an air-water loop which is used to evaluate two-phase flow-measuring instrumentation

Oak Ridge Reservation Federal Facility Agreement: Quarterly report for the Environmental Restoration Program. Volume 2, January--March 1996

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-04-01

This report provides information about ER Program activities conducted on the Oak Ridge Reservation under the Federal Facility Agreement (FFA). Specifically, it includes information on milestones scheduled for completion during the reporting period as well as scheduled for completion during the next reporting period (quarter), accomplishments of the ER Program, concerns related to program work, and scheduled activities for the next quarter. It also provides a listing of the identity and assigned tasks of contractors performing ER Program work under the FFA.

Methods and results of implementing a commercially available videotaped health physics training program in a multi-disciplined DOE facility

International Nuclear Information System (INIS)

O'Neal, B.L.

1979-01-01

Sandia, a prime contractor for DOE, is a multi-disciplined research and development laboratory. Its various activities include the operations of two nuclear reactors, several multi-kilocurie gamma irradiation facilities, a transuranic hot cell facility, various and numerous particle accelerators and x-ray generators, and many other areas involving employees working with or around radioactive materials or radiation producing machines. Since March 1979, Sandia has conducted a formalized basic radiation safety training program using a commercially available videotaped training package. The videotapes are generic in nature and are accompanied with hard copy text material, vu-graphs, quizzes, and an instructor's guide. Sandia's overall training program and the methods, results, and problem areas of implementing an off the shelf, commercially available videotaped training program are described. Results are summarized using an instructor/course/student evaluation form

Nuclear Station Facilities Improvement Planning

International Nuclear Information System (INIS)

Hooks, R. W.; Lunardini, A. L.; Zaben, O.

1991-01-01

An effective facilities improvement program will include a plan for the temporary relocation of personnel during the construction of an adjoining service building addition. Since the smooth continuation of plant operation is of paramount importance, the phasing plan is established to minimize the disruptions in day-to-day station operation and administration. This plan should consider the final occupancy arrangements and the transition to the new structure; for example, computer hookup and phase-in should be considered. The nuclear industry is placing more emphasis on safety and reliability of nuclear power plants. In order to do this, more emphasis is placed on operations and maintenance. This results in increased size of managerial, technical and maintenance staffs. This in turn requires improved office and service facilities. The facilities that require improvement may include training areas, rad waste processing and storage facilities, and maintenance facilities. This paper discusses an approach for developing an effective program to plan and implement these projects. These improvement projects can range in magnitude from modifying a simple system to building a new structure to allocating space for a future project. This paper addresses the planning required for the new structures with emphasis on site location, space allocation, and internal layout. Since facility planning has recently been completed by Sargent and Leyden at six U. S. nuclear stations, specific examples from some of those plants are presented. Site planning and the establishment of long-range goals are of the utmost importance when undertaking a facilities improvement program for a nuclear station. A plan that considers the total site usage will enhance the value of both the new and existing facilities. Proper planning at the beginning of the program can minimize costs and maximize the benefits of the program

Feasibility study for a postaccident heat removal facility

International Nuclear Information System (INIS)

Barts, E.W.; Apperson, C.E. Jr.; Dunwoody, W.E.; Bennett, J.G.

1978-01-01

An initial feasibility investigation for PAHRTEF, a Postaccident Heat Removal Test Facility, is presented. The facility would provide an experimental capability for PAHR experiments beyond that available in any currently existing or proposed U.S. safety test facility. The facility design presented in this report is based upon the technology developed for the ROVER nuclear rocket propulsion program. The core is a graphite-moderated, helium-cooled, epithermal core with radial reflector control. The PAHR experiments are located just below the reactor containment vessel, very near the bottom of the core. The experiments (up to 55% enriched) are driven and controlled by neutrons leaking axially from the core such that the PAHRTEF core and the experiment form a coupled reactor system. The experiment can be designed so that it is extremely unlikely that the test fuel by itself could form a critical system. The investigation indicates that adequate fission heating of large PAHR experiments could be provided at low driver core power levels. Both the reactor and the experiment handling and examination equipment can use available technology and, whenever possible, existing equipment and buildings

Monitored Retrievable Storage conceptual system study: dry receiving and handling facility

International Nuclear Information System (INIS)

1984-01-01

A preconceptual design and estimate for a MRS receiving and handling (R and H) facility at a hypothetical site in the United States are presented. The facility consists of a receiving and handling building plus associated operating buildings, system, and site development features. The R and H building and the supporting buildings and site development features are referred to as the R and H area. Adjoining the R and H area will be an interim waste storage area currently being considered by others. The desirability of building a full capacity (3000-MTU) MRS facility initially versus adding additional capacity at a later date in a phased construction program was investigated. Several advantages of phased construction include incorporation of new designs, modification of receiving-handling-packaging, and changes in regulatory requirements or the waste management program which may develop following startup and operation of an 1800-MTU MRS facility. The cost of a 3000-MTU MRS facility constructed initially was estimated at $193,200,000. If a phased construction program was implemented, including escalation to the mid-point of Phase 2 construction, a capital expenditure of $215,300,000 is estimated - a cost penalty of $22,100,000 or about 11% for phased construction

NRC program of inspection and enforcement

International Nuclear Information System (INIS)

LeDoux, J.C.; Rehfuss, C.

1978-01-01

The Nuclear Regulatory Commission (NRC) regulates civilian uses of nuclear materials to ensure the protection of the public health and safety and the environment. The Office of Inspection and Enforcement (IE) develops and implements the inspection, investigation, and enforcement programs for the NRC. The IE conducts inspection programs for reactors under construction and in operation, nuclear industry vendors, fuel facilities and users of nuclear materials, and all aspects of the safeguarding of facilities and materials. Recently the IE began implementing a program that will place inspectors on site at nuclear power reactors and will provide for national appraisal of licensee performance and for an evaluation of the effectiveness of the inspection programs

Construction program for a large superconducting MHD magnet system at the coal-fired flow facility

International Nuclear Information System (INIS)

Wang, S.T.; Genens, L.; Gonczy, J.; Ludwig, H.; Lieberg, M.; Kraft, E.; Gacek, D.; Huang, Y.C.; Chen, C.J.

1980-01-01

The Argonne National Laboratory has designed and is constructing a 6 T large aperture superconducting MHD magnet for use in the Coal-Fired Flow Facility (CFFF) at the University of Tennessee Space Institute (UTSI) at Tullahoma, Tennessee. The magnet system consists of the superconducting magnet, a magnet power supply, an integrated instrumentation for operation, control and protection, and a complete cryogenic facility including a CTI Model 2800 helium refrigerator/liquefier with two compressors, helium gas handling system and a 7500 liter liquid helium dewar. The complete system will be tested at Argonne, IL in 1981. The magnet design is reviewed, and the coil fabrication programs are described in detail

The effect of facility-based antiretroviral therapy programs on outpatient services in Kenya and Uganda.

Science.gov (United States)

Wollum, Alexandra; Dansereau, Emily; Fullman, Nancy; Achan, Jane; Bannon, Kelsey A; Burstein, Roy; Conner, Ruben O; DeCenso, Brendan; Gasasira, Anne; Haakenstad, Annie; Hanlon, Michael; Ikilezi, Gloria; Kisia, Caroline; Levine, Aubrey J; Masters, Samuel H; Njuguna, Pamela; Okiro, Emelda A; Odeny, Thomas A; Allen Roberts, D; Gakidou, Emmanuela; Duber, Herbert C

2017-08-16

Considerable debate exists concerning the effects of antiretroviral therapy (ART) service scale-up on non-HIV services and overall health system performance in sub-Saharan Africa. In this study, we examined whether ART services affected trends in non-ART outpatient department (OPD) visits in Kenya and Uganda. Using a nationally representative sample of health facilities in Kenya and Uganda, we estimated the effect of ART programs on OPD visits from 2007 to 2012. We modeled the annual percent change in non-ART OPD visits using hierarchical mixed-effects linear regressions, controlling for a range of facility characteristics. We used four different constructs of ART services to capture the different ways in which the presence, growth, overall, and relative size of ART programs may affect non-ART OPD services. Our final sample included 321 health facilities (140 in Kenya and 181 in Uganda). On average, OPD and ART visits increased steadily in Kenya and Uganda between 2007 and 2012. For facilities where ART services were not offered, the average annual increase in OPD visits was 4·2% in Kenya and 13·5% in Uganda. Among facilities that provided ART services, we found average annual OPD volume increases of 7·2% in Kenya and 5·6% in Uganda, with simultaneous annual increases of 13·7% and 12·5% in ART volumes. We did not find a statistically significant relationship between annual changes in OPD services and the presence, growth, overall, or relative size of ART services. However, in a subgroup analysis, we found that Ugandan hospitals that offered ART services had statistically significantly less growth in OPD visits than Ugandan hospitals that did not provide ART services. Our findings suggest that ART services in Kenya and Uganda did not have a statistically significant deleterious effects on OPD services between 2007 and 2012, although subgroup analyses indicate variation by facility type. Our findings are encouraging, particularly given recent recommendations

Fuzzy linear programming based optimal fuel scheduling incorporating blending/transloading facilities

Energy Technology Data Exchange (ETDEWEB)

Djukanovic, M.; Babic, B.; Milosevic, B. [Electrical Engineering Inst. Nikola Tesla, Belgrade (Yugoslavia); Sobajic, D.J. [EPRI, Palo Alto, CA (United States). Power System Control; Pao, Y.H. [Case Western Reserve Univ., Cleveland, OH (United States)]|[AI WARE, Inc., Cleveland, OH (United States)

1996-05-01

In this paper the blending/transloading facilities are modeled using an interactive fuzzy linear programming (FLP), in order to allow the decision-maker to solve the problem of uncertainty of input information within the fuel scheduling optimization. An interactive decision-making process is formulated in which decision-maker can learn to recognize good solutions by considering all possibilities of fuzziness. The application of the fuzzy formulation is accompanied by a careful examination of the definition of fuzziness, appropriateness of the membership function and interpretation of results. The proposed concept provides a decision support system with integration-oriented features, whereby the decision-maker can learn to recognize the relative importance of factors in the specific domain of optimal fuel scheduling (OFS) problem. The formulation of a fuzzy linear programming problem to obtain a reasonable nonfuzzy solution under consideration of the ambiguity of parameters, represented by fuzzy numbers, is introduced. An additional advantage of the FLP formulation is its ability to deal with multi-objective problems.

Atomic physics with highly-charged heavy ions at the GSI future facility: The scientific program of the SPARC collaboration

International Nuclear Information System (INIS)

Stoehlker, Th.; Beier, T.; Beyer, H.F.; Bosch, F.; Braeuning-Demian, A.; Gumberidze, A.; Hagmann, S.; Kozhuharov, C.; Kuehl, Th.; Liesen, D.; Mann, R.; Mokler, P.H.; Quint, W.; Schuch, R.; Warczak, A.

2005-01-01

In the current report a short overview about the envisioned program of the atomic physics research collaboration SPARC (Stored Particle Atomic Research Collaboration, at the new international accelerator Facility for Antiproton and Ion Research (FAIR) at GSI is given. In addition, a condensed description of the planned experimental areas devoted to atomic physics research at the new facility is presented

Access to major overseas research facilities

International Nuclear Information System (INIS)

Bolderman, J. W.

1997-01-01

This paper will describe four schemes which have been established to permit Australian researchers access to some of the most advanced overseas research facilities. These include, access to Major Research Facilities Program, the Australian National Beamline Facility at the Photon Factory, the Australian Synchrotron Research Program and the ISIS Agreement. The details of each of these programs is discussed and the statistics on the scientific output provided. All programs are managed on behalf of the Department of Industry, Science and Tourism by the Australian Nuclear Science and Technology Organisation. One hundred and thirteen senior scientists plus forty, one postgraduate, students were supported through these schemes during the 1996-1997 financial year

Segmented fuel irradiation program: investigation on advanced materials

International Nuclear Information System (INIS)

Uchida, H.; Goto, K.; Sabate, R.; Abeta, S.; Baba, T.; Matias, E. de; Alonso, J.

1999-01-01

The Segmented Fuel Irradiation Program, started in 1991, is a collaboration between the Japanese organisations Nuclear Power Engineering Corporation (NUPEC), the Kansai Electric Power Co., Inc. (KEPCO) representing other Japanese utilities, and Mitsubishi Heavy Industries, Ltd. (MHI); and the Spanish Organisations Empresa Nacional de Electricidad, S.A. (ENDESA) representing A.N. Vandellos 2, and Empresa Nacional Uranio, S.A. (ENUSA); with the collaboration of Westinghouse. The objective of the Program is to make substantial contribution to the development of advanced cladding and fuel materials for better performance at high burn-up and under operational power transients. For this Program, segmented fuel rods were selected as the most appropriate vehicle to accomplish the aforementioned objective. Thus, a large number of fuel and cladding combinations are provided while minimising the total amount of new material, at the same time, facilitating an eventual irradiation extension in a test reactor. The Program consists of three major phases: phase I: design, licensing, fabrication and characterisation of the assemblies carrying the segmented rods (1991 - 1994); phase II: base irradiation of the assemblies at Vandellos 2 NPP, and on-site examination at the end of four cycles (1994-1999). Phase III: ramp testing at the Studsvik facilities and hot cell PIE (1996-2001). The main fuel design features whose effects on fuel behaviour are being analysed are: alloy composition (MDA and ZIRLO vs. Zircaloy-4); tubing texture; pellet grain size. The Program is progressing satisfactorily as planned. The base irradiation is completed in the first quarter of 1999, and so far, tests and inspections already carried out are providing useful information on the behaviour of the new materials. Also, the Program is delivering a well characterized fuel material, irradiated in a commercial reactor, which can be further used in other fuel behaviour experiments. The paper presents the main

User Delay Cost Model and Facilities Maintenance Cost Model for a Terminal Control Area : Volume 3. User's Manual and Program Documentation for the Facilities Maintenance Cost Model

Science.gov (United States)

1978-05-01

The Facilities Maintenance Cost Model (FMCM) is an analytic model designed to calculate expected annual labor costs of maintenance within a given FAA maintenance sector. The model is programmed in FORTRAN IV and has been demonstrated on the CDC Krono...

Investigation of beryllium/steam interaction

Energy Technology Data Exchange (ETDEWEB)

Chekhonadskikh, A.M.; Vurim, A.D.; Vasilyev, Yu.S.; Pivovarov, O.S. [Inst. of Atomic Energy National Nuclear Center of the Republic of Kazakstan Semipalatinsk (Kazakhstan); Shestakov, V.P.; Tazhibayeva, I.L.

1998-01-01

In this report program on investigations of beryllium emissivity and transient processes on overheated beryllium surface attacked by water steam to be carried out in IAE NNC RK within Task S81 TT 2096-07-16 FR. The experimental facility design is elaborated in this Report. (author)

Program for upgrading nuclear materials protection, control, and accounting at all facilities within the All-Russian Institute of Experimental Physics (VNIIEF)

International Nuclear Information System (INIS)

Yuferev, V.; Zhikharev, S.; Yakimov, Y.

1998-01-01

As part of the Department of Energy-Russian program for strengthening nuclear material protection, control, and accounting (MPC and A), plans have now been formulated to install an integrated MPC and A system at all facilities containing large quantities of weapons-usable nuclear material within the All-Russian Institute of Experimental Physics (VNIIEF, Arzamas-16) complex. In addition to storage facilities, the complex houses a number of critical facilities used to conduct nuclear physics research and facilities for developing procedures for disassembly of nuclear weapons

Overview of US fast-neutron facilities and testing capabilities

International Nuclear Information System (INIS)

Evans, E.A.; Cox, C.M.; Jackson, R.J.

1982-01-01

Rather than attempt a cataloging of the various fast neutron facilities developed and used in this country over the last 30 years, this paper will focus on those facilities which have been used to develop, proof test, and explore safety issues of fuels, materials and components for the breeder and fusion program. This survey paper will attempt to relate the evolution of facility capabilities with the evolution of development program which use the facilities. The work horse facilities for the breeder program are EBR-II, FFTF and TREAT. For the fusion program, RTNS-II and FMIT were selected

Evaluation of the Nuclear Medicine facilities in Minas Gerais state: quality control program of equipment

International Nuclear Information System (INIS)

Kubo, Tadeu Takao Almodovar; Biancardi, Rodrigo; Rocha, Adriana Marcia Guimaraes; Ferreira, Denia Romao; Silva, Franciele Aquiles Anjos; Assuncao, Jonathan Buenos Aires; Alves, Ederson Henrique; Almeida, Ana Flavia Batista; Alves, Nathalia Fernandes; Xavier, Faber Henrique Zacarias; Gontijo, Rodrigo Modesto Gadelha; Mamede, Marcelo; Universidade Federal de Minas Gerais

2017-01-01

With the reformulation of the CNEN-NN-3.05 standard in December 2013, Brazil's Nuclear Medicine (NMS) services have to perform a greater number of quality controls for SPECT and PET equipment. However, little is known about the reality of the quality control programs of these services regarding the application of the new standard. Thus, in this context, the objective of the present study was to evaluate the quality control program of MNSs in the state of Minas Gerais. All NMSs in the state of Minas Gerais were invited to participate in the project. Of these, 34.48% (20 facilities) agreed to participate in the project, 50.00% (29 facilities) did not respond to the invitation and 15.52%(9 facilities) declined their participation. Thus, as of November 2015, 20 SPECT and 2 PET/CT equipment were evaluated for the performance of the quality control tests recommended by the new CNEN standard. The phantoms required for the evaluation came from the Laboratory of Dosimetry and Quality Control of UFMG. Even with the deadlines set by CNEN for the implementation of the quality control program in the NMSs, more than 50% of the evaluated services did not implement the quality controls, and the absence of specific phantoms is the main reason for the failure. Among the problems found in the installations, the most critical were: collimators with no conditions of use in the clinical routine, linearity problems of the evaluated image and values of image uniformity superior to the limits of acceptance. Problems in the uniformity and linearity of the image found directly impacted the performance of other tests, such as spatial resolution, SPECT performance, among others. In a general way, the NMSs in the state of Minas Gerais evaluated with the present study are in clinical feasible conditions. (author)

Experimental platforms in support of the ASTRID program: existing and planned facilities - 15126

International Nuclear Information System (INIS)

Gastaldi, O.; Rodriguez, G.; Ayrault, L.; Collard, B.; Dumesnil, J.; Dujet, F.; Journeau, C.; Latge, C.; Sanseigne, E.; Serre, F.; Tkatschenko, I.; Willermoz, G.

2015-01-01

The sodium cooled fast reactors (SFR) French program currently focused on the design of the ASTRID (Advanced Sodium Technological Reactor for Industrial Demonstration) reactor in different fields: energy conversion system, instrumentation for continuous monitoring, In Service Inspection and Repair, core design, fuel handling, thermo hydraulic, severe accidents, large flow electromagnetic pumps... Even if the French experimental prototype implies the development of innovative techniques, concepts and feedback of operations of SFRs are important, the new challenges coming from the objectives to meet GEN-IV requirements need some research and development. To achieve this goal, the generation four French SFR program includes the development of technological platforms with experimental facilities to develop and evaluate innovative options and also qualify some ASTRID specific components. The needs in terms of development, validation and qualification of techniques, components or systems to be used on ASTRID have been reviewed exhaustively in 2014. It allowed to consolidate or to precise the experimental purposes of the four CEA platforms regrouping technological facilities with different strategy of erection. PAPIRUS platform (largely already constructed) is dedicated to in-sodium experimental testing; GISEH platform (also largely already constructed) is devoted to water and air tests in support to hydraulic, thermal-hydraulic and fluid-structure interaction studies; CHEOPS platform (detailed studies and realization contract launched in 2014 aiming at commissioning and start up in 2018) deals with in sodium research and development and some qualifications requiring large scale; and last, PLINIUS-2 platform (commissioning and start up in 2019) concerns prototypic corium behavior studies in severe accident conditions and mitigation device qualification. This paper presents the four platforms and for each of them the experimental needs which are covered by their facilities

The Soreq Applied Research Accelerator Facility (SARAF): Overview, research programs and future plans

Science.gov (United States)

Mardor, Israel; Aviv, Ofer; Avrigeanu, Marilena; Berkovits, Dan; Dahan, Adi; Dickel, Timo; Eliyahu, Ilan; Gai, Moshe; Gavish-Segev, Inbal; Halfon, Shlomi; Hass, Michael; Hirsh, Tsviki; Kaiser, Boaz; Kijel, Daniel; Kreisel, Arik; Mishnayot, Yonatan; Mukul, Ish; Ohayon, Ben; Paul, Michael; Perry, Amichay; Rahangdale, Hitesh; Rodnizki, Jacob; Ron, Guy; Sasson-Zukran, Revital; Shor, Asher; Silverman, Ido; Tessler, Moshe; Vaintraub, Sergey; Weissman, Leo

2018-05-01

The Soreq Applied Research Accelerator Facility (SARAF) is under construction in the Soreq Nuclear Research Center at Yavne, Israel. When completed at the beginning of the next decade, SARAF will be a user facility for basic and applied nuclear physics, based on a 40 MeV, 5 mA CW proton/deuteron superconducting linear accelerator. Phase I of SARAF (SARAF-I, 4 MeV, 2 mA CW protons, 5 MeV 1 mA CW deuterons) is already in operation, generating scientific results in several fields of interest. The main ongoing program at SARAF-I is the production of 30 keV neutrons and measurement of Maxwellian Averaged Cross Sections (MACS), important for the astrophysical s-process. The world leading Maxwellian epithermal neutron yield at SARAF-I (5 × 10^{10} epithermal neutrons/s), generated by a novel Liquid-Lithium Target (LiLiT), enables improved precision of known MACSs, and new measurements of low-abundance and radioactive isotopes. Research plans for SARAF-II span several disciplines: precision studies of beyond-Standard-Model effects by trapping light exotic radioisotopes, such as 6He, 8Li and 18, 19, 23Ne, in unprecedented amounts (including meaningful studies already at SARAF-I); extended nuclear astrophysics research with higher energy neutrons, including generation and studies of exotic neutron-rich isotopes relevant to the rapid (r-) process; nuclear structure of exotic isotopes; high energy neutron cross sections for basic nuclear physics and material science research, including neutron induced radiation damage; neutron based imaging and therapy; and novel radiopharmaceuticals development and production. In this paper we present a technical overview of SARAF-I and II, including a description of the accelerator and its irradiation targets; a survey of existing research programs at SARAF-I; and the research potential at the completed facility (SARAF-II).

Environmental Restoration Program pollution prevention performance measures for FY 1993 and 1994 remedial investigations: Generator training manual

International Nuclear Information System (INIS)

1993-03-01

This computer-based program is designed to help waste generators in the Environmental Restoration (ER) Program prevent pollution at the DOE Oak Ridge Field Office (DOE-OR) facilities in Oak Ridge, Paducah, and Portsmouth. The Numerical Scoring System (NSS) is an interactive system designed to maintain data on ER Program pollution prevention efforts and to measure the success of these efforts through the ER Program life cycle

Environmental Restoration Program pollution prevention performance measures for FY 1993 and 1994 remedial investigations: Management training manual

International Nuclear Information System (INIS)

1993-03-01

This computer-based program is designed to help waste generators in the Environmental Restoration (ER) Program prevent pollution at the DOE Oak Ridge Field Office (DOE-OR) facilities in Oak Ridge, Paducah, and Portsmouth. The Numerical Scoring System (NSS) is an interactive system designed to maintain data on ER Program pollution prevention efforts and to measure the success of these efforts through the ER Program life cycle

Second session: operating European facilities and their programs; Session 2: Les installations Europeennes actuelles et leurs programmes

Energy Technology Data Exchange (ETDEWEB)

Iracane, D. [CEA Saclay, Dir. de l' Energie Nucleaire (DEN), 91 - Gif sur Yvette (France); Porracchia, A.; Fougeras, P.; Morey, J.M. [CEA Cadarache, 13 - Saint-Paul-lez-Durance (France). Dept. d' Etudes des Reacteurs; Loubiere, S.; Durande-Ayme, P. [CEA Saclay, Nuclear Energy Div., Reactors and Nuclear Services Deptment, 91 - Gif-sur-Yvette (France); Guidez, J.; Goux, D. [CEA Valrho, Dir. de l' Energie Nucleaire, DEN, 30 - Marcoule (France); Dupraz, R.; Brand, B. [FRAMATOME, AREVA-FANP, 69 - Lyon (France); Blanc, J.Y. [CEA Saclay, 91 - Gif sur Yvette (France); Perthuis, S. de [FRAMATOME ANP, 92 - Paris-La-Defence (France); Le Rouzic, J.F. [Electricite de France (EDF), 92 - Clamart (France)

2005-07-01

Most European nuclear post-irradiation examination facilities are ageing and the optimization of the remaining infrastructures may lead to connect them through a network implying consistent staff competence between countries and efficient nuclear material transport means. The second article describes the 3 very-low power research reactors operating in France: Minerve, Masurca and Eole. The Osiris reactor is presented in the third article, the author focuses on the devices available in Osiris to perform irradiation in light water reactor conditions and in high temperature reactor conditions and on the associated programs. Phenix reactor located on the Marcoule site had been performing from 1974 to 1990 the necessary technological qualifications required by the fast reactor system. An important upgrading program, led from 1994 to 2003, has allowed the reactor to begin a second life. Its investigation program encompasses research work on the transmutation of actinides and fission products and on new nuclear fuels and materials required for the future fourth generation of reactors. In Europe about 20 hot laboratories offer services to perform examination and qualification required by their national civil nuclear programs. Most are state-owned and show a large range of activities: nuclear fuels, materials, reprocessing, radio-nuclides, and radio-active sources. The last article reviews the main test loops operating in France and in neighboring countries. About 30 installations are reported and classified according to their activity fields : critical heat flux, hydro-mechanics, device testing, accidental situations, helium and severe reactor accidents. (A.C.)

Nuclear physics accelerator facilities

International Nuclear Information System (INIS)

1985-01-01

The Department of Energy's Nuclear Physics program is a comprehensive program of interdependent experimental and theoretical investigation of atomic nuclei. Long range goals are an understanding of the interactions, properties, and structures of atomic nuclei and nuclear matter at the most elementary level possible and an understanding of the fundamental forces of nature by using nuclei as a proving ground. Basic ingredients of the program are talented and imaginative scientists and a diversity of facilities to provide the variety of probes, instruments, and computational equipment needed for modern nuclear research. Approximately 80% of the total Federal support of basic nuclear research is provided through the Nuclear Physics program; almost all of the remaining 20% is provided by the National Science Foundation. Thus, the Department of Energy (DOE) has a unique responsibility for this important area of basic science and its role in high technology. Experimental and theoretical investigations are leading us to conclude that a new level of understanding of atomic nuclei is achievable. This optimism arises from evidence that: (1) the mesons, protons, and neutrons which are inside nuclei are themselves composed of quarks and gluons and (2) quantum chromodynamics can be developed into a theory which both describes correctly the interaction among quarks and gluons and is also an exact theory of the strong nuclear force. These concepts are important drivers of the Nuclear Physics program

The calculation and estimation of wastes generated by decommissioning of nuclear facilities. Tokai works and Ningyo-toge Environmental Engineering Center

International Nuclear Information System (INIS)

Ayame, Y.; Tanabe, T.; Takahashi, K.; Takeda, S.

2001-07-01

This investigation was conducted as a part of planning the low-level radioactive waste management program (LLW management program). The aim of this investigation was contributed to compile the radioactive waste database of JNC's LLW management program. All nuclear facilities of the Tokai works and Ningyo-toge Environmental Engineering Center were investigated in this work. The wastes generated by the decommissioning of each nuclear facility were classified into radioactive waste and others (exempt waste and non-radioactive waste), and the amount of the wastes was estimated. The estimated amounts of radioactive wastes generated by decommissioning of the nuclear facilities are as follows. (1) Tokai works: The amount of waste generated by decommissioning of nuclear facilities of the Tokai works is about 1,079,100 ton. The amount of radioactive waste is about 15,400 ton. The amount of exempt waste and non-radioactive waste is about 1,063,700 ton. (2) Ningyo-toge Environmental Engineering Center: The amount of waste generated by decommissioning of nuclear facilities of Ningyo-toge Environmental Engineering Center is about 112,500 ton. The amount of radioactive waste is about 7,800 ton. The amount of exempt waste and non-radioactive waste is about 104,700 ton. (author)

Oak Ridge Reservation Federal Facility Agreement for the Environmental Restoration Program. Volume 1, Quarterly report, October--December 1995

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-01-01

This Oak Ridge Reservation Federal Facility Agreement Quarterly Report for the Environmental Restoration Program was prepared to satisfy requirements for progress reporting on Environmental Restoration Program (ER) activities as specified in the Oak Ridge Reservation Federal Facility Agreement (FFA) established between the US Department of Energy (DOE), the US Environmental Protection Agency, and the Tennessee Department of Environment and Conservation. The reporting period covered in this document is October through December 1995. This work was performed under Work Breakdown Structure 1.4.12.2.3.04 (Activity Data Sheet 8304). Publication of this document meets two FFA milestones. The FFA Quarterly Report meets an FFA milestone defined as 30 days following the end of the applicable reporting period. Appendix A of this report meets the FFA milestone for the Annual Removal Action Report for the period FYs 1991--95. This document provides information about ER Program activities conducted on the Oak Ridge Reservation under the FFA. Specifically, it includes information on milestones scheduled for completion during the reporting period, as well as scheduled for completion during the next reporting period (quarter); accomplishments of the ER Program; concerns related to program work; and scheduled activities for the next quarter. It also provides a listing of the identity and assigned tasks of contractors performing ER Program work under the FFA.

Access to major overseas research facilities

Energy Technology Data Exchange (ETDEWEB)

Bolderman, J. W. [Australian Nuclear Science and Technology Organisation, Lucas Heights, NSW (Australia)

1997-12-31

This paper will describe four schemes which have been established to permit Australian researchers access to some of the most advanced overseas research facilities. These include, access to Major Research Facilities Program, the Australian National Beamline Facility at the Photon Factory, the Australian Synchrotron Research Program and the ISIS Agreement. The details of each of these programs is discussed and the statistics on the scientific output provided. All programs are managed on behalf of the Department of Industry, Science and Tourism by the Australian Nuclear Science and Technology Organisation. One hundred and thirteen senior scientists plus forty, one postgraduate, students were supported through these schemes during the 1996-1997 financial year. 1 fig.

10 CFR 611.206 - Existing facilities.

Science.gov (United States)

2010-01-01

... 10 Energy 4 2010-01-01 2010-01-01 false Existing facilities. 611.206 Section 611.206 Energy... PROGRAM Facility/Funding Awards § 611.206 Existing facilities. The Secretary shall, in making awards to those manufacturers that have existing facilities, give priority to those facilities that are oldest or...

A Guide for Planning Facilities for Occupational Preparation Programs in Metallurgy Technology. Interim Report. Research 28.

Science.gov (United States)

German, Carl, Jr.

The major purpose of this guide is to elicit the information necessary for writing educational specifications for facilities to house technical education programs in metallurgy. It is organized in these parts: (1) Part I discusses the major purpose, underlying assumptions, recent instructional trends, and guiding principles utilized in the…

Reactor safety issues resolved by the 2D/3D Program

International Nuclear Information System (INIS)

Damerell, P.S.; Simons, J.W.

1993-07-01

The 2D/3D Program studied multidimensional thermal-hydraulics in a PWR core and primary system during the end-of-blowdown and post-blowdown phases of a large-break LOCA (LBLOCA), and during selected small-break LOCA (SBLOCA) transients. The program included tests at the Cylindrical Core Test Facility (CCTF), the Slab Core Test Facility (SCTF), and the Upper Plenum Test Facility (UPTF), and computer analyses using TRAC. Tests at CCTF investigated core thermal-hydraulics and overall system behavior while tests at SCTF concentrated on multidimensional core thermal-hydraulics. The UPTF tests investigated two-phase flow behavior in the downcomer, upper plenum, tie plate region, and primary loops. TRAC analyses evaluated thermal-hydraulic behavior throughout the primary system in tests as well as in PWRs. This report summarizes the test and analysis results in each of the main areas where improved information was obtained in the 2D/3D Program. The discussion is organized in terms of the reactor safety issues investigated

Reliability and safety program plan outline for the operational phase of a waste isolation facility

International Nuclear Information System (INIS)

Ammer, H.G.; Wood, D.E.

1977-01-01

A Reliability and Safety Program plan outline has been prepared for the operational phase of a Waste Isolation Facility. The program includes major functions of risk assessment, technical support activities, quality assurance, operational safety, configuration monitoring, reliability analysis and support and coordination meetings. Detailed activity or task descriptions are included for each function. Activities are time-phased and presented in the PERT format for scheduling and interactions. Task descriptions include manloading, travel, and computer time estimates to provide data for future costing. The program outlined here will be used to provide guidance from a reliability and safety standpoint to design, procurement, construction, and operation of repositories for nuclear waste. These repositories are to be constructed under the National Waste Terminal Storage program under the direction of the Office of Waste Isolation, Union Carbide Corp. Nuclear Division

Microdosimetric investigations at the fast neutron therapy facility at Fermilab

International Nuclear Information System (INIS)

Langen, K.M.

1997-01-01

Microdosimetry was used to investigate three issues at the neutron therapy facility (NTF) at Fermilab. Firstly, the conversion factor from absorbed dose in A-150 tissue equivalent plastic to absorbed dose in ICRU tissue was determined. For this, the effective neutron kerma factor ratios, i.e., oxygen tissue equivalent plastic and carbon to A-150 tissue equivalent plastic, were measured in the neutron beam. An A-150 tissue equivalent plastic to ICRU tissue absorbed dose conversion factor of 0.92 ± 0.04 was determined. Secondly, variations in the radiobiological effectiveness (RBE) in the beam were mapped by determining variations in two related quantities, e * and R, with field size and depth in tissue. Maximal variation in e * and R of 9% and 15% respectively were determined. Lastly, the feasibility of utilizing the boron neutron capture reaction on boron-10 to selectively enhance the tumor dose in the NTF beam was investigated

45 CFR 84.22 - Existing facilities.

Science.gov (United States)

2010-10-01

... HANDICAP IN PROGRAMS OR ACTIVITIES RECEIVING FEDERAL FINANCIAL ASSISTANCE Accessibility § 84.22 Existing facilities. (a) Accessibility. A recipient shall operate its program or activity so that when each part is..., welfare, or other social services at alternate accessible sites, alteration of existing facilities and...

Identifying and Funding the Greatest Needs in School Facilities

Science.gov (United States)

Gorrell, Bob; Salamone, Frank

2012-01-01

How should public school facilities programs allocate limited resources to school facilities needs fairly, cost-effectively, and efficiently while taking into account facility condition, educational adequacy, and other priorities? New Mexico has developed a solution that overcomes key challenges that are common to school facilities programs across…

Nuclear facility decommissioning and site remedial actions: A selected bibliography, Volume 13: Part 1, Main text. Environmental Restoration Program

Energy Technology Data Exchange (ETDEWEB)

Goins, L.F.; Webb, J.R.; Cravens, C.D.; Mallory, P.K.

1992-09-01

This publication contains 1035 abstracted references on environmental restoration, nuclear facility decommissioning, uranium mill tailings management, and site remedial actions. These citations constitute the thirteenth in a series of reports prepared annually for the US Department of Energy (DOE) Environmental Restoration programs. Citations to foreign and domestic literature of all types. There are 13 major sections of the publication, including: (1) DOE Decontamination and Decommissioning Program; (2) Nuclear Facilities Decommissioning; (3) DOE Formerly Utilized Sites Remedial Action Program; (4) DOE Uranium Mill Tailings Remedial Action Project; (5) Uranium Mill Tailings Management; (6) DOE Environmental Restoration Program; (7) DOE Site-Specific Remedial Actions; (8) Contaminated Site Restoration; (9) Remediation of Contaminated Soil and Groundwater; (10) Environmental Data Measurements, Management, and Evaluation; (11) Remedial Action Assessment and Decision-Making; (12) Technology Development and Evaluation; and (13) Environmental and Waste Management Issues. Bibliographic references are arranged in nine subject categories by geographic location and then alphabetically by first author, corporate affiliation, or publication title. Indexes are provided for author, corporate affiliation, title word, publication description, geographic location, subject category, and key word.

Interactive house investigation and radon diagnostics computer program

International Nuclear Information System (INIS)

Gillette, L.M.

1990-01-01

This paper reports on the interactive computer program called Dungeons and Radon which was developed as part of the Environmental Protection Agency's (EPA's) Radon Contractor Proficiency (RCP) Program's Radon Technology for Mitigators (RTM) course which is currently being offered in the Regional Radon Training Centers (RRTCs). The program was designed by Terry Brennan to be used in training radon mitigation contractors. The Macintosh based program consists of a series of animated, sound and voice enhanced house scenes. The participants choose where and what to investigate and where to perform diagnostic tests in order to gather enough information to design a successful mitigation system

Results of the groundwater quality assessment program at the 216-A-29 ditch RCRA facility

International Nuclear Information System (INIS)

Votava, J.M.

1995-01-01

This report presents the findings of the groundwater quality assessment program for the 216-A-29 Ditch. The information presented in this report Ditch have affected the quality of the groundwater in the unconfined aquifer beneath the facility. The results indicate that the 216-A-29 Ditch is the source of elevated specific conductance in well 299-E25-35 and that the source is nonhazardous. This report describes the current monitoring status of the 216-A-29 Ditch, groundwater chemical data interpretation, and recommends the reinstatement of an indicator-evaluation monitoring program in accordance with 40 CFR 265.93(d)(6)

Grande Ronde Endemic Spring Chinook Salmon Supplementation Program: Facility Operation and Maintenance and Monitoring and Evaluation, 2000 Annual Report.

Energy Technology Data Exchange (ETDEWEB)

Boe, Stephen J.; Lofy, Peter T. (Confederated Tribes of the Umatilla Indian Reservation, Pendleton, OR)

2003-03-01

This is the third annual report of a multi-year project to operate adult collection and juvenile acclimation facilities on Catherine Creek and the upper Grande Ronde River for Snake River spring chinook salmon. These two streams have historically supported populations that provided significant tribal and non-tribal fisheries. Supplementation using conventional and captive broodstock techniques is being used to restore fisheries in these streams. Statement of Work Objectives for 2000: (1) Participate in implementation of the comprehensive multiyear operations plan for the Grande Ronde Endemic Spring Chinook Supplementation Program (GRESCP). (2) Plan for recovery of endemic summer steelhead populations in Catherine Creek and the upper Grande Ronde River. (3) Ensure proper construction and trial operation of semi-permanent adult and juvenile facilities for use in 2000. (4) Collect summer steelhead. (5) Collect adult endemic spring chinook salmon broodstock. (6) Acclimate juvenile spring chinook salmon prior to release into the upper Grande Ronde River and Catherine Creek. (7) Document accomplishments and needs to permitters, comanagers, and funding agency. (8) Communicate project results to the scientific community. (9) Plan detailed GRESCP Monitoring and Evaluation for future years. (10) Monitor adult population abundance and characteristics of Grande Ronde River spring chinook salmon populations and incidentally-caught summer steelhead and bull trout. (11) Monitor condition, movement, and mortality of spring chinook salmon acclimated at remote facilities. (12) Monitor water quality at facilities. (13) Participate in Monitoring & Evaluation of the captive brood component of the Program to document contribution to the Program.

Environmental Restoration Program pollution prevention checklist guide for the facility characterization project phase

International Nuclear Information System (INIS)

1993-09-01

A facility characterization (FC) is conducted to determine the nature and extent contamination at a potential hazardous facility waste site. The information gathered during an FC includes (1) data on the volume and chemical nature of the waste, (2) information on the extent of contamination and the migration potential of the contaminants, (3) preliminary information on evaluation of alternative concepts that can or cannot be considered, and (4)supportive technical and cost data. For the purposes of identification, the following operational phases will be used for definition for this phase of the decommissioning and decontamination process (1) facility characterization before clean up, (2) characterization during clean up, (3) characterization of waste materials, and (4) site characterization after clean up. A key consideration in this process is the prevention of any waste to be generated from these characterization activities. The purpose of this checklist guide is to assist users with incorporating pollution prevention/waste minimization (PP/WM) in all FC phase projects of the Environmental Restoration (ER) Program. This guide will help users document PP/WM activities for technology transfer and reporting requirements. Automated computer screens will be created from the checklist data to assist users with implementing and evaluating waste reduction

Spent fuel receipt and lag storage facility for the spent fuel handling and packaging program

International Nuclear Information System (INIS)

Black, J.E.; King, F.D.

1979-01-01

Savannah River Laboratory (SRL) is participating in the Spent Fuel Handling and Packaging Program for retrievable, near-surface storage of spent light water reactor (LWR) fuel. One of SRL's responsibilities is to provide a technical description of the wet fuel receipt and lag storage part of the Spent Fuel Handling and Packaging (SFHP) facility. This document is the required technical description

Final master work plan : environmental investigations at former CCC/USDA facilities in Kansas, 2002 revision.

Energy Technology Data Exchange (ETDEWEB)

Burton, J. C.; Environmental Research

2003-01-23

The Commodity Credit Corporation (CCC) of the U.S. Department of Agriculture (USDA) has entered into an interagency agreement with the U.S. Department of Energy (DOE) under which Argonne National Laboratory provides technical assistance for hazardous waste site characterization and remediation for the CCC/USDA. Carbon tetrachloride is the contaminant of primary concern at sites in Kansas where former CCC/USDA grain storage facilities were located. Argonne applies its QuickSite(reg sign) Expedited Site Characterization (ESC) approach to these former facilities. The QuickSite environmental site characterization methodology is Argonne's proprietary implementation of the ESC process (ASTM 1998). Argonne has used this approach at several former CCC/USDA facilities in Kansas, including Agenda, Agra, Everest, and Frankfort. The Argonne ESC approach revolves around a multidisciplinary, team-oriented approach to problem solving. The basic features and steps of the QuickSite methodology are as follows: (1) A team of scientists with diverse expertise and strong field experience is required to make the process work. The Argonne team is composed of geologists, geochemists, geophysicists, hydrogeologists, chemists, biologists, engineers, computer scientists, health and safety personnel, and regulatory staff, as well as technical support staff. Most of the staff scientists are at the Ph.D. level; each has on average, more than 15 years of experience. The technical team works together throughout the process. In other words, the team that plans the program also implements the program in the field and writes the reports. More experienced scientists do not remain in the office while individuals with lesser degrees or experience carry out the field work. (2) The technical team reviews, evaluates, and interprets existing data for the site and the contaminants there to determine which data sets are technically valid and can be used in initially designing the field program. A basic

EG and G long-range hazardous waste program plan

International Nuclear Information System (INIS)

1985-02-01

The purpose of this document is to develop and implement a program for safe, economic management of hazardous and radioactive mixed waste generated, transported, treated, stored, or disposed of by EG and G Idaho operated facilities. The initial part of this program involves identification and characterization of EG and G-generated hazardous and radioactive mixed waste, and activities for corrective action, including handling, packaging, and shipping of these wastes off site for treatment, storage, and/or disposal, or for interim remedial action. The documentation necessary for all areas of the plan is carefully defined, so as to ensure compliance, at every step, with the requisite orders and guidelines. A second part of this program calls for assessment, and possible development and implementation of a treatment, storage, and disposal (T/S/D) program for special hazardous and radioactive mixed wastes which cannot practically, economically, and safely be disposed of at off-site facilities. This segment of the plan addresses obtaining permits for the existing Waste Experimental Reduction Facility (WERF) incinerator and for the construction of an adjacent hazardous waste solidification facility and a storage area. The permitting and construction of a special hazardous waste treatment and storage facility is also explored. The report investigates permitting the Hazardous Waste Storage Facility (HWSF) as a permanent storage facility

ERDA test facilities, East Mesa Test Site. Geothermal resource investigations, Imperial Valley, California

Energy Technology Data Exchange (ETDEWEB)

1976-01-01

Detailed specifications which must be complied with in the construction of the ERDA Test Facilities at the East Mesa Site for geothermal resource investigations in Imperial Valley, California are presented for use by prospective bidders for the construction contract. The principle construction work includes a 700 gpm cooling tower with its associated supports and equipment, pipelines from wells, electrical equipment, and all earthwork. (LCL)

Investigation on Transmission and Substation Facilities of Sichuan Power Grid in Wenchuan Earthquake

Institute of Scientific and Technical Information of China (English)

Yu Yongqing; Li Guangfan; Li Peng; Zhu Quanjun; Yuan Dalu; Wang Chengyu; Li Jinzhong; Huang Huang; Li Lixin; Zhang Xinghai; Liu Jingmin

2009-01-01

@@ On May 12,2008,an earthquake of Ms 8.0 hit the area around Wenchuan County,Sichuan Province,China.It has been one of the most destructive earthquakes since the founding of P.R.China in 1949.The quake caused not only tremendous loss of life and wealth,but also severe damage to transmission and substation facilities.After the disaster,an expert group from China Electric Power Research Institute (CEPRI)was sent for on-site investigation.This paper is a summary of the investigation,in which suggestions for electric equipment to resist earthquake disasters are also proponed.

University multi-user facility survey-2010.

Science.gov (United States)

Riley, Melissa B

2011-12-01

Multi-user facilities serve as a resource for many universities. In 2010, a survey was conducted investigating possible changes and successful characteristics of multi-user facilities, as well as identifying problems in facilities. Over 300 surveys were e-mailed to persons identified from university websites as being involved with multi-user facilities. Complete responses were received from 36 facilities with an average of 20 years of operation. Facilities were associated with specific departments (22%), colleges (22%), and university research centers (8.3%) or were not affiliated with any department or college within the university (47%). The five most important factors to succeed as a multi-user facility were: 1) maintaining an experienced, professional staff in an open atmosphere; 2) university-level support providing partial funding; 3) broad client base; 4) instrument training programs; and 5) an effective leader and engaged strategic advisory group. The most significant problems were: 1) inadequate university financial support and commitment; 2) problems recovering full service costs from university subsidies and user fees; 3) availability of funds to repair and upgrade equipment; 4) inability to retain highly qualified staff; and 5) unqualified users dirtying/damaging equipment. Further information related to these issues and to fee structure was solicited. Overall, there appeared to be a decline in university support for facilities and more emphasis on securing income by serving clients outside of the institution and by obtaining grants from entities outside of the university.

Experimental investigation of photoreactions in Bonn

International Nuclear Information System (INIS)

Anton, G.

1988-01-01

In this paper the investigation of nuclear photoreactions in Bonn is reviewed. At the new stretcher ring ELSA considerable experimental improvements are possible with an energy tagged photon beam in conjunction with a large acceptance hadron detector. The future program and the new experimental facilities are described

The planning of future research program of underground laboratories in overseas

International Nuclear Information System (INIS)

Honma, Nobuyuki; Tanai, Kenji; Hasegawa, Hiroshi

2002-02-01

The objectives of this study is to identify the research issues, which are to be conducted in the future underground research laboratory, about operation and logistics systems for the planning of future research and development program. The research programs and experiments, etc. were investigated for the geological disposal projects in overseas sedimentary rocks and coastal geological environments aiming to reflect in the future underground research facility plan in Japan. In the investigation, information on the engineered-barrier performance, design and construction of underground facilities, tunnel support, transportation and emplacement, and backfilling technology, etc. were collected. Based on these informations, the purpose, the content, and the result of each investigations and tests were arranged. The strategy and the aim in the entire underground research facility, and the flow of investigations and tests, etc. were also arranged from the purpose, the relations and the sequence of each investigation and experiment, and the usage of results, etc. (author)

Nuclear facility decommissioning and site remedial actions

International Nuclear Information System (INIS)

Knox, N.P.; Webb, J.R.; Ferguson, S.D.; Goins, L.F.; Owen, P.T.

1990-09-01

The 394 abstracted references on environmental restoration, nuclear facility decommissioning, uranium mill tailings management, and site remedial actions constitute the eleventh in a series of reports prepared annually for the US Department of Energy's Remedial Action Programs. Citations to foreign and domestic literature of all types -- technical reports, progress reports, journal articles, symposia proceedings, theses, books, patents, legislation, and research project descriptions -- have been included. The bibliography contains scientific, technical, economic, regulatory, and legal information pertinent to the US Department of Energy's Remedial Action Programs. Major sections are (1) Surplus Facilities Management Program, (2) Nuclear Facilities Decommissioning, (3) Formerly Utilized Sites Remedial Action Programs, (4) Facilities Contaminated with Naturally Occurring Radionuclides, (5) Uranium Mill Tailings Remedial Action Program, (6) Grand Junction Remedial Action Program, (7) Uranium Mill Tailings Management, (8) Technical Measurements Center, (9) Remedial Action Program, and (10) Environmental Restoration Program. Within these categories, references are arranged alphabetically by first author. Those references having no individual author are listed by corporate affiliation or by publication title. Indexes are provided for author, corporate affiliation, title word, publication description, geographic location, subject category, and keywords. This report is a product of the Remedial Action Program Information Center (RAPIC), which selects and analyzes information on remedial actions and relevant radioactive waste management technologies

Nuclear facility decommissioning and site remedial actions

Energy Technology Data Exchange (ETDEWEB)

Knox, N.P.; Webb, J.R.; Ferguson, S.D.; Goins, L.F.; Owen, P.T.

1990-09-01

The 394 abstracted references on environmental restoration, nuclear facility decommissioning, uranium mill tailings management, and site remedial actions constitute the eleventh in a series of reports prepared annually for the US Department of Energy's Remedial Action Programs. Citations to foreign and domestic literature of all types -- technical reports, progress reports, journal articles, symposia proceedings, theses, books, patents, legislation, and research project descriptions -- have been included. The bibliography contains scientific, technical, economic, regulatory, and legal information pertinent to the US Department of Energy's Remedial Action Programs. Major sections are (1) Surplus Facilities Management Program, (2) Nuclear Facilities Decommissioning, (3) Formerly Utilized Sites Remedial Action Programs, (4) Facilities Contaminated with Naturally Occurring Radionuclides, (5) Uranium Mill Tailings Remedial Action Program, (6) Grand Junction Remedial Action Program, (7) Uranium Mill Tailings Management, (8) Technical Measurements Center, (9) Remedial Action Program, and (10) Environmental Restoration Program. Within these categories, references are arranged alphabetically by first author. Those references having no individual author are listed by corporate affiliation or by publication title. Indexes are provided for author, corporate affiliation, title word, publication description, geographic location, subject category, and keywords. This report is a product of the Remedial Action Program Information Center (RAPIC), which selects and analyzes information on remedial actions and relevant radioactive waste management technologies.

28 CFR 54.410 - Comparable facilities.

Science.gov (United States)

2010-07-01

... 28 Judicial Administration 2 2010-07-01 2010-07-01 false Comparable facilities. 54.410 Section 54... in Education Programs or Activities Prohibited § 54.410 Comparable facilities. A recipient may provide separate toilet, locker room, and shower facilities on the basis of sex, but such facilities...

SITE: a methodology for assessment of energy facility siting patterns. Regional studies program

International Nuclear Information System (INIS)

Frigerio, N.A.; Habegger, L.J.; King, R.F.; Hoover, L.J.; Clark, N.A.; Cobian, J.M.

1975-08-01

The timely development of the nation's energy production capacity in a manner that minimizes potential adverse local and regional impacts associated with energy facilities requires the use of sophisticated techniques for evaluation of siting alternatives and fuel cycle options. This report is a documentation of the computerized SITE methodology that has been developed for evaluating health, environmental, and socioeconomic impacts related to utilization of alternate sites for energy production within a region of interest. The cost, impact, and attribute vectors, which are generated and displayed on density maps, can be used in a multiparameter overlay process to identify preferable siting areas. The assessment of clustered facilities in energy centers is also possible within the SITE analysis framework. An application of the SITE methodology to Northern Illinois is presented. Also included is a description of the ongoing extension of SITE for the accumulative evaluation of alternative regional energy siting patterns and fuel cycle options. An appendix provides documentation and user information for the SITE computer program

Nuclear facility decommissioning and site remedial actions

International Nuclear Information System (INIS)

Owen, P.T.; Knox, N.P.; Ferguson, S.D.; Fielden, J.M.; Schumann, P.L.

1989-09-01

The 576 abstracted references on nuclear facility decommissioning, uranium mill tailings management, and site remedial actions constitute the tenth in a series of reports prepared annually for the US Department of Energy's Remedial Action Programs. Citations to foreign and domestic literature of all types--technical reports, progress reports, journal articles, symposia proceedings, theses, books, patents, legislation, and research project descriptions--have been included. The bibliography contains scientific, technical, economic, regulatory, and legal information pertinent to the US Department of Energy's Remedial Action Programs. Major sections are (1) Surplus Facilities Management Program, (2) Nuclear Facilities Decommissioning, (3) Formerly Utilized Sites Remedial Action Program, (4) Facilities Contaminated with Naturally Occurring Radionuclides, (5) Uranium Mill Tailings Remedial Action Program, (6) Uranium Mill Tailings Management, (7) Technical Measurements Center, and (8) General Remedial Action Program Studies. Within these categories, references are arranged alphabetically by first author. Those references having no individual author are listed by corporate affiliation or by publication description. Indexes are provided for author, corporate affiliation, title work, publication description, geographic location, subject category, and keywords

Nuclear facility decommissioning and site remedial actions

Energy Technology Data Exchange (ETDEWEB)

Owen, P.T.; Knox, N.P.; Ferguson, S.D.; Fielden, J.M.; Schumann, P.L.

1989-09-01

The 576 abstracted references on nuclear facility decommissioning, uranium mill tailings management, and site remedial actions constitute the tenth in a series of reports prepared annually for the US Department of Energy's Remedial Action Programs. Citations to foreign and domestic literature of all types--technical reports, progress reports, journal articles, symposia proceedings, theses, books, patents, legislation, and research project descriptions--have been included. The bibliography contains scientific, technical, economic, regulatory, and legal information pertinent to the US Department of Energy's Remedial Action Programs. Major sections are (1) Surplus Facilities Management Program, (2) Nuclear Facilities Decommissioning, (3) Formerly Utilized Sites Remedial Action Program, (4) Facilities Contaminated with Naturally Occurring Radionuclides, (5) Uranium Mill Tailings Remedial Action Program, (6) Uranium Mill Tailings Management, (7) Technical Measurements Center, and (8) General Remedial Action Program Studies. Within these categories, references are arranged alphabetically by first author. Those references having no individual author are listed by corporate affiliation or by publication description. Indexes are provided for author, corporate affiliation, title work, publication description, geographic location, subject category, and keywords.

Russian Federal nuclear center facilities for nuclear spectroscopy investigations

International Nuclear Information System (INIS)

Ilkaev, R.I.; Punin, V.T.; Abramovich, S.N.

2001-01-01

Russian Federal Nuclear Center facilities for Spectroscopy investigation in the field of nuclear spectroscopy are described. Here are discussed basic properties of used radiation sources, facilities and technologies for target material production and manufacture of targets from rare, high-toxic or radioactive materials. Here are also reported basic features of complex detector systems and technologies for manufacture of scintillation detectors with special properties VNIIEF was founded as a weapons laboratory. The development of nuclear and thermonuclear bombs was followed by a wide complex of nuclear-physics investigations. Naturally, data on nuclear-physics properties of active and structure materials being part of nuclear weapons were of greatest interest.At the initial stage of work on the development of nuclear weapons the information on nuclear constants of materials including the most important neutron ones was rather scant. Data published in scientific literature had low exactness and were insecure. Results of measurements sometimes differed greatly by various groups of investigators. At the same time it was clear that, for example, a 1,5-times mistake in the fission cross-section could cause a several times mistake in the choice of uranium or plutonium mass, which is necessary for the bomb development. These circumstances determined importance of the nuclear-physics investigations. Demands on knowledge of process details occurring inside the nuclei conditioned by a problem of developing and improving of nuclear weapons and atomic power are rather limited. However, the further development of nuclear industry has proved a well-known point that this knowledge being accumulated forms a critical mass that leads to an explosive situation in the elaboration both of ideological and technological aspects of these problems. It is the tendency of inside development of nuclear science that has conditioned preparedness of knowledge about intranuclear processes for

Bypassing health facilities for childbirth in the context of the JSY cash transfer program to promote institutional birth: A cross-sectional study from Madhya Pradesh, India.

Science.gov (United States)

Sabde, Yogesh; Chaturvedi, Sarika; Randive, Bharat; Sidney, Kristi; Salazar, Mariano; De Costa, Ayesha; Diwan, Vishal

2018-01-01

Bypassing health facilities for childbirth can be costly both for women and health systems. There have been some reports on this from Sub-Saharan African and from Nepal but none from India. India has implemented the Janani Suraksha Yojana (JSY), a large national conditional cash transfer program which has successfully increased the number of institutional births in India. This paper aims to study the extent of bypassing the nearest health facility offering intrapartum care in three districts of Madhya Pradesh, India, and to identify individual and facility determinants of bypassing in the context of the JSY program. Our results provide information to support the optimal utilization of facilities at different levels of the healthcare system for childbirth. Data was collected from 96 facilities (74 public) and 720 rural mothers who delivered at these facilities were interviewed. Multilevel logistic regression was used to analyze the data. Facility obstetric care functionality was assessed by the number of emergency obstetric care (EmOC) signal functions performed in the last three months. Thirty eighth percent of the mothers bypassed the nearest public facility for their current delivery. Primiparity, higher education, arriving by hired transport and a longer distance from home to the nearest facility increased the odds of bypassing a public facility for childbirth. The variance partition coefficient showed that 37% of the variation in bypassing the nearest public facility can be attributed to difference between facilities. The number of basic emergency obstetric care signal functions (AOR = 0.59, 95% CI 0.37-0.93), and the availability of free transportation at the nearest facility (AOR = 0.11, 95% CI 0.03-0.31) were protective factors against bypassing. The variation between facilities (MOR = 3.85) was more important than an individual's characteristics to explain bypassing in MP. This multilevel study indicates that in this setting, a focus on increasing the level

Bypassing health facilities for childbirth in the context of the JSY cash transfer program to promote institutional birth: A cross-sectional study from Madhya Pradesh, India

Science.gov (United States)

Sabde, Yogesh; Chaturvedi, Sarika; Randive, Bharat; Sidney, Kristi; Salazar, Mariano; De Costa, Ayesha; Diwan, Vishal

2018-01-01

Bypassing health facilities for childbirth can be costly both for women and health systems. There have been some reports on this from Sub-Saharan African and from Nepal but none from India. India has implemented the Janani Suraksha Yojana (JSY), a large national conditional cash transfer program which has successfully increased the number of institutional births in India. This paper aims to study the extent of bypassing the nearest health facility offering intrapartum care in three districts of Madhya Pradesh, India, and to identify individual and facility determinants of bypassing in the context of the JSY program. Our results provide information to support the optimal utilization of facilities at different levels of the healthcare system for childbirth. Data was collected from 96 facilities (74 public) and 720 rural mothers who delivered at these facilities were interviewed. Multilevel logistic regression was used to analyze the data. Facility obstetric care functionality was assessed by the number of emergency obstetric care (EmOC) signal functions performed in the last three months. Thirty eighth percent of the mothers bypassed the nearest public facility for their current delivery. Primiparity, higher education, arriving by hired transport and a longer distance from home to the nearest facility increased the odds of bypassing a public facility for childbirth. The variance partition coefficient showed that 37% of the variation in bypassing the nearest public facility can be attributed to difference between facilities. The number of basic emergency obstetric care signal functions (AOR = 0.59, 95% CI 0.37–0.93), and the availability of free transportation at the nearest facility (AOR = 0.11, 95% CI 0.03–0.31) were protective factors against bypassing. The variation between facilities (MOR = 3.85) was more important than an individual’s characteristics to explain bypassing in MP. This multilevel study indicates that in this setting, a focus on increasing the

Evaluation of multiple emission point facilities

International Nuclear Information System (INIS)

Miltenberger, R.P.; Hull, A.P.; Strachan, S.; Tichler, J.

1988-01-01

In 1970, the New York State Department of Environmental Conservation (NYSDEC) assumed responsibility for the environmental aspect of the state's regulatory program for by-product, source, and special nuclear material. The major objective of this study was to provide consultation to NYSDEC and the US NRC to assist NYSDEC in determining if broad-based licensed facilities with multiple emission points were in compliance with NYCRR Part 380. Under this contract, BNL would evaluate a multiple emission point facility, identified by NYSDEC, as a case study. The review would be a nonbinding evaluation of the facility to determine likely dispersion characteristics, compliance with specified release limits, and implementation of the ALARA philosophy regarding effluent release practices. From the data collected, guidance as to areas of future investigation and the impact of new federal regulations were to be developed. Reported here is the case study for the University of Rochester, Strong Memorial Medical Center and Riverside Campus

Investigating Public Facility Characteristics from a Spatial Interaction Perspective: A Case Study of Beijing Hospitals Using Taxi Data

Directory of Open Access Journals (Sweden)

Xiaoqing Kong

2017-02-01

Full Text Available Services provided by public facilities are essential to people’s lives and are closely associated with human mobility. Traditionally, public facility access characteristics, such as accessibility, equity issues and service areas, are investigated mainly based on static data (census data, travel surveys and particular records, such as medical records. Currently, the advent of big data offers an unprecedented opportunity to obtain large-scale human mobility data, which can be used to study the characteristics of public facilities from the spatial interaction perspective. Intuitively, spatial interaction characteristics and service areas of different types and sizes of public facilities are different, but how different remains an open question, so we, in turn, examine this question. Based on spatial interaction, we classify public facilities and explore the differences in facilities. In the research, based on spatial interaction extracted from taxi data, we introduce an unsupervised classification method to classify 78 hospitals in 6 districts of Beijing, and the results better reflect the type of hospital. The findings are of great significance for optimizing the spatial configuration of medical facilities or other types of public facilities, allocating public resources reasonably and relieving traffic pressure.

Study on thermal-hydraulic phenomena identification of passive heat removal facilities

International Nuclear Information System (INIS)

Park, J. Y.

2011-01-01

Recently, passive heat removal facilities have been integral features of new generation or future reactor designs worldwide. This is because the passive heat removal facilities depending on a natural force such as buoyancy can give much higher operational reliability compared to active heat removal facilities depending on pumped fluid flow and as a result they can decrease core damage frequency of a nuclear power plant drastically ever achievable before. Keeping pace with this global trend, SMART and APR+ reactors also have introduced passive heat removal features such as a passive residual heat removal system (PRHRS) and a passive auxiliary feed water system (PAFS) in their designs. Since many thermal-hydraulic (T-H) phenomena including steam condensation are involved during operation of the passive heat removal facilities, they ought to be properly simulated by T-H codes such as MARS-KS and RELAP5 in order to guarantee reliable safety analysis by these codes. Unfortunately, however, these T-H codes are not well validated with respect to phenomena related to passive heat removal mechanism because previous focus on these codes validation was mainly on the LB LOCA and resulting phenomena. To resolve this gap, Korea Institute of Nuclear Safety has initiated a research program on the development of safety analysis technology for passive heat removal facilities. The main target of this program is PRHRS and PAFS in SMART and APR+ reactors and through this program, validation of capability of existing T-H codes and improvement of codes regarding passive facilities analysis are to be sought. In part of this research, T-H phenomena important to passive heat removal facilities (PRHRS and PAFS) are investigated in the present study

INVESTIGATION OF QUANTIFICATION OF FLOOD CONTROL AND WATER UTILIZATION EFFECT OF RAINFALL INFILTRATION FACILITY BY USING WATER BALANCE ANALYSIS MODEL

OpenAIRE

文, 勇起; BUN, Yuki

2013-01-01

In recent years, many flood damage and drought attributed to urbanization has occurred. At present infiltration facility is suggested for the solution of these problems. Based on this background, the purpose of this study is investigation of quantification of flood control and water utilization effect of rainfall infiltration facility by using water balance analysis model. Key Words : flood control, water utilization , rainfall infiltration facility

Emission Facilities - Air Emission Plants

Data.gov (United States)

NSGIC Education | GIS Inventory — Represents the Primary Facility type Air Emission Plant (AEP) point features. Air Emissions Plant is a DEP primary facility type related to the Air Quality Program....

Facility model for the Los Alamos Plutonium Facility

International Nuclear Information System (INIS)

Coulter, C.A.; Thomas, K.E.; Sohn, C.L.; Yarbro, T.F.; Hench, K.W.

1986-01-01

The Los Alamos Plutonium Facility contains more than sixty unit processes and handles a large variety of nuclear materials, including many forms of plutonium-bearing scrap. The management of the Plutonium Facility is supporting the development of a computer model of the facility as a means of effectively integrating the large amount of information required for material control, process planning, and facility development. The model is designed to provide a flexible, easily maintainable facility description that allows the faciltiy to be represented at any desired level of detail within a single modeling framework, and to do this using a model program and data files that can be read and understood by a technically qualified person without modeling experience. These characteristics were achieved by structuring the model so that all facility data is contained in data files, formulating the model in a simulation language that provides a flexible set of data structures and permits a near-English-language syntax, and using a description for unit processes that can represent either a true unit process or a major subsection of the facility. Use of the model is illustrated by applying it to two configurations of a fictitious nuclear material processing line

Program for studying fundamental interactions at the PIK reactor facilities

International Nuclear Information System (INIS)

Serebrov, A. P.; Vassiljev, A. V.; Varlamov, V. E.; Geltenbort, P.; Gridnev, K. A.; Dmitriev, S. P.; Dovator, N. A.; Egorov, A. I.; Ezhov, V. F.; Zherebtsov, O. M.; Zinoviev, V. G.; Ivochkin, V. G.; Ivanov, S. N.; Ivanov, S. A.; Kolomensky, E. A.; Konoplev, K. A.; Krasnoschekova, I. A.; Lasakov, M. S.; Lyamkin, V. A.; Martemyanov, V. P.

2016-01-01

A research program aimed at studying fundamental interactions by means of ultracold and polarized cold neutrons at the GEK-4-4′ channel of the PIK reactor is presented. The apparatus to be used includes a source of cold neutrons in the heavy-water reflector of the reactor, a source of ultracold neutrons based on superfluid helium and installed in a cold-neutron beam extracted from the GEK-4 channel, and a number of experimental facilities in neutron beams. An experiment devoted to searches for the neutron electric dipole moment and an experiment aimed at a measurement the neutron lifetime with the aid of a large gravitational trap are planned to be performed in a beam of ultracold neutrons. An experiment devoted to measuring neutron-decay asymmetries with the aid of a superconducting solenoid is planned in a beam of cold polarized neutrons from the GEK-4′ channel. The second ultracold-neutron source and an experiment aimed at measuring the neutron lifetime with the aid of a magnetic trap are planned in the neutron-guide system of the GEK-3 channel. In the realms of neutrino physics, an experiment intended for sterile-neutrino searches is designed. The state of affairs around the preparation of the experimental equipment for this program is discussed.

Program for studying fundamental interactions at the PIK reactor facilities

Energy Technology Data Exchange (ETDEWEB)

Serebrov, A. P., E-mail: serebrov@pnpi.spb.ru; Vassiljev, A. V.; Varlamov, V. E. [National Research Center Kurchatov Institute, Petersburg Nuclear Physics Institute (Russian Federation); Geltenbort, P. [Institut Laue-Langevin (France); Gridnev, K. A. [St. Petersburg State University (Russian Federation); Dmitriev, S. P.; Dovator, N. A. [Russian Academy of Sciences, Ioffe Physical-Technical Institute (Russian Federation); Egorov, A. I.; Ezhov, V. F.; Zherebtsov, O. M.; Zinoviev, V. G.; Ivochkin, V. G.; Ivanov, S. N.; Ivanov, S. A.; Kolomensky, E. A.; Konoplev, K. A.; Krasnoschekova, I. A.; Lasakov, M. S.; Lyamkin, V. A. [National Research Center Kurchatov Institute, Petersburg Nuclear Physics Institute (Russian Federation); Martemyanov, V. P. [National Research Center Kurchatov Institute (Russian Federation); and others

2016-05-15

A research program aimed at studying fundamental interactions by means of ultracold and polarized cold neutrons at the GEK-4-4′ channel of the PIK reactor is presented. The apparatus to be used includes a source of cold neutrons in the heavy-water reflector of the reactor, a source of ultracold neutrons based on superfluid helium and installed in a cold-neutron beam extracted from the GEK-4 channel, and a number of experimental facilities in neutron beams. An experiment devoted to searches for the neutron electric dipole moment and an experiment aimed at a measurement the neutron lifetime with the aid of a large gravitational trap are planned to be performed in a beam of ultracold neutrons. An experiment devoted to measuring neutron-decay asymmetries with the aid of a superconducting solenoid is planned in a beam of cold polarized neutrons from the GEK-4′ channel. The second ultracold-neutron source and an experiment aimed at measuring the neutron lifetime with the aid of a magnetic trap are planned in the neutron-guide system of the GEK-3 channel. In the realms of neutrino physics, an experiment intended for sterile-neutrino searches is designed. The state of affairs around the preparation of the experimental equipment for this program is discussed.

45 CFR 1170.32 - Existing facilities.

Science.gov (United States)

2010-10-01

... 45 Public Welfare 3 2010-10-01 2010-10-01 false Existing facilities. 1170.32 Section 1170.32... ASSISTED PROGRAMS OR ACTIVITIES Accessibility § 1170.32 Existing facilities. (a) Accessibility. A recipient... require a recipient to make each of its existing facilities or every part of a facility accessible to and...

45 CFR 605.22 - Existing facilities.

Science.gov (United States)

2010-10-01

... 45 Public Welfare 3 2010-10-01 2010-10-01 false Existing facilities. 605.22 Section 605.22 Public... Accessibility § 605.22 Existing facilities. (a) Accessibility. A recipient shall operate each program or... existing facilities or every part of a facility accessible to and usable by qualified handicapped persons...

10 CFR 1040.72 - Existing facilities.

Science.gov (United States)

2010-01-01

... 10 Energy 4 2010-01-01 2010-01-01 false Existing facilities. 1040.72 Section 1040.72 Energy... § 1040.72 Existing facilities. (a) Accessibility. A recipient shall operate any program or activity to... facilities or every part of a facility accessible to and useable by handicapped persons. (b) Methods. A...

45 CFR 1151.22 - Existing facilities.

Science.gov (United States)

2010-10-01

... 45 Public Welfare 3 2010-10-01 2010-10-01 false Existing facilities. 1151.22 Section 1151.22... Prohibited Accessibility § 1151.22 Existing facilities. (a) A recipient shall operate each program or... make each of its existing facilities or every part of a facility accessible to and usable by...

2D/3D Program work summary report

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-09-01

The 2D/3D Program was carried out by Germany, Japan and the United States to investigate the thermal-hydraulics of a PWR large-break LOCA. A contributory approach was utilized in which each country contributed significant effort to the program and all three countries shared the research results. Germany constructed and operated the Upper Plenum Test Facility (UPTF), and Japan constructed and operated the Cylindrical Core Test Facility (CCTF) and the Slab Core Test Facility (SCTF). The US contribution consisted of provision of advanced instrumentation to each of the three test facilities, and assessment of the TRAC computer code against the test results. Evaluations of the test results were carried out in all three countries. This report summarizes the 2D/3D Program in terms of the contributing efforts of the participants, and was prepared in a coordination among three countries. US and Germany have published the report as NUREG/IA-0126 and GRS-100, respectively. (author).

2D/3D Program work summary report

International Nuclear Information System (INIS)

1995-09-01

The 2D/3D Program was carried out by Germany, Japan and the United States to investigate the thermal-hydraulics of a PWR large-break LOCA. A contributory approach was utilized in which each country contributed significant effort to the program and all three countries shared the research results. Germany constructed and operated the Upper Plenum Test Facility (UPTF), and Japan constructed and operated the Cylindrical Core Test Facility (CCTF) and the Slab Core Test Facility (SCTF). The US contribution consisted of provision of advanced instrumentation to each of the three test facilities, and assessment of the TRAC computer code against the test results. Evaluations of the test results were carried out in all three countries. This report summarizes the 2D/3D Program in terms of the contributing efforts of the participants, and was prepared in a coordination among three countries. US and Germany have published the report as NUREG/IA-0126 and GRS-100, respectively. (author)

Revisiting the Service Physical Education Program at the Tertiary Level: Basis For A Revitalized Program

Directory of Open Access Journals (Sweden)

Marilou M. Orlanda

2015-12-01

Full Text Available This study investigated the service Physical Education Program at Batangas State University system based on the assessments of the administrators, faculty and students on its implementation in consideration of its program components and attitudes of PE teachers towards the subject with the proposed revitalized Physical Education program as an output. Using descriptive research design of research and statistical tools such as percentage, weighted mean, and f-test, the result showed a great extent of the implementation of the service Physical Education program at BSU system in terms of attainment of objectives, curriculum, teaching effectiveness of faculty, and adequacy of facilities, equipment, supplies, and instructional materials. Positive attitudes towards PE except on the concerns on reducing the time allocation for the subject and that it should be mainly sports and play were among the findings. In addition, the objectives of the PE program are believed to be the best indicators while the least indicator is the facilities, equipment and supplies.

Department of Energy Defense Programs Environmental Restoration Program update

International Nuclear Information System (INIS)

Lehr, J.C.; Eyman, L.D.; Thompson, W.W. Jr.

1989-01-01

Federal facilities are under increasing pressure to remediate inactive hazardous waste sites and associated off-site areas. The Superfund Amendments and Reauthorization Act federal facilities provision requires that the Environmental Protection Agency establish a public docket to list all federal sites contaminated by hazardous wastes or substances and to monitor the progress of investigations and cleanups against an established schedule. In addition, the Resource Conservation and Recovery Act requires that operating permits for hazardous waste treatment, storage, and disposal facilities be issued only upon binding agreements that identify specific schedules for corrective action for all hazardous waste releases that have or are occurring at the facility. Defense Programs (DP) must make remedial actions integral to its mission. Environmental cleanups are given increased emphasis with the new regulations/laws providing the right to private citizens and the states to sue to enforce these statutes and schedule commitments. 1 fig., 2 tabs

RCRA corrective action program guide (Interim)

Energy Technology Data Exchange (ETDEWEB)

1993-05-01

The US Department of Energy (DOE) is responsible for compliance with an increasingly complex spectrum of environmental regulations. One of the most complex programs is the corrective action program proposed by the US Environmental Protection Agency (EPA) under the authority of the Resource Conservation and Recovery Act (RCRA) as amended by the Hazardous and Solid Waste Amendments (HSWA). The proposed regulations were published on July 27, 1990. The proposed Subpart S rule creates a comprehensive program for investigating and remediating releases of hazardous wastes and hazardous waste constituents from solid waste management units (SWMUs) at facilities permitted to treat, store, or dispose of hazardous wastes. This proposed rule directly impacts many DOE facilities which conduct such activities. This guidance document explains the entire RCRA Corrective Action process as outlined by the proposed Subpart S rule, and provides guidance intended to assist those persons responsible for implementing RCRA Corrective Action at DOE facilities.

Mirror Fusion Test Facility (MFTF)

International Nuclear Information System (INIS)

Thomassen, K.I.

1978-01-01

A large, new Mirror Fusion Test Facility is under construction at LLL. Begun in FY78 it will be completed at the end of FY78 at a cost of $94.2M. This facility gives the mirror program the flexibility to explore mirror confinement principles at a signficant scale and advances the technology of large reactor-like devices. The role of MFTF in the LLL program is described here

Field Investigation Plan for 1301-N and 1325-N Facilities Sampling to Support Remedial Design

International Nuclear Information System (INIS)

Weiss, S. G.

1998-01-01

This field investigation plan (FIP) provides for the sampling and analysis activities supporting the remedial design planning for the planned removal action for the 1301-N and 1325-N Liquid Waste Disposal Facilities (LWDFs), which are treatment, storage,and disposal (TSD) units (cribs/trenches). The planned removal action involves excavation, transportation, and disposal of contaminated material at the Environmental Restoration Disposal Facility (ERDF).An engineering study (BHI 1997) was performed to develop and evaluate various options that are predominantly influenced by the volume of high- and low-activity contaminated soil requiring removal. The study recommended that additional sampling be performed to supplement historical data for use in the remedial design

Engineering program in order to increase the irradiated fuel storage capacity in pool facilities of Juragua

International Nuclear Information System (INIS)

Rodriguez R, J.

1996-01-01

In 1993, a technical program in the spent fuel storage area of Nuclear Plant Juragua was launched. Such a program tries to carry out an engineering assessment of the possibility of increasing the spent fuel storage capacity in pool storage facilities by using high density racks (re-racking) instead of the original (non-compact) ones. The purpose of the above-mentioned program is to evaluate possible solutions that can be applied to the construction works prior to plant operation. The first stage of the program for the 1994-95 period is an ongoing Engineering-Economic Feasibility Study (EEFS), which endeavors to examine the capabilities of the reloading pool in Unit-1 Reactor building and long-term storage pool in auxiliary building in high density storage conditions. Technical details of the EEFS and reached results and difficulties are described. (author). 5 refs., 2 figs

The U.S. DOE new production reactor/heavy water reactor facility pollution prevention/waste minimization program

International Nuclear Information System (INIS)

Kaczmarsky, Myron M.; Tsang, Irving; Stepien, Walter P.

1992-01-01

A Pollution Prevention/Waste Minimization Program was established during the early design phase of the U.S. DOE's New Production Reactor/Heavy Water Reactor Facility (NPR/HWRF) to encompass design, construction, operation and decommissioning. The primary emphasis of the program was given to waste elimination, source reduction and/or recycling to minimize the quantity and toxicity of material before it enters the waste stream for treatment or disposal. The paper discusses the regulatory and programmatic background as it applies to the NPR/HWRF and the waste assessment program developed as a phased approach to pollution prevention/waste minimization for the NPR/HWRF. Implementation of the program will be based on various factors including life cycle cost analysis, which will include costs associated with personnel, record keeping, transportation, pollution control equipment, treatment, storage, disposal, liability, compliance and oversight. (author)

Investigation of air cleaning system response to accident conditions

International Nuclear Information System (INIS)

Andrae, R.W.; Bolstad, J.W.; Foster, R.D.; Gregory, W.S.; Horak, H.L.; Idar, E.S.; Martin, R.A.; Ricketts, C.I.; Smith, P.R.; Tang, P.K.

1980-01-01

Air cleaning system response to the stress of accident conditions are being investigated. A program overview and hghlight recent results of our investigation are presented. The program includes both analytical and experimental investigations. Computer codes for predicting effects of tornados, explosions, fires, and material transport are described. The test facilities used to obtain supportive experimental data to define structural integrity and confinement effectiveness of ventilation system components are described. Examples of experimental results for code verification, blower response to tornado transients, and filter response to tornado and explosion transients are reported

IOTA (Integrable Optics Test Accelerator): facility and experimental beam physics program

Science.gov (United States)

Antipov, S.; Broemmelsiek, D.; Bruhwiler, D.; Edstrom, D.; Harms, E.; Lebedev, V.; Leibfritz, J.; Nagaitsev, S.; Park, C. S.; Piekarz, H.; Piot, P.; Prebys, E.; Romanov, A.; Ruan, J.; Sen, T.; Stancari, G.; Thangaraj, C.; Thurman-Keup, R.; Valishev, A.; Shiltsev, V.

2017-03-01

The Integrable Optics Test Accelerator (IOTA) is a storage ring for advanced beam physics research currently being built and commissioned at Fermilab. It will operate with protons and electrons using injectors with momenta of 70 and 150 MeV/c, respectively. The research program includes the study of nonlinear focusing integrable optical beam lattices based on special magnets and electron lenses, beam dynamics of space-charge effects and their compensation, optical stochastic cooling, and several other experiments. In this article, we present the design and main parameters of the facility, outline progress to date and provide the timeline of the construction, commissioning and research. The physical principles, design, and hardware implementation plans for the major IOTA experiments are also discussed.

IOTA (Integrable Optics Test Accelerator): Facility and experimental beam physics program

International Nuclear Information System (INIS)

Antipov, Sergei; Broemmelsiek, Daniel; Bruhwiler, David; Edstrom, Dean; Harms, Elvin

2017-01-01

The Integrable Optics Test Accelerator (IOTA) is a storage ring for advanced beam physics research currently being built and commissioned at Fermilab. It will operate with protons and electrons using injectors with momenta of 70 and 150 MeV/c, respectively. The research program includes the study of nonlinear focusing integrable optical beam lattices based on special magnets and electron lenses, beam dynamics of space-charge effects and their compensation, optical stochastic cooling, and several other experiments. In this article, we present the design and main parameters of the facility, outline progress to date and provide the timeline of the construction, commissioning and research. Finally, the physical principles, design, and hardware implementation plans for the major IOTA experiments are also discussed.

Atmospheric Radiation Measurement Program facilities newsletter, February 2001.; TOPICAL

International Nuclear Information System (INIS)

Holdridge, D. J.

2001-01-01

This newsletter consists of the following: (1) ARM Science Team Meeting Scheduled-The 11th Annual ARM Science Team meeting is scheduled for March 19-23, 2001, in Atlanta, Georgia. Members of the science team will exchange research results achieved by using ARM data. The science team is composed of working groups that investigate four topics: instantaneous radiative flux, cloud parameterizations and modeling, cloud properties, and aerosols. The annual meeting brings together the science team's 150 members to discuss issues related to ARM and its research. The members represent universities, government laboratories and research facilities, and independent research companies. (2) Communications to Extended Facilities Upgraded-New communications equipment has been installed at all of the SGP extended facilities. Shelters were installed to house the new equipment used to transfer data from instruments via the Internet to the site data system at the central facility. This upgrade has improved data availability from the extended facilities to 100% and reduced telephone costs greatly. (3) SGP Goes ''Buggy''-Steve Sekelsky, a researcher from the University of Massachusetts, is planning to bring a 95-GHz radar to the SGP central facility for deployment in March-October 2001. The radar will help to identify signals due to insects flying in the air. The ARM millimeter cloud radar, which operates at 35 GHz, is sensitive to such insect interference. Testing will also be performed by using a second 35-GHz radar with a polarized radar beam, which can differentiate signals from insects versus cloud droplets. (4) Winter Fog-Fog can add to hazards already associated with winter weather. Common types of fog formation include advection, radiation, and steam. Advection fog: An advection fog is a dense fog that forms when a warm, moist air mass moves into an area with cooler ground below. For example, fog can form in winter when warmer, water-saturated air from the south (associated with

Computer program for storage of historical and routine safety data related to radiologically controlled facilities

International Nuclear Information System (INIS)

Marsh, D.A.; Hall, C.J.

1984-01-01

A method for tracking and quick retrieval of radiological status of radiation and industrial safety systems in an active or inactive facility has been developed. The system uses a mini computer, a graphics plotter, and mass storage devices. Software has been developed which allows input and storage of architectural details, radiological conditions such as exposure rates, current location of safety systems, and routine and historical information on exposure and contamination levels. A blue print size digitizer is used for input. The computer program retains facility floor plans in three dimensional arrays. The software accesses an eight pen color plotter for output. The plotter generates color plots of the floor plans and safety systems on 8 1/2 x 11 or 20 x 30 paper or on overhead transparencies for reports and presentations

Utilization of the state led public private partnership program "Chiranjeevi Yojana" to promote facility births in Gujarat, India: a cross sectional community based study.

Science.gov (United States)

Yasobant, Sandul; Vora, Kranti Suresh; Shewade, Hemant Deepak; Annerstedt, Kristi Sidney; Isaakidis, Petros; Mavalankar, Dileep V; Dholakia, Nishith B; De Costa, Ayesha

2016-07-15

"Chiranjeevi Yojana (CY)", a state-led large-scale demand-side financing scheme (DSF) under public-private partnership to increase institutional delivery, has been implemented across Gujarat state, India since 2005. The scheme aims to provide free institutional childbirth services in accredited private health facilities to women from socially disadvantaged groups (eligible women). These services are paid for by the state to the private facility with the intention of service being free to the user. This community-based study estimates CY uptake among eligible women and explores factors associated with non-utilization of the CY program. This was a community-based cross sectional survey of eligible women who gave birth between January and July 2013 in 142 selected villages of three districts in Gujarat. A structured questionnaire was administered by trained research assistant to collect information on socio-demographic details, pregnancy details, details of childbirth and out-of-pocket (OOP) expenses incurred. A multivariable inferential analysis was done to explore the factors associated with non-utilization of the CY program. Out of 2,143 eligible women, 559 (26 %) gave birth under the CY program. A further 436(20 %) delivered at free public facilities, 713(33 %) at private facilities (OOP payment) and 435(20 %) at home. Eligible women who belonged to either scheduled tribe or poor [aOR = 3.1, 95 % CI:2.4 - 3.8] or having no formal education [aOR = 1.6, 95 % CI:1.1, 2.2] and who delivered by C-section [aOR = 2.1,95 % CI: 1.2, 3.8] had higher odds of not utilizing CY program. Of births at CY accredited facilities (n = 924), non-utilization was 40 % (n = 365) mostly because of lack of required official documentation that proved eligibility (72 % of eligible non-users). Women who utilized the CY program overall paid more than women who delivered in the free public facilities. Uptake of the CY among eligible women was low after almost a decade

Thermal hydraulic behavior of a PWR under beyond-design-basis accident conditions: Conclusions from an experimental program in a 4-loop test facility (PKL)

International Nuclear Information System (INIS)

Umminger, K.J.; Kastner, W.; Mandl, R.M.; Weber, P.

1993-01-01

Within the scope of German reactor safety research, extensive experiments covering the behavior of nuclear power plants under accident conditions have been carried out in the PKL test facility which simulates a 4-loop, 1,300 MWe KWU-designed PWR. While the investigations dealing with design-basis accidents and with the efficiency of the emergency core cooling systems have been largely completed, the main interest nowadays concentrates on the investigation of beyond-design-basis accidents to demonstrate the safety margins of nuclear power plants and to investigate the contribution of the built-in safety features for a further reduction of the residual risk. The thermal hydraulic behavior of a PWR under these extreme accident conditions was experimentally investigated within the PKL III B test program. This paper presents the fundamental findings with some of the most important results being discussed in detail. Future plans are also outlined

Isotopes facilities deactivation project at Oak Ridge National Laboratory

International Nuclear Information System (INIS)

Eversole, R.E.

1997-01-01

The production and distribution of radioisotopes for medical, scientific, and industrial applications has been a major activity at Oak Ridge National Laboratory (ORNL) since the late 1940s. As the demand for many of these isotopes grew and their sale became profitable, the technology for the production of the isotopes was transferred to private industry, and thus, many of the production facilities at ORNL became underutilized. In 1989, the U.S. Department of Energy (DOE) instructed ORNL to identify and prepare various isotopes production facilities for safe shutdown. In response, ORNL identified 19 candidate facilities for shutdown and established the Isotopes Facilities Shutdown Program. In 1993, responsibility for the program was transitioned from the DOE Office of Nuclear Energy to the DOE Office of Environmental Management and Uranium Enrichment Operation's Office of Facility Transition and Management. The program was retitled the Isotopes Facilities Deactivation Project (IFDP), and implementation responsibility was transferred from ORNL to the Lockheed Martin Energy Systems, Inc. (LMES), Environmental Restoration (ER) Program

Isotopes facilities deactivation project at Oak Ridge National Laboratory

Energy Technology Data Exchange (ETDEWEB)

Eversole, R.E.

1997-05-01

The production and distribution of radioisotopes for medical, scientific, and industrial applications has been a major activity at Oak Ridge National Laboratory (ORNL) since the late 1940s. As the demand for many of these isotopes grew and their sale became profitable, the technology for the production of the isotopes was transferred to private industry, and thus, many of the production facilities at ORNL became underutilized. In 1989, the U.S. Department of Energy (DOE) instructed ORNL to identify and prepare various isotopes production facilities for safe shutdown. In response, ORNL identified 19 candidate facilities for shutdown and established the Isotopes Facilities Shutdown Program. In 1993, responsibility for the program was transitioned from the DOE Office of Nuclear Energy to the DOE Office of Environmental Management and Uranium Enrichment Operation`s Office of Facility Transition and Management. The program was retitled the Isotopes Facilities Deactivation Project (IFDP), and implementation responsibility was transferred from ORNL to the Lockheed Martin Energy Systems, Inc. (LMES), Environmental Restoration (ER) Program.

Radiation safety training for accelerator facilities

International Nuclear Information System (INIS)

Trinoskey, P.A.

1997-02-01

In November 1992, a working group was formed within the U.S. Department of Energy's (DOE's) accelerator facilities to develop a generic safety training program to meet the basic requirements for individuals working in accelerator facilities. This training, by necessity, includes sections for inserting facility-specific information. The resulting course materials were issued by DOE as a handbook under its technical standards in 1996. Because experimenters may be at a facility for only a short time and often at odd times during the day, the working group felt that computer-based training would be useful. To that end, Lawrence Livermore National Laboratory (LLNL) and Argonne National Laboratory (ANL) together have developed a computer-based safety training program for accelerator facilities. This interactive course not only enables trainees to receive facility- specific information, but time the training to their schedule and tailor it to their level of expertise

Design of a hydrogen test facility

International Nuclear Information System (INIS)

Morgan, M.J.; Beam, J.E.; Sehmbey, M.S.; Pais, M.R.; Chow, L.C.; Hahn, O.J.

1992-01-01

The Air Force has sponsored a program at the University of Kentucky which will lead to a better understanding of the thermal and fluid instabilities during blowdown of supercritical fluids at cryogenic temperatures. An integral part of that program is the design and construction of that hydrogen test facility. This facility will be capable of providing supercritical hydrogen at 30 bars and 35 K at a maximum flow rate of 0.1 kg/s for 90 seconds. Also presented here is an extension of this facility to accommodate the use of supercritical helium

RCRA Facility investigation report for Waste Area Grouping 6 at Oak Ridge National Laboratory, Oak Ridge, Tennessee

International Nuclear Information System (INIS)

1991-09-01

This report describes the borehole geophysical logging performed at selected monitoring wells at waste area grouping (WAG) 6 of Oak Ridge National Laboratory in support of the WAG 6 Resource Conservation and Recovery Act Facility Investigation (RFI). It identifies the locations and describes the methods, equipment used in the effort, and the results of the activity. The actual logs for each well logged are presented in Attachment 1 through 4 of the TM. Attachment 5 provide logging contractor service literature and Attachment 6 is the Oak Ridge National Laboratory (ORNL) Procedure for Control of a Nuclear Source Utilized in Geophysical logging. The primary objectives of the borehole geophysical logging program were to (1) identify water-bearing fractured bedrock zones to determine the placement of the screen and sealed intervals for subsequent installation, and (2) further characterize local bedrock geology and hydrogeology and gain insight about the deeper component of the shallow bedrock aquifer flow system. A secondary objective was to provide stratigraphic and structural correlations with existing logs for Hydraulic Head Monitoring Station (HHMS) wells, which display evidence of faulting

SUCO program

International Nuclear Information System (INIS)

Knebel, J.U.

1995-01-01

The SUCO program is a three-step series of scaled model experiments investigating the optional sump cooling concept of the EPR. This concept is entirely based on passive safety features. This report presents the basic physical phenomena and scaling criteria of decay heat removal from a large coolant pool by single-phase and two-phase natural circulation flow. The physical significance of the dimensionless similarity groups derived is evaluated. The report gives first measurement results of the 1:20 linearly scaled plane two-dimensional SUCOS-2D test facility. The real height SUCOT test facility that is in its building up phase is presented. (orig.)

Oregon state university's advanced plant experiment (APEX) AP1000 integral facility test program

International Nuclear Information System (INIS)

Reyes, J.N.; Groome, J.T.; Woods, B.G.; Young, E.; Abel, K.; Wu, Q.

2005-01-01

Oregon State University (OSU) has recently completed a three year study of the thermal hydraulic behavior of the Westinghouse AP1000 passive safety systems. Eleven Design Basis Accident (DBA) scenarios, sponsored by the U.S. Department of Energy (DOE) with technical support from Westinghouse Electric, were simulated in OSU's Advanced Plant Experiment (APEX)-1000. The OSU test program was conducted within the purview of the requirements of 10CFR50 Appendix B, NQA-1 and 10 CFR 21 and the test data was used to provide benchmarks for computer codes used in the final design approval of the AP1000. In addition to the DOE certification testing, OSU conducted eleven confirmatory tests for the U.S. Nuclear Regulatory Commission. This paper presents the test program objectives, a description of the APEX-1000 test facility and an overview of the test matrix that was conducted in support of plant certification. (authors)

Space Nuclear Thermal Propulsion (SNTP) Air Force facility

Science.gov (United States)

Beck, David F.

The Space Nuclear Thermal Propulsion (SNTP) Program is an initiative within the US Air Force to acquire and validate advanced technologies that could be used to sustain superior capabilities in the area or space nuclear propulsion. The SNTP Program has a specific objective of demonstrating the feasibility of the particle bed reactor (PBR) concept. The term PIPET refers to a project within the SNTP Program responsible for the design, development, construction, and operation of a test reactor facility, including all support systems, that is intended to resolve program technology issues and test goals. A nuclear test facility has been designed that meets SNTP Facility requirements. The design approach taken to meet SNTP requirements has resulted in a nuclear test facility that should encompass a wide range of nuclear thermal propulsion (NTP) test requirements that may be generated within other programs. The SNTP PIPET project is actively working with DOE and NASA to assess this possibility.

Work control in separations facilities

International Nuclear Information System (INIS)

Olson, L.D.

1990-01-01

The topic addressed in this technical review is the development and implementation of a work control program in one of the chemical separations facilities at the Savannah River Site (SRS) in Aiken, SC. This program will be used as a pilot for the Nuclear Materials Processing Division at the site. The SRS Work Control Pilot program is based on the Institute of Nuclear Power Operations (INPO) good practices and guidelines for the conduct of maintenance and complies with SRS quality assurance and DOE orders on maintenance management. The program follows a ten-step process for control of maintenance and maintenance-related activities in a chemical separations facility. The program took the existing maintenance planning and scheduling system and upgraded it to comply with all INPO work control and related guidelines for histories, post-maintenance testing and scheduling. The development process of adapting a nuclear-related- based plan to a batch/continuous chemical separations plant was a challenge. There were many opportunities to develop improvements in performance while being creative and realistic in applying reactor maintenance technology to chemical plant maintenance. This pilot program for work control in a nonreactor nuclear facility will provide valuable information for applying a controlled maintenance process to a multiphase chemical operating plant environment

New Ideas on Facilities Management.

Science.gov (United States)

Grimm, James C.

1986-01-01

Examines trends in facilities management relating to products and people. Reviews new trends in products, including processes, techniques, and programs that are being expounded by business and industry. Discusses the "people factors" involved in facilities management. (ABB)

41 CFR 101-4.410 - Comparable facilities.

Science.gov (United States)

2010-07-01

... 41 Public Contracts and Property Management 2 2010-07-01 2010-07-01 true Comparable facilities... in Education Programs or Activities Prohibited § 101-4.410 Comparable facilities. A recipient may provide separate toilet, locker room, and shower facilities on the basis of sex, but such facilities...

Defense Treaty Inspection Readiness Program

International Nuclear Information System (INIS)

Cronin, J.J.; Kohen, M.D.; Rivers, J.D.

1996-01-01

The Defense Treaty Inspection Readiness Program (DTIRP) was established by the Department of Defense in 1990 to assist defense facilities in preparing for treaty verification activities. Led by the On-Site Inspection Agency (OSIA), an element of the Department of Defense, DTIRP''s membership includes representatives from other Department of Defense agencies, the Department of Energy (DOE), the Central Intelligence Agency, the Federal Bureau of Investigation, the Department of Commerce, and others. The Office of Safeguards and Security has a significant interest in this program, due to the number of national defense facilities within its purview that are candidates for future inspections. As a result, the Office of Safeguards and Security has taken a very active role in DTIRP. This paper discusses the Office of Safeguards and Security''s increasing involvement in various elements of the DTIRP, ranging from facility assessments to training development and implementation

Inpatient Psychiatric Facility Quality Measure Data – by State

Data.gov (United States)

U.S. Department of Health & Human Services — Psychiatric facilities that are eligible for the Inpatient Psychiatric Facility Quality Reporting (IPFQR) program are required to meet all program requirements,...

9 CFR 149.6 - Slaughter facilities.

Science.gov (United States)

2010-01-01

... 9 Animals and Animal Products 1 2010-01-01 2010-01-01 false Slaughter facilities. 149.6 Section... AGRICULTURE LIVESTOCK IMPROVEMENT VOLUNTARY TRICHINAE CERTIFICATION PROGRAM § 149.6 Slaughter facilities. Only slaughter facilities that are under continuous inspection by the Food Safety and Inspection Service or under...

Nye County Nuclear Waste Repository Project Office independent scientific investigations program annual report, May 1997 - April 1998

International Nuclear Information System (INIS)

1998-07-01

This annual summary report, prepared by the Nye County Nuclear Waste Repository Project Office (NWRPO), summarizes the activities that were performed during the period from May 1, 1997 to April 30, 1998. These activities were conducted in support of the Independent Scientific Investigation Program (ISIP) of Nye County at the Yucca Mountain Site (YMS). The Nye County NWRPO is responsible for protecting the health and safety of the Nye County residents. NWRPO's on-site representative is responsible for designing and implementing the Independent Scientific Investigation Program (ISIP). Major objectives of the ISIP include: Investigating key issues related to conceptual design and performance of the repository that can have major impact on human health, safety, and the environment; identifying areas not being addressed adequately by the Department of Energy (DOE). Nye County has identified several key scientific issues of concern that may affect repository design and performance which were not being adequately addressed by DOE. Nye County has been conducting its own independent study to evaluate the significance of these issues. This report summarizes the results of monitoring from two boreholes and the Exploratory Studies Facility (ESF) tunnel that have been instrumented by Nye County since March and April of 1995. The preliminary data and interpretations presented in this report do not constitute and should not be considered as the official position of Nye County. The ISIP presently includes borehole and tunnel instrumentation, monitoring, data analysis, and numerical modeling activities to address the concerns of Nye County

Nye County Nuclear Waste Repository Project Office independent scientific investigations program annual report, May 1997--April 1998

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-07-01

This annual summary report, prepared by the Nye County Nuclear Waste Repository Project Office (NWRPO), summarizes the activities that were performed during the period from May 1, 1997 to April 30, 1998. These activities were conducted in support of the Independent Scientific Investigation Program (ISIP) of Nye County at the Yucca Mountain Site (YMS). The Nye County NWRPO is responsible for protecting the health and safety of the Nye County residents. NWRPO`s on-site representative is responsible for designing and implementing the Independent Scientific Investigation Program (ISIP). Major objectives of the ISIP include: Investigating key issues related to conceptual design and performance of the repository that can have major impact on human health, safety, and the environment; identifying areas not being addressed adequately by the Department of Energy (DOE). Nye County has identified several key scientific issues of concern that may affect repository design and performance which were not being adequately addressed by DOE. Nye County has been conducting its own independent study to evaluate the significance of these issues. This report summarizes the results of monitoring from two boreholes and the Exploratory Studies Facility (ESF) tunnel that have been instrumented by Nye County since March and April of 1995. The preliminary data and interpretations presented in this report do not constitute and should not be considered as the official position of Nye County. The ISIP presently includes borehole and tunnel instrumentation, monitoring, data analysis, and numerical modeling activities to address the concerns of Nye County.

An update on the LEU target development and conversion program for the MAPLE reactors and new processing facility

International Nuclear Information System (INIS)

Malkoske, G.R.; Eng, B.Sc; Eng, P.

2002-01-01

Historically, the production of molybdenum-99 in the NRU research reactors at Chalk River, Canada, has been extracted from reactor targets employing highly enriched uranium (HEU). A reliable supply of HEU metal from the United States used in the manufacture of targets for the NRU research reactor has been a key factor to enable MDS Nordion to develop a secure supply of medical isotopes for the international nuclear medicine community. The molybdenum extraction process from HEU targets provides predictable, consistent yields for our high-volume molybdenum production process. Each link of the isotope supply chain, from isotope production to ultimate use by the physician, has been established using this proven and established method of HEU target irradiation and processing to extract molybdenum-99. To ensure a continued reliable and timely supply of medical isotopes, MDS Nordion is completing the construction of two MAPLE reactors and a New Processing Facility. The design of the MAPLE facilities was based on an established process developed by Atomic Energy of Canada Ltd. (AECL)-extraction of isotopes from HEU target material. However, in concert with the global trend to utilize low enriched uranium (LEU) in research reactors, MDS Nordion has launched a three phase LEU Target Development and Conversion Program for the MAPLE facilities. Phase 1, the Initial Feasibility Study, which identified the technical issues to convert the MAPLE reactor targets from HEU to LEU for large scale commercial production was reported on at the RERTR-2000 conference. The second phase of the LEU Target Development and Conversion Program was developed with extensive consultation and involvement of experts knowledgeable in target development, process system design, enriched uranium conversion chemistry and commercial scale reactor operations and molybdenum production. This paper will provide an overview of the Phase 2 Conversion Development Program, report on progress to date, and further

Measurement plan and observational construction program on drift excavation at the Horonobe Underground Research Laboratory project

International Nuclear Information System (INIS)

Yamasaki, Masanao; Yamaguchi, Takehiro; Funaki, Hironori; Fujikawa, Daisuke; Tsusaka, Kimikazu

2008-09-01

The Horonobe URL Project is being pursued by the Japan Atomic Energy Agency (JAEA) to enhance the reliability of relevant disposal technologies through investigations of the deep geological environment within the host sedimentary formations at Horonobe, northern Hokkaido. The project consists of two major research areas, 'Geoscientific Research' and 'R and D' on Geological Disposal', and proceeds in three overlapping phases, 'Phase I: Surface-based investigation', 'Phase II: Construction' and 'Phase III: Operation', over a period of 20 years. On the Horonobe URL Project, 'Phase 1' was finished in 2005FY and construction of the underground facility was started since then. Now, 'Phase 2' (investigations during construction of the underground facilities) is on-going. On the 'Development of engineering techniques for use in the deep underground environment' in Phase 1, based on the various types of data acquired on investigations from the surface, the design of underground facility in advance was planned. At the inception of the Phase II investigations, an investigation report titled 'Measurement Plan and Observational Construction Program on Shaft Excavation at the Horonobe URL Project' (hereinafter referred to as 'Observational Construction Program') was published. The Observational Construction Program summarizes followings from the Phase I investigations: measurements for safety/reasonable construction, measurements for R and D on enhancement of shaft design/construction technology, and measurements for verification of the deep geological environment model estimated before shaft excavation, and it is on-going. This report summarizes the measurement plan during construction of drifts based on the design in advance and the observational construction program for feedback measurements data into design and construction on subsequent steps. This report also describes about design and construction management program of underground facility and R and D program on

US EPA Region 4 RMP Facilities

Science.gov (United States)

To improve public health and the environment, the United States Environmental Protection Agency (USEPA) collects information about facilities, sites, or places subject to environmental regulation or of environmental interest. Through the Geospatial Data Download Service, the public is now able to download the EPA Geodata shapefile containing facility and site information from EPA's national program systems. The file is Internet accessible from the Envirofacts Web site (http://www.epa.gov/enviro). The data may be used with geospatial mapping applications. (Note: The shapefile omits facilities without latitude/longitude coordinates.) The EPA Geospatial Data contains the name, location (latitude/longitude), and EPA program information about specific facilities and sites. In addition, the file contains a Uniform Resource Locator (URL), which allows mapping applications to present an option to users to access additional EPA data resources on a specific facility or site.

2D/3D Program work summary report, [January 1988--December 1992

International Nuclear Information System (INIS)

Damerell, P.S.; Simons, J.W.

1993-06-01

The 2D/3D Program was carried out by Germany, Japan and the United States to investigate the thermal-hydraulics of a PWR large-break LOCA. A contributory approach was utilized in which each country contributed significant effort to the program and all three countries shared the research results. Germany constructed and operated the Upper Plenum Test Facility (UPTF), and Japan constructed and operated the Cylindrical Core Test Facility (CCTF) and the Slab Core Test Facility (SCTF). The US contribution consisted of provision of advanced instrumentation to each of the three test facilities, and assessment of the TRAC computer code against the test results. Evaluations of the test results were carried out in all three countries. This report summarizes the 2D/3D Program in terms of the contributing efforts of the participants

An Empirical Investigation into Programming Language Syntax

Science.gov (United States)

Stefik, Andreas; Siebert, Susanna

2013-01-01

Recent studies in the literature have shown that syntax remains a significant barrier to novice computer science students in the field. While this syntax barrier is known to exist, whether and how it varies across programming languages has not been carefully investigated. For this article, we conducted four empirical studies on programming…

Sites Requiring Facility Response Plans, Geographic NAD83, EPA (2006) [facility_response_plan_sites_la_EPA_2007

Data.gov (United States)

Louisiana Geographic Information Center — Locations of facilities in Louisiana requiring Oil Pollution Act (OPA) Facility Response Plans (FRP). The dataset was provided by the Region 6 OSCARS program....

Grout treatment facility dangerous waste permit application

International Nuclear Information System (INIS)

1992-07-01

The Grout Treatment Facility (GTF) will provide permanent disposal for approximately 43 Mgal of low-level radioactive liquid waste currently being stored in underground tanks on the Hanford Site. The first step in permanent disposal is accomplished by solidifying the liquid waste with cementitious dry materials. The resulting grout is cast within underground vaults. This report on the GTF contains information on the following: Geologic data, hydrologic data, groundwater monitoring program, information, detection monitoring program, groundwater characterization drawings, building emergency plan--grout treatment facility, response action plan for grout treatment facility, Hanford Facility contingency plan, training course descriptions, overview of the Hanford Facility Grout Performance, assessment, bland use and zoning map, waste minimization plan, cover design engineering report, and clay liners (ADMIXTURES) in semiarid environments

Coeur d'Alene Tribe Fish, Water and Wildlife Program : Coeur d'Alene Tribe Trout Production Facility Master Plan.

Energy Technology Data Exchange (ETDEWEB)

Peters, Ronald L.; Woodward-Lilengreen, Kelly L.; Vitale, Angelo J.

1999-09-01

The Northwest Power Planning Council (Council) receives and reviews proposals to mitigate for fish and wildlife losses and refers approved measures to Bonneville Power Administration (BPA) for funding. The Northwest Power Act (Act) calls on the Council to include measures in its Columbia River Basin Fish and Wildlife Program (Program) to address system-wide fish and wildlife losses. The Act further states that the Council may include in its Program measures that provide off-site mitigation--mitigation physically removed from the hydro project(s) that caused the need to mitigate. The Program includes a goal ''to recover and preserve the health of native resident fish injured by the hydropower system, where feasible, and, where appropriate, to use resident fish to mitigate for anadromous fish losses in the system.'' Among those recommended measures are off-site mitigation for losses of anadromous fisheries including the measure under analysis in this Coeur d'Alene Tribe Trout Production Facility Master Plan, proposed by the Coeur d'Alene Tribe. To meet the need for off-site mitigation for anadromous fish losses in the Columbia River Basin in a manner consistent with the objectives of the Council's Fish and Wildlife Program, the Coeur d'Alene Tribe is proposing that the BPA fund the design, construction, operations and maintenance of a trout production facility on the Coeur d'Alene Indian Reservation. Measures for establishing a Coeur d'Alene fish production facility have been a part of the Council's Program since 1987. The Coeur d'Alene Tribe Trout Production Facility is intended to rear and release westslope cutthroat trout into rivers and streams with the express purpose of increasing the numbers of fish spawning, incubating and rearing in the natural environment. It will use the modern technology that hatcheries offer to overcome the mortality resulting from habitat degradation in lakes, rivers, and

6 CFR 17.410 - Comparable facilities.

Science.gov (United States)

2010-01-01

... 6 Domestic Security 1 2010-01-01 2010-01-01 false Comparable facilities. 17.410 Section 17.410... the Basis of Sex in Education Programs or Activities Prohibited § 17.410 Comparable facilities. A recipient may provide separate toilet, locker room, and shower facilities on the basis of sex, but such...

13 CFR 113.410 - Comparable facilities.

Science.gov (United States)

2010-01-01

... 13 Business Credit and Assistance 1 2010-01-01 2010-01-01 false Comparable facilities. 113.410... Discrimination on the Basis of Sex in Education Programs Or Activities Prohibited § 113.410 Comparable facilities. A recipient may provide separate toilet, locker room, and shower facilities on the basis of sex, but...

14 CFR 1253.410 - Comparable facilities.

Science.gov (United States)

2010-01-01

... 14 Aeronautics and Space 5 2010-01-01 2010-01-01 false Comparable facilities. 1253.410 Section... on the Basis of Sex in Education Programs or Activities Prohibited § 1253.410 Comparable facilities. A recipient may provide separate toilet, locker room, and shower facilities on the basis of sex, but...

Availability program: Phase I report

International Nuclear Information System (INIS)

Thomson, S.L.; Dabiri, A.; Keeton, D.C.; Riemer, B.W.; Waganer, L.M.

1985-05-01

An Availability Working Group was formed within the Office of Fusion Energy in March 1984 to consider the establishment of an availability program for magnetic fusion. The scope of this program is defined to include the development of (1) a comprehensive data base, (2) empirical correlations, and (3) analytical methods for application to fusion facilities and devices. The long-term goal of the availability program is to develop a validated, integrated methodology that will provide (1) projections of plant availability and (2) input to design decisions on maintainability and system reliability requirements. The Phase I study group was commissioned to assess the status of work in progress that is relevant to the availability program. The scope of Phase I included surveys of existing data and data collection programs at operating fusion research facilities, the assessment of existing computer models to calculate system availability, and the review of methods to predict and correlate data on component failure and maintenance. The results of these investigations are reported to the Availability Working Group in this document

Fast Flux Test Facility Asbestos Location Tracking Program

International Nuclear Information System (INIS)

REYNOLDS, J.A.

1999-01-01

Procedure Number HNF-PRO-408, revision 0, paragraph 1.0, ''Purpose,'' and paragraph 2.0, ''Requirements for Facility Management of Asbestos,'' relate building inspection and requirements for documentation of existing asbestos-containing building material (ACBM) per each building assessment. This documentation shall be available to all personnel (including contractor personnel) entering the facility at their request. Corrective action was required by 400 Area Integrated Annual Appraisal/Audit for Fiscal Year 1992 (IAA-92-0007) to provide this notification documentation. No formal method had been developed to communicate the location and nature of ACBM to maintenance personnel in the Fast Flux Test Facility (FFTF) 400 Area. The scope of this Data Package Document is to locate and evaluate any ACBM found at FFTF which constitutes a baseline. This includes all buildings within the protected area. These findings are compiled from earlier reports, numerous work packages and engineering evaluations of employee findings

Data analysis facility at LAMPF

International Nuclear Information System (INIS)

Perry, D.G.; Amann, J.F.; Butler, H.S.; Hoffman, C.J.; Mischke, R.E.; Shera, E.B.; Thiessen, H.A.

1977-11-01

This report documents the discussions and conclusions of a study held in July 1977 to develop the requirements for a data analysis facility to support the experimental program in medium-energy physics at the Clinton P. Anderson Meson Physics Facility (LAMPF). 2 tables

Investigation on integrity of JMTR concrete structures, cooling system and utility facilities

International Nuclear Information System (INIS)

Ebisawa, Hiroyuki; Tobita, Kenji; Fukasaku, Akitomi; Kaminaga, Masanori

2010-02-01

The condition of facilities and components to be used for re-operation of the Japan Materials Testing Reactor (JMTR) from FY2011, was investigated before the refurbishment work. An investigation of aged components (aged-investigation) was carried out for concrete structures of the JMTR reactor building, exhaust stack, trench, canal, filter banks and for aged components of tanks in the primary cooling system, heat exchangers, pipes in the secondary cooling system, cooling tower, emergency generators and so on, in order to identify their integrity. The aged-investigation was carried out from the beginning of FY2007. As a result, cracks of concrete structures such as the exhaust stack, a foundation of the UCL (Utility Cooling Line) elevated water tank were repaired and pipe linings of secondary cooling system were replaced. Motors of primary cooling pumps, pumps in the secondary cooling system and in other systems were decided to replace from viewpoints of future maintenance and improvement of reliability. Other components and the reactor building were decided to use continuously for a long-term by appropriate maintenance activities based on the long-term maintenance plan. In this paper, the aged-investigation for the JMTR reactor building, heat exchangers and emergency generators is presented. (author)

Radiological Control Technician: Phase 4, Facility practical training attachment

International Nuclear Information System (INIS)

1992-10-01

At DOE sites with more than one facility, and where RCT tasks at each facility may differ, site and facility tasks should be separated. The tasks that are common to all the facilities on the site should be included in Phase II training with the core tasks. Tasks unique to a facility should be added to the training program qualification standard, as an attachment, as Phase IV training. Not all the DOE sites will include Phase IV training in their programs. Phase IV training allows each site to qualify technicians to a select facility. Since the core training for the technicians is standardized, the transfer of technicians between facilities requires that only facility tasks be taught, provided the core qualification is current

Reactor safety issues resolved by the 2D/3D program

International Nuclear Information System (INIS)

1995-09-01

The 2D/3D Program studied multidimensional thermal-hydraulics in a PWR core and primary system during the end-of-blowdown and post-blowdown phases of a large-break LOCA (LBLOCA), and during selected small-break LOCA (SBLOCA) transients. The program included tests at the Cylindrical Core Test Facility (CCTF), the Slab Core Test Facility (SCTF), and the Upper Plenum Test Facility (UPTF), and computer analyses using TRAC. Tests at CCTF investigated core thermal-hydraulics and overall system behavior while tests at SCTF concentrated on multidimensional core thermal-hydraulics. The UPTF tests investigated two-phase flow behavior in the downcomer, upper plenum, tie plate region, and primary loops. TRAC analyses evaluated thermal-hydraulic behavior throughout the primary system in tests as well as in PWRs. This report summarizes the test and analysis results in each of the main areas where improved information was obtained in the 2D/3D Program. The discussion is organized in terms of the reactor safety issues investigated. This report was prepared in a coordination among US, Germany and Japan. US and Germany have published the report as NUREG/IA-0127 and GRS-101 respectively. (author)

Reactor safety issues resolved by the 2D/3D program

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-09-01

The 2D/3D Program studied multidimensional thermal-hydraulics in a PWR core and primary system during the end-of-blowdown and post-blowdown phases of a large-break LOCA (LBLOCA), and during selected small-break LOCA (SBLOCA) transients. The program included tests at the Cylindrical Core Test Facility (CCTF), the Slab Core Test Facility (SCTF), and the Upper Plenum Test Facility (UPTF), and computer analyses using TRAC. Tests at CCTF investigated core thermal-hydraulics and overall system behavior while tests at SCTF concentrated on multidimensional core thermal-hydraulics. The UPTF tests investigated two-phase flow behavior in the downcomer, upper plenum, tie plate region, and primary loops. TRAC analyses evaluated thermal-hydraulic behavior throughout the primary system in tests as well as in PWRs. This report summarizes the test and analysis results in each of the main areas where improved information was obtained in the 2D/3D Program. The discussion is organized in terms of the reactor safety issues investigated. This report was prepared in a coordination among US, Germany and Japan. US and Germany have published the report as NUREG/IA-0127 and GRS-101 respectively. (author).

New synchrotron radiation facility project. Panel on new synchrotron radiation facility project

CERN Document Server

Sato, S; Kimura, Y

2003-01-01

The project for constructing a new synchrotron radiation facility dedicated to the science in VUV (or EUV) and Soft X-ray (SX) region has been discussed for these two years at the Panel on New Synchrotron Radiation Facility Project. The Panel together with the Accelerator Design Working Group (WG), Beamline Design WG and Research Program WG suggested to the Ministry of Education, Science, Culture and Sports the construction of a 1.8 GeV electron storage ring suitable for 'Top-Up' operation and beamlines and monochromators designed for undulator radiation. The scientific programs proposed by nationwide scientists are summarized with their requirements of the characteristics of the beam. (author)

Nuclear materials facility safety initiative

International Nuclear Information System (INIS)

Peddicord, K.L.; Nelson, P.; Roundhill, M.; Jardine, L.J.; Lazarev, L.; Moshkov, M.; Khromov, V.V.; Kruchkov, E.; Bolyatko, V.; Kazanskij, Yu.; Vorobeva, I.; Lash, T.R.; Newton, D.; Harris, B.

2000-01-01

Safety in any facility in the nuclear fuel cycle is a fundamental goal. However, it is recognized that, for example, should an accident occur in either the U.S. or Russia, the results could seriously delay joint activities to store and disposition weapons fissile materials in both countries. To address this, plans are underway jointly to develop a nuclear materials facility safety initiative. The focus of the initiative would be to share expertise which would lead in improvements in safety and safe practices in the nuclear fuel cycle.The program has two components. The first is a lab-to-lab initiative. The second involves university-to-university collaboration.The lab-to-lab and university-to-university programs will contribute to increased safety in facilities dealing with nuclear materials and related processes. These programs will support important bilateral initiatives, develop the next generation of scientists and engineers which will deal with these challenges, and foster the development of a safety culture

Chemical inventory control program for mixed and hazardous waste facilities at SRS

International Nuclear Information System (INIS)

Ades, M.J.; Vincent, A.M. III.

1997-01-01

Mixed Waste (MW) and Hazardous Waste (HW) are being stored at the Savannah River Site (SRS) pending onsite and/or offsite treatment and disposal. The inventory control for these wastes has recently been brought under Technical Safety Requirements (TSR) in accordance with DOE Order 5480.22. With the TSRs was the question of the degree of rigor with which the inventory is to be tracked, considering that the variety of chemicals present, or that could be present, numbers in the hundreds. This paper describes the graded approach program to track Solid Waste (SW) inventories relative to TSRs. The approach uses a ratio of the maximum anticipated chemical inventory to the permissible inventory in accordance with Emergency Response Planning Guideline (ERPG) limits for on- and off-site receptors. A specific threshold ratio can then be determined. The chemicals above this threshold ratio are to be included in the chemical inventory control program. The chemicals that fall below the threshold ratio are managed in accordance with existing practice per State and RCRA hazardous materials requirements. Additionally, the facilities are managed in accordance with process safety management principles, specifically using process hazards analyses, which provides safety assurance for even the small quantities that may be excluded from the formal inventory control program. The method yields a practical approach to chemical inventory control, while maintaining appropriate chemical safety margins. The resulting number of specific chemicals that require inclusion in a rigorous inventory control program is greatly reduced by about 80%, thereby resulting in significant reduction in chemical data management while preserving appropriate safety margins

34 CFR 104.22 - Existing facilities.

Science.gov (United States)

2010-07-01

... 34 Education 1 2010-07-01 2010-07-01 false Existing facilities. 104.22 Section 104.22 Education... Accessibility § 104.22 Existing facilities. (a) Accessibility. A recipient shall operate its program or activity.... This paragraph does not require a recipient to make each of its existing facilities or every part of a...

34 CFR 106.33 - Comparable facilities.

Science.gov (United States)

2010-07-01

... 34 Education 1 2010-07-01 2010-07-01 false Comparable facilities. 106.33 Section 106.33 Education... Discrimination on the Basis of Sex in Education Programs or Activities Prohibited § 106.33 Comparable facilities. A recipient may provide separate toilet, locker room, and shower facilities on the basis of sex, but...

45 CFR 618.410 - Comparable facilities.

Science.gov (United States)

2010-10-01

... 45 Public Welfare 3 2010-10-01 2010-10-01 false Comparable facilities. 618.410 Section 618.410... Discrimination on the Basis of Sex in Education Programs or Activities Prohibited § 618.410 Comparable facilities. A recipient may provide separate toilet, locker room, and shower facilities on the basis of sex, but...

31 CFR 28.410 - Comparable facilities.

Science.gov (United States)

2010-07-01

... 31 Money and Finance: Treasury 1 2010-07-01 2010-07-01 false Comparable facilities. 28.410 Section... on the Basis of Sex in Education Programs or Activities Prohibited § 28.410 Comparable facilities. A recipient may provide separate toilet, locker room, and shower facilities on the basis of sex, but such...

Environmental Monitoring, Water Quality - Water Pollution Control Facilities

Data.gov (United States)

NSGIC Education | GIS Inventory — A Water Pollution Control Facility is a DEP primary facility type related to the Water Pollution Control Program. The sub-facility types related to Water Pollution...

TMI-2 Vessel Investigation Project Metallurgical Program

International Nuclear Information System (INIS)

Diercks, D.R.; Neimark, L.A.

1990-01-01

The TMI-2 [Three Mile Island unit 2] Vessel Investigation Project Metallurgical Program at Argonne National Laboratory is a part of the international TMI-2 Vessel Investigation Project being conducted jointly by the U.S. Nuclear Regulatory Commission and the Organization for Economic Co-operation and Development (OECD). The overall project consists of three phases, namely (1) recovery of material samples from the lower head of the TMI-2 reactor, (2) examination and analysis of the lower head samples and the preparation and testing of archive material subjected to a similar thermal history, and (3) procurement, examination, and analysis of companion core material located adjacent to or near the lower head material. The specific objectives of the ANL Metallurgical Program, which accounts for a major portion of Phase 2, are to prepare metallographic and mechanical test specimen blanks from the TMI-2 lower head material, prepare similar test specimen blanks from suitable archive material subjected to the appropriate thermal processing, determine the mechanical properties of the lower vessel head and archive materials under the conditions of the core-melt accident, and assess the lower head integrity and margin-to-failure during the accident. The ANL work consists of three tasks: (1) archive materials program, (2) fabrication of metallurgical and mechanical test specimens from the TMI-2 pressure vessel samples, and (3) mechanical property characterization of TMI-2 lower pressure vessel head and archive material

Environmental monitoring radiological programs for the nuclear centre and the low level radioactive waste facility in Mexico

International Nuclear Information System (INIS)

Quintero, E.; Cervantes, L.; Rojas, V.

2006-01-01

The National Institute of Nuclear Research of Mexico (ININ) has its Laboratory of Environmental Radiological Monitoring, (LVRA), to assure the critical population and the environment they are not exposed to radiation doses greater than the limits established by the national and international legislation, this laboratory carries out environmental monitoring radiological programs the Nuclear Centre and its surroundings and the Low Level Radioactive Waste Facility (CADER) and its around. In order to carry out these programs the LVRA has rooms for evaporation, drying, grinding, ashing of environmental and food samples, and a laboratory for gamma ray spectrometry, liquid scintillation, alpha-beta gross counting and computer room. Since the year 2000 the (ININ) has tried to implant the quality system ISO 9001:2000 including a its (LVRA). This quality system includes: a Plan of Quality, Quality Manual, programs of technical and administrative document elaboration, technical and administrative procedures, technical and administrative qualification programmes for the laboratory staff, maintenance and calibration programs for measurement systems and finally participation in national and international exercises of intercomparison. The ININ counts with the management of quality assurance to verify these programs, in addition, our Nuclear Regulatory Commission (CNSNS) carries out periodic audits to authorize the of use and handling of radioactive and nuclear material licenses of these facilities. In this work we presented the advances and difficulties found in the implantation of the quality system, also we present the benefits obtained with uses of this system, the samples analyses results, and the calculation of the annual dose to the critical population for the last five years. In addition, we presented the calculation the radionuclides concentration tendencies in different sample types, according to our (CNSNS) requirements. In the same way the results of the calibrations

Antimicrobial stewardship in long term care facilities: what is effective?

Science.gov (United States)

Nicolle, Lindsay E

2014-02-12

Intense antimicrobial use in long term care facilities promotes the emergence and persistence of antimicrobial resistant organisms and leads to adverse effects such as C. difficile colitis. Guidelines recommend development of antimicrobial stewardship programs for these facilities to promote optimal antimicrobial use. However, the effectiveness of these programs or the contribution of any specific program component is not known. For this review, publications describing evaluation of antimicrobial stewardship programs for long term care facilities were identified through a systematic literature search. Interventions included education, guidelines development, feedback to practitioners, and infectious disease consultation. The studies reviewed varied in types of facilities, interventions used, implementation, and evaluation. Comprehensive programs addressing all infections were reported to have improved antimicrobial use for at least some outcomes. Targeted programs for treatment of pneumonia were minimally effective, and only for indicators of uncertain relevance for stewardship. Programs focusing on specific aspects of treatment of urinary infection - limiting treatment of asymptomatic bacteriuria or prophylaxis of urinary infection - were reported to be effective. There were no reports of cost-effectiveness, and the sustainability of most of the programs is unclear. There is a need for further evaluation to characterize effective antimicrobial stewardship for long term care facilities.

10 CFR 850.27 - Hygiene facilities and practices.

Science.gov (United States)

2010-01-01

... 10 Energy 4 2010-01-01 2010-01-01 false Hygiene facilities and practices. 850.27 Section 850.27 Energy DEPARTMENT OF ENERGY CHRONIC BERYLLIUM DISEASE PREVENTION PROGRAM Specific Program Requirements § 850.27 Hygiene facilities and practices. (a) General. The responsible employer must assure that in...

E-SCAPE: A scale facility for liquid-metal, pool-type reactor thermal hydraulic investigations

Energy Technology Data Exchange (ETDEWEB)

Van Tichelen, Katrien, E-mail: kvtichel@sckcen.be [SCK-CEN, Boeretang 200, 2400 Mol (Belgium); Mirelli, Fabio, E-mail: fmirelli@sckcen.be [SCK-CEN, Boeretang 200, 2400 Mol (Belgium); Greco, Matteo, E-mail: mgreco@sckcen.be [SCK-CEN, Boeretang 200, 2400 Mol (Belgium); Viviani, Giorgia, E-mail: giorgiaviviani@gmail.com [University of Pisa, Lungarno Pacinotti 43, 56126 Pisa (Italy)

2015-08-15

Highlights: • The E-SCAPE facility is a thermal hydraulic scale model of the MYRRHA fast reactor. • The focus is on mixing and stratification in liquid-metal pool-type reactors. • Forced convection, natural convection and the transition are investigated. • Extensive instrumentation allows validation of computational models. • System thermal hydraulic and CFD models have been used for facility design. - Abstract: MYRRHA (Multi-purpose hYbrid Research Reactor for High-tech Applications) is a flexible fast-spectrum research reactor under design at SCK·CEN. MYRRHA is a pool-type reactor with lead bismuth eutectic (LBE) as primary coolant. The proper understanding of the thermal hydraulic phenomena occurring in the reactor pool is an important issue in the design and licensing of the MYRRHA system and liquid-metal cooled reactors by extension. Model experiments are necessary for understanding the physics, for validating experimental tools and to qualify the design for the licensing. The E-SCAPE (European SCAled Pool Experiment) facility at SCK·CEN is a thermal hydraulic 1/6-scale model of the MYRRHA reactor, with an electrical core simulator, cooled by LBE. It provides experimental feedback to the designers on the forced and natural circulation flow patterns. Moreover, it enables to validate the computational methods for their use with LBE. The paper will elaborate on the design of the E-SCAPE facility and its main parameters. Also the experimental matrix and the pre-test analysis using computational fluid dynamics (CFD) and system thermal hydraulics codes will be described.

7 CFR 210.13 - Facilities management.

Science.gov (United States)

2010-01-01

... 7 Agriculture 4 2010-01-01 2010-01-01 false Facilities management. 210.13 Section 210.13... Participation § 210.13 Facilities management. Link to an amendment published at 74 FR 66216, Dec. 15, 2009. (a..., the added text is set forth as follows: § 210.13 Facilities management. (c) Food safety program. The...

Manipulator system man-machine interface evaluation program. [technology assessment

Science.gov (United States)

Malone, T. B.; Kirkpatrick, M.; Shields, N. L.

1974-01-01

Application and requirements for remote manipulator systems for future space missions were investigated. A manipulator evaluation program was established to study the effects of various systems parameters on operator performance of tasks necessary for remotely manned missions. The program and laboratory facilities are described. Evaluation criteria and philosophy are discussed.

An investigation of scale effects in family substance abuse treatment programs

Directory of Open Access Journals (Sweden)

Lee A James

2010-07-01

Full Text Available Abstract This short report investigates scale effects in family substance abuse treatment programs. In Massachusetts, the family substance abuse treatment programs were much more costly than other adult residential treatment models. State officials were concerned that the "scale" or size of these programs (averaging just eight families was too small to be economical. Although the sample size (just nine programs was too small to permit reliable inference, the data clearly signalled the importance of "scale effects" in these family substance abuse treatment programs. To further investigate scale effects in family substance abuse treatment programs, data from the Center for Substance Abuse Treatment's (CSAT's Residential Women and Children and Pregnant and Postpartum Women (RWC-PPW Demonstration were re-analyzed, focusing on the relationship between cost per family-day and the estimated average family census. This analysis indicates strong economies of scale up until an average family census of about 14, and less apparent scale effects beyond that point. In consideration of these and other study findings, a multidisciplinary interagency team redesigned the Massachusetts' family treatment program model. The new programs are larger than the former family treatment programs, with each new program having capacity to treat 11 to 15 families depending on family makeup.

Survey of tritium wastes and effluents in near-term fusion-research facilities

International Nuclear Information System (INIS)

Bickford, W.E.; Dingee, D.A.; Willingham, C.E.

1981-08-01

The use of tritium control technology in near-term research facilities has been studied for both the magnetic and inertial confinement fusion programs. This study focused on routine generation of tritium wastes and effluents, with little referene to accidents or facility decommissioning. This report serves as an independent review of the effectiveness of planned control technology and radiological hazards associated with operation. The facilities examined for the magnetic fusion program included Fusion Materials Irradiation Testing Facility (FMIT), Tritium Systems Test Assembly (TSTA), and Tokamak Fusion Test Reactor (TFTR) in the magnetic fusion program, while NOVA and Antares facilities were examined for the inertial confinement program

Environmental monitoring program of the uranium enrichment facility Almirante Alvaro Alberto

International Nuclear Information System (INIS)

Hiromoto, G.; Jacomino, V.M.F.; Venturini, L.; Moreira, S.R.D.; Gordon, A.M.P.L.; Duarte, C.L.; Pocequilo, B.R.S.; Mazzilli, B.P.

1988-11-01

In this report, the Environmental Monitoring Program of the Uranium Enrichment Facility Almirante Alvaro Alberto is outlined and the results obtained during the preoperational period are presented. Information concerning the population distribution, the use of water and land, the local agricultural production and the local meteorology are also available. In order to evaluate the levels of the background radiation, sample of water, air and biological and terrestrial indicators were analysed. Measurements were performed of natural gamma emitters concentrations levels and of uranium in air, surface water, precipitation, groundwater, river sediment, soil, grass, vegetation and various foodstuffs. For direct measurement of background radiation levels a solid state dosimeter network was used. Results are also presented for the analysis of non radioactive pollutants in the water samples and for the particles and gaseous fluorides concentration in the atmosphere. (author) [pt

Report of investigation regarding accident in Tomsk reprocessing facilities in Russia

International Nuclear Information System (INIS)

1994-01-01

At 1258 on April 6, 1993, the explosion accident of a welded tank occurred in the military reprocessing facilities in Tomsk, Siberia District, Russia. Japan carried out the investigation of the effect on the environmental radiation in Japan, dispatched the investigation mission to Russia, and explained the way of thinking on securing the safety of Japanese reprocessing plants to local communities. Science and Technology Agency organized the working group for investigating the accident, which exerted efforts to collect the information, analyze and examine it. This report is the summary of its results. The explosion occurred in the tank for adjusting the acid concentration of the solution to be supplied to the solvent extraction shop, and the building was destructed. No one died or was injured. The results of the radioactivity examination are reported. The process of the accident was inferred, and described. The factors that caused the accident were the mixing of organic impurities the use of the diluting liquid containing aromatic hydrocarbon, the contact of nitric acid with organic substances at high temperature, in sufficient agitation at the time of pouring nitric acid and so on. The safety countermeasures in Japanese reprocessing plants and the response by Japan based on the accident are described. (K.I.)

Oak Ridge Reservation Federal Facility Agreement for the Environmental Restoration Program. Volume 4

International Nuclear Information System (INIS)

1993-10-01

This quarterly progress report satisfies requirements for the Environmental Restoration (ER) Program that are specified in the Oak Ridge Reservation (ORR) Federal Facility Agreement (FFA) established between the U.S. Department of Energy (DOE), the U.S. Environmental protection Agency (EPA), and the Tennessee Department of Environment and Conservation (TDEC). The reporting period covered is July through September 1993 (fourth quarter of FY 1993). Sections 1.1 and 1.2 provide respectively the milestones scheduled for completion during the reporting period and a list of documents that have been proposed for transmittal during the following quarter but have not been approved as FY 1994 commitments

An Investigation of Teaching and Learning Programs in Pharmacy Education.

Science.gov (United States)

Strang, Aimee F; Baia, Patricia

2016-05-25

Objective. To investigate published, peer-reviewed literature on pharmacy teaching and learning development programs and to synthesize existing data, examine reported efficacy and identify future areas for research. Methods. Medline and ERIC databases were searched for studies on teaching development programs published between 2001 and 2015. Results. Nineteen publications were included, representing 21 programs. Twenty programs were resident teaching programs, one program described faculty development. The majority of programs spanned one year and delivered instruction on teaching methodologies and assessment measures. All except one program included experiential components. Thirteen publications presented outcomes data; most measured satisfaction and self-perceived improvement. Conclusion. Published literature on teacher development in pharmacy is focused more on training residents than on developing faculty members. Although programs are considered important and highly valued by program directors and participants, little data substantiates that these programs improve teaching. Future research could focus on measurement of program outcomes and documentation of teaching development for existing faculty members.

Environmental monitoring of nuclear facilities

International Nuclear Information System (INIS)

Winter, M.

1983-01-01

The objectives of one environmental monitoring program for nuclear facilities, are presented. The program in Federal Republic of Germany, its goals, its basic conditions, its regulations, and its dose limits are emphasized. (E.G.) [pt

Analytical throughput-estimating methods for the Hot Fuel Examination Facility

International Nuclear Information System (INIS)

Keyes, R.W.; Phipps, R.D.

1983-01-01

The Hot Fuel Examination Facility (HFEF) supports the operation and experimental programs of the major Liquid Metal Fast Breeder Reactor (LMFBR) test facilities; specifically, the Fast Flux Test Facility (FFTF), the Experimental Breeder Reactor II (EBR-II), and the Transient Reactor Test (TREAT) Facility. Successful management of HFEF and of LMFBR safety and fuels and materials programs, therefore, requires reliable information regarding HFEF's capability to handle expected or proposed program work loads. This paper describes the 10-step method that has been developed to consider all variables which significantly affect the HFEF examination throughput and quickly provide the necessary planning information

[Design of an HACCP program for a cocoa processing facility].

Science.gov (United States)

López D'Sola, Patrizia; Sandia, María Gabriela; Bou Rached, Lizet; Hernández Serrano, Pilar

2012-12-01

The HACCP plan is a food safety management tool used to control physical, chemical and biological hazards associated to food processing through all the processing chain. The aim of this work is to design a HACCP Plan for a Venezuelan cocoa processing facility.The production of safe food products requires that the HACCP system be built upon a solid foundation of prerequisite programs such as Good Manufacturing Practices (GMP) and Sanitation Standard Operating Procedures (SSOP). The existence and effectiveness of these prerequisite programs were previously assessed.Good Agriculture Practices (GAP) audit to cocoa nibs suppliers were performed. To develop the HACCP plan, the five preliminary tasks and the seven HACCP principles were accomplished according to Codex Alimentarius procedures. Three Critical Control Points (CCP) were identified using a decision tree: winnowing (control of ochratoxin A), roasting (Salmonella control) and metallic particles detection. For each CCP, Critical limits were established, the Monitoring procedures, Corrective actions, Procedures for Verification and Documentation concerning all procedures and records appropriate to these principles and their application was established. To implement and maintain a HACCP plan for this processing plant is suggested. Recently OchratoxinA (OTA) has been related to cocoa beans. Although the shell separation from the nib has been reported as an effective measure to control this chemical hazard, ochratoxin prevalence study in cocoa beans produced in the country is recommended, and validate the winnowing step as well

Development and implementation of a construction environmental protection program at a solid radioactive waste management facility

Energy Technology Data Exchange (ETDEWEB)

Wong, T.S. [Atomic Energy of Canada Limited, Mississauga, Ontario (Canada); Bishop, T. [Atomic Energy of Canada Limited, Saint John, New Brunswick (Canada); Hickman, C.N. [Point Lepreau Generating Station, Saint John, New Brunswick (Canada)

2007-07-01

Refurbishment of ageing nuclear stations has great economic and environmental benefits, including reduced greenhouse gas emissions. The Government of New Brunswick (NB) decided in 2005 to refurbish the Point Lepreau Generating Station with Atomic Energy of Canada Limited (AECL) as the general contractor. The project includes construction of additional radioactive waste management facilities. AECL developed, for the construction project, an environmental protection program to comply with commitments made during the environmental assessment process, and regulatory requirements. The program covers detailed environmental plans, training courses, and engagement of consultants to provide training and conduct monitoring of the construction activities. Construction related environmental effects have been successfully mitigated and the monitoring results indicate compliance with all environmental requirements. (author)

Medicare Program; Inpatient Rehabilitation Facility Prospective Payment System for Federal Fiscal Year 2018. Final rule.

Science.gov (United States)

2017-08-03

This final rule updates the prospective payment rates for inpatient rehabilitation facilities (IRFs) for federal fiscal year (FY) 2018 as required by the statute. As required by section 1886(j)(5) of the Social Security Act (the Act), this rule includes the classification and weighting factors for the IRF prospective payment system's (IRF PPS) case-mix groups and a description of the methodologies and data used in computing the prospective payment rates for FY 2018. This final rule also revises the International Classification of Diseases, 10th Revision, Clinical Modification (ICD-10-CM) diagnosis codes that are used to determine presumptive compliance under the "60 percent rule," removes the 25 percent payment penalty for inpatient rehabilitation facility patient assessment instrument (IRF-PAI) late transmissions, removes the voluntary swallowing status item (Item 27) from the IRF-PAI, summarizes comments regarding the criteria used to classify facilities for payment under the IRF PPS, provides for a subregulatory process for certain annual updates to the presumptive methodology diagnosis code lists, adopts the use of height/weight items on the IRF-PAI to determine patient body mass index (BMI) greater than 50 for cases of single-joint replacement under the presumptive methodology, and revises and updates measures and reporting requirements under the IRF quality reporting program (QRP).

A conversion development program to LEU targets for medical isotope production in the MAPLE Facilities

International Nuclear Information System (INIS)

Malkoske, G.R.

2000-01-01

Historically, the production of molybdenum-99 in the NRU research reactors at Chalk River, Canada has been extracted from reactor targets employing highly enriched uranium (HEU). The molybdenum extraction process from the HEU targets provided predictable, consistent yields for our high-volume molybdenum production process. A reliable supply of HEU for the NRU research reactor targets has enabled MDS Nordion to develop a secure chain of medical isotope supply for the international nuclear medicine community. Each link of the isotope supply chain, from isotope production to patient application, has been established on a proven method of HEU target irradiation and processing. To ensure a continued reliable and timely supply of medical isotopes, the design of the MAPLE facilities was based on our established process - extraction of isotopes from HEU target material. However, in concert with the global trend to utilize low enriched uranium (LEU) in research reactors, MDS Nordion has launched a program to convert the MAPLE facilities to LEU targets. An initial feasibility study was initiated to identify the technical issues to convert the MAPLE targets from HEU to LEU. This paper will present the results of the feasibility study. It will also describe future challenges and opportunities in converting the MAPLE facilities to LEU targets for large scale, commercial medical isotope production. (author)

New instrument calibration facility for the DOE Savannah River Site

Energy Technology Data Exchange (ETDEWEB)

Wilkie, W.H.; Polz, E.J. [Westinghouse Savannah River Company, Aiken, SC (United States)

1993-12-31

A new laboratory facility is being designed, constructed, and equipped at the Savannah River Site (SRS) as a fiscal year 1992 line item project. This facility will provide space and equipment for test, evaluation, repair, maintenance, and calibration of radiation monitoring instrumentation. The project will replace an obsolete facility and will allow implementation of program upgrades necessary to meet ANSI N323 requirements and National Voluntary Laboratory Accreditation Program (NVLAP) criteria for accreditation of federally owned secondary calibration laboratories. An outline of the project is presented including description, scope, cost, management organization, chronology, and current status. Selected design criteria and their impacts on the project are discussed. The upgraded SRS calibration program is described, and important features of the new facility and equipment that will accommodate this program are listed. The floor plan for the facility is shown, and equipment summaries and functional descriptions for each area are provided.

New instrument calibration facility for the DOE Savannah River Site

International Nuclear Information System (INIS)

Wilkie, W.H.; Polz, E.J.

1993-01-01

A new laboratory facility is being designed, constructed, and equipped at the Savannah River Site (SRS) as a fiscal year 1992 line item project. This facility will provide space and equipment for test, evaluation, repair, maintenance, and calibration of radiation monitoring instrumentation. The project will replace an obsolete facility and will allow implementation of program upgrades necessary to meet ANSI N323 requirements and National Voluntary Laboratory Accreditation Program (NVLAP) criteria for accreditation of federally owned secondary calibration laboratories. An outline of the project is presented including description, scope, cost, management organization, chronology, and current status. Selected design criteria and their impacts on the project are discussed. The upgraded SRS calibration program is described, and important features of the new facility and equipment that will accommodate this program are listed. The floor plan for the facility is shown, and equipment summaries and functional descriptions for each area are provided

Applications of microtron facility

International Nuclear Information System (INIS)

Sanjeev, Ganesh

2013-01-01

An 8 MeV Microtron accelerator installed and commissioned in Mangalore University to strengthen research activities in the area of Radiation Physics and allied sciences is also being used extensively for coordinated research programs in basic and applied areas of science and technology involving researchers from national laboratories and sister universities of the region. The electron accelerator with its versatile features extends energetic electrons, intense photons and neutrons of moderate flux to cater to the needs of the users of the facility. A brief view of this 'first of its kind' facility in the country and the R and D programs with some sample results is presented. (author)

Making of the NSTX Facility

International Nuclear Information System (INIS)

Neumeyer, C.; Ono, M.; Kaye, S.M.; Peng, Y.-K.M.

1999-01-01

The NSTX (National Spherical Torus Experiment) facility located at Princeton Plasma Physics Laboratory is the newest national fusion science experimental facility for the restructured US Fusion Energy Science Program. The NSTX project was approved in FY 97 as the first proof-of-principle national fusion facility dedicated to the spherical torus research. On Feb. 15, 1999, the first plasma was achieved 10 weeks ahead of schedule. The project was completed on budget and with an outstanding safety record. This paper gives an overview of the NSTX facility construction and the initial plasma operations

Molecular Contamination Investigation Facility (MCIF) Capabilities

Science.gov (United States)

Soules, David M.

2013-01-01

This facility was used to guide the development of ASTM E 1559 center dot Multiple Quartz Crystal Microbalances (QCMs), large sample and spectral effects capability center dot Several instrumented, high vacuum chamber systems are used to evaluate the molecular outgassing characteristics of materials, flight components and other sensitive surfaces. Test materials for spacecraft/instrument selection center.Test flight components for acceptable molecular outgas levels center dot Determine time/temperature vacuum bake-out requirements center. Data used to set limits for use of materials and specific components center. Provide Input Data to Contamination Transport Models -Applied to numerous flight projects over the past 20 years.

Model training curriculum for Low-Level Radioactive Waste Disposal Facility Operations

Energy Technology Data Exchange (ETDEWEB)

Tyner, C.J.; Birk, S.M.

1995-09-01

This document is to assist in the development of the training programs required to be in place for the operating license for a low-level radioactive waste disposal facility. It consists of an introductory document and four additional appendixes of individual training program curricula. This information will provide the starting point for the more detailed facility-specific training programs that will be developed as the facility hires and trains new personnel and begins operation. This document is comprehensive and is intended as a guide for the development of a company- or facility-specific program. The individual licensee does not need to use this model training curriculum as written. Instead, this document can be used as a menu for the development, modification, or verification of customized training programs.

Model training curriculum for Low-Level Radioactive Waste Disposal Facility Operations

International Nuclear Information System (INIS)

Tyner, C.J.; Birk, S.M.

1995-09-01

This document is to assist in the development of the training programs required to be in place for the operating license for a low-level radioactive waste disposal facility. It consists of an introductory document and four additional appendixes of individual training program curricula. This information will provide the starting point for the more detailed facility-specific training programs that will be developed as the facility hires and trains new personnel and begins operation. This document is comprehensive and is intended as a guide for the development of a company- or facility-specific program. The individual licensee does not need to use this model training curriculum as written. Instead, this document can be used as a menu for the development, modification, or verification of customized training programs

Program user's manual: cryogen system for the analysis for the Mirror Fusion Test Facility

International Nuclear Information System (INIS)

1979-04-01

The Mirror Fusion Test Facility being designed and constructed at the Lawrence Livermore Laboratory requires a liquid helium liquefaction, storage, distribution, and recovery system and a liquid nitrogen storage and distribution system. To provide a powerful analytical tool to aid in the design evolution of this system through hardware, a thermodynamic fluid flow model was developed. This model allows the Lawrence Livermore Laboratory to verify that the design meets desired goals and to play what if games during the design evolution. For example, what if the helium flow rate is changed in the magnet liquid helium flow loop; how does this affect the temperature, fluid quality, and pressure. This manual provides all the information required to run all or portions of this program as desired. In addition, the program is constructed in a modular fashion so changes or modifications can be made easily to keep up with the evolving design

EPA Linked Open Data: Facility Registry Service

Data.gov (United States)

U.S. Environmental Protection Agency — The Facility Registry Service (FRS) identifies facilities, sites, or places subject to environmental regulation or of environmental interest to EPA programs or...

40 CFR 60.32c - Designated facilities.

Science.gov (United States)

2010-07-01

... 40 Protection of Environment 6 2010-07-01 2010-07-01 false Designated facilities. 60.32c Section 60.32c Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) AIR PROGRAMS (CONTINUED... Solid Waste Landfills § 60.32c Designated facilities. (a) The designated facility to which the...

Horonobe Underground Research Laboratory project. Plans of investigations during shaft and drift excavation (Construction of underground facilities: Phase II)

International Nuclear Information System (INIS)

2005-06-01

Horonobe Underground Research Laboratory Project is planned for over 20 years to establish the scientific and technical basis for the underground disposal of high-level radioactive wastes in Japan. The investigations are conducted by JNC in three phases, from the surface (Phase I), during the construction of the underground facilities (Phase II), and using the facilities (Phase III). This report concerns the investigation plans for Phase II. During excavation of shafts and drifts, detailed geological and borehole investigation will be conducted and the geological model constructed in Phase I is evaluated and revised by newly acquired data of geophysical and geological environment. Detailed in-situ experiments, as well as the effects of shaft excavation, are also done to study long-term changes, rock properties, groundwater flow and chemistry to ensure the reliability of repository technology and establish safety assessment methodology. (S. Ohno)

Investigating the Availability of Quality Assurance Standards of Academic Programs in the Music Teacher Preparation Program- University of Jordan, from the Students’ Perspective

Directory of Open Access Journals (Sweden)

Nedal M. Nsairat

2017-08-01

Full Text Available This study aimed to find out how far quality assurance standards were applied in the music teacher preparation program at the University of Jordan, from the viewpoint of the students enrolled in the same program. The population of this study consisted of all the students (53 enrolled in the program , and majoring in music education and music performance. The study followed a descriptive analytical approach to collect the data. The study results revealed the extent of relevance of the BA program of preparing music teachers in the University of Jordan, which came as a result of applying each quality assurance standard in the program except the standard of facilities and equipment. In light of the findings, the study recommended that all those in charge of the educational process should pay more heed to certification programs of music teacher education. This should be done by designing and implementing programs to support this type of program, so as to be in conformity with quality assurance standards of music teacher education. Keywords: Preparation , Music teacher education , Standard , Quality assurance.

Investigating proton emitters at the limits of stability with radioactive beams from the Oak Ridge facility

Energy Technology Data Exchange (ETDEWEB)

Toth, K.S. [Oak Ridge National Lab., TN (United States); Batchelder, J.C.; Zganjar, E.F. [Louisiana State Univ., Baton Rouge, LA (United States); Bingham, C.R.; Wauters, J. [Tennessee Univ., Knoxville, TN (United States); Davinson, T.; MacKenzie, J.A.; Woods, P.J. [Edinburgh Univ. (United Kingdom)

1996-10-01

By using beams from the Holifield Radioactive Ion Beam Facility at ORNL, it should be possible to identify many new ground-state proton emitters in the mass region from Sn to Pb. In these investigations nuclei produced in fusion-evaporation reactions will be separated from incident ions and dispersed in mass/charge with a recoil mass separator and then implanted into a double-sided Si strip detector for study of proton (and {alpha}-particle) radioactivity. This paper summarizes data presently extant on proton emitters and then focuses on tests and initial experiments that will be carried out with stable beams and with radioactive ions as they are developed at the Oak Ridge facility.

Horonobe underground research program. Research report of 2002 FY investigation

International Nuclear Information System (INIS)

2003-06-01

Main results of investigation about Horonobe deep underground research center in 2002 FY were reported. It consists of six chapters: introduction, main results, selection of research center area, underground science research, R and D of geological disposal, and the environmental survey and research center on the ground. The research center area at about 3 km north of Horonobe (B1) was selected in the four areas: A, B1, B2 and C on the basis of data, researches in the sky, aboveground and underground and other conditions. The model of geological environment was constructed by physical, geological, surface water supply researches. Development of geological environment monitoring techniques, investigation of long stabilization of geological environment and design of underground facilities are reported. The basic design of preparation of research center was investigated. (S.Y.)

[Dynamics of tooth decay prevalence in children receiving long-term preventive program in school dental facilities].

Science.gov (United States)

Avraamova, O G; Kulazhenko, T V; Gabitova, K F

2016-01-01

The paper presents the assessment of tooth decay prevalence in clinically homogenous groups of children receiving long-term preventive program (PP) in school dental facilities. Five-years PP were introduced in clinical practice in 2 Moscow schools. Preventive treatment was performed by dental hygienist. The results show that systematic preventive treatment in school dental offices starting from elementary school allows reducing dental caries incidence 46-53% and stabilize the incidence of caries complications. It should be mentioned though that analysis of individualized outcomes proves heterogeneity of study results despite of equal conditions of PP. Potentially significant hence is early diagnostics and treatment of initial caries forms as demineralization foci, especially in children with intensive tooth decay. Optimization of pediatric dentist and dental hygienist activity in school dental facilities is the main factor of caries prevention efficiency.

Decommissioning and Decontamination Program: Battelle Plutonium Facility, Environmental assessment

International Nuclear Information System (INIS)

1979-09-01

This assessment describes the decontamination of Battelle-Columbus Plutonium Facility and removal from the site of all material contamination which was associated with or produced by the Plutonium Facility. Useable uncontaminated material will be disposed of by procedures normally employed in scrap declaration and transfer. Contaminated waste will be transported to approved radioactive waste storage sites. 5 refs., 1 fig

Report of preliminary investigations on the next-generation large-scale synchrotron radiation facility projects

International Nuclear Information System (INIS)

1990-01-01

The Special Committee for Future Project of the Japanese Society for Synchrotron Radiation Research investigated the construction-projects of the large-scaled synchrotron radiation facilities which are presently in progress in Japan. As a result, the following both projects are considered the very valuable research-project which will carry the development of Japan's next-generation synchrotron radiation science: 1. the 8 GeV synchrotron radiation facilities (SPring-8) projected to be constructed by Japan Atomic Energy Research Institute and the Institute of Physical and Chemical Research under the sponsorship of Science Technology Agency at Harima Science Park City, Hyogo Pref., Japan. 2. The project to utilize the Tristan Main Ring (MR) of the National Laboratory for High Energy Physics as the radiation source. Both projects are unique in research theme and technological approach, and complemental each other. Therefore it has been concluded that both projects should be aided and ratified by the Society. (M.T.)

Investigation of development and management of treatment planning systems for BNCT at foreign facilities

International Nuclear Information System (INIS)

2001-03-01

A new computational dosimetry system for BNCT: JCDS is developed by JAERI in order to carry out BNCT with epithermal neutron beam at present. The development and management situation of computational dosimetry system, which are developed and are used in BNCT facilities in foreign countries, were investigated in order to accurately grasp functions necessary for preparation of the treatment planning and its future subjects. In present state, 'SERA', which are developed by Idaho National Engineering and Environmental Laboratory (INEEL), is used in many BNCT facilities. Followings are necessary for development and management of the treatment planning system. (1) Reliability confirmation of system performance by verification as comparison examination of calculated value with actual experimental measured value. (2) Confirmation systems such as periodic maintenance for retention of the system quality. (3) The improvement system, which always considered relative merits and demerits with other computational dosimetry system. (4) The development of integrated system with patient setting. (author)

Nuclear physics accelerator facilities

International Nuclear Information System (INIS)

1988-12-01

This paper describes many of the nuclear physics heavy-ion accelerator facilities in the US and the research programs being conducted. The accelerators described are: Argonne National Laboratory--ATLAS; Brookhaven National Laboratory--Tandem/AGS Heavy Ion Facility; Brookhaven National Laboratory--Relativistic Heavy Ion Collider (RHIC) (Proposed); Continuous Electron Beam Accelerator Facility; Lawrence Berkeley Laboratory--Bevalac; Lawrence Berkeley Laboratory--88-Inch Cyclotron; Los Alamos National Laboratory--Clinton P. Anderson Meson Physics Facility (LAMPF); Massachusetts Institute of Technology--Bates Linear Accelerator Center; Oak Ridge National Laboratory--Holifield Heavy Ion Research Facility; Oak Ridge National Laboratory--Oak Ridge Electron Linear Accelerator; Stanford Linear Accelerator Center--Nuclear Physics Injector; Texas AandM University--Texas AandM Cyclotron; Triangle Universities Nuclear Laboratory (TUNL); University of Washington--Tandem/Superconducting Booster; and Yale University--Tandem Van de Graaff

Workplace Violence Training Programs for Health Care Workers: An Analysis of Program Elements.

Science.gov (United States)

Arbury, Sheila; Hodgson, Michael; Zankowski, Donna; Lipscomb, Jane

2017-06-01

Commercial workplace violence (WPV) prevention training programs differ in their approach to violence prevention and the content they present. This study reviews 12 such programs using criteria developed from training topics in the Occupational Safety and Health Administration's (OSHA) Guidelines for Preventing Workplace Violence for Healthcare and Social Service Workers and a review of the WPV literature. None of the training programs addressed all the review criteria. The most significant gap in content was the lack of attention to facility-specific risk assessment and policies. To fill this gap, health care facilities should supplement purchased training programs with specific training in organizational policies and procedures, emergency action plans, communication, facility risk assessment, and employee post-incident debriefing and monitoring. Critical to success is a dedicated program manager who understands risk assessment, facility clinical operations, and program management and evaluation.

Mechanistic facility safety and source term analysis

International Nuclear Information System (INIS)

PLYS, M.G.

1999-01-01

A PC-based computer program was created for facility safety and source term analysis at Hanford The program has been successfully applied to mechanistic prediction of source terms from chemical reactions in underground storage tanks, hydrogen combustion in double contained receiver tanks, and proccss evaluation including the potential for runaway reactions in spent nuclear fuel processing. Model features include user-defined facility room, flow path geometry, and heat conductors, user-defined non-ideal vapor and aerosol species, pressure- and density-driven gas flows, aerosol transport and deposition, and structure to accommodate facility-specific source terms. Example applications are presented here

Investigation of high flux test module for the international fusion materials irradiation facilities (IFMIF)

International Nuclear Information System (INIS)

Miyashita, Makoto; Sugimoto, Masayoshi; Yutani, Toshiaki

2007-03-01

This report describes investigation on structure of a high neutron flux test module (HFTM) for the International Fusion Materials Irradiation Facilities (IFMIF). The HFTM is aimed for neutron irradiation of a specimen in a high neutron flux domain of the test cell for irradiation ground of IFMIF. We investigated the overall structure of the HFTM that was able to include specimens in a rig and thermocouple arrangement, an interface of control signal and support structure. Moreover, pressure and the amount of the bend in the module vessel (a rectangular section pressure vessel) were calculated. The module vessel did a rectangular section from limitation of a high neutron flux domain. Also, we investigated damage of thermocouples under neutron irradiation, which was a temperature sensor of irradiation materials temperature control demanded high precision. Based on these results, drawings on the HTFM structure. (author)

Minimum dose method for walking-path planning of nuclear facilities

International Nuclear Information System (INIS)

Liu, Yong-kuo; Li, Meng-kun; Xie, Chun-li; Peng, Min-jun; Wang, Shuang-yu; Chao, Nan; Liu, Zhong-kun

2015-01-01

Highlights: • For radiation environment, the environment model is proposed. • For the least dose walking path problem, a path-planning method is designed. • The path-planning virtual–real mixed simulation program is developed. • The program can plan walking path and simulate. - Abstract: A minimum dose method based on staff walking road network model was proposed for the walking-path planning in nuclear facilities. A virtual–reality simulation program was developed using C# programming language and Direct X engine. The simulation program was used in simulations dealing with virtual nuclear facilities. Simulation results indicated that the walking-path planning method was effective in providing safety for people walking in nuclear facilities

The cascad spent fuel dry storage facility

International Nuclear Information System (INIS)

Guay, P.; Bonnet, C.

1991-01-01

France has a wide variety of experimental spent fuels different from LWR spent fuel discharged from commercial reactors. Reprocessing such fuels would thus require the development and construction of special facilities. The French Atomic Energy Commission (CEA) has consequently opted for long-term interim storage of these spent fuels over a period of 50 years. Comparative studies of different storage concepts have been conducted on the basis of safety (mainly containment barriers and cooling), economic, modular design and operating flexibility criteria. These studies have shown that dry storage in a concrete vault cooled by natural convection is the best solution. A research and development program including theoretical investigations and mock-up tests confirmed the feasibility of cooling by natural convection and the validity of design rules applied for fuel storage. A facility called CASCAD was built at the CEA's Cadarache Nuclear Research Center, where it has been operational since mid-1990. This paper describes the CASCAD facility and indicates how its concept can be applied to storage of LWR fuel assemblies

GIF++: A new CERN Irradiation Facility to test large-area particle detectors for the High-Luminosity LHC program

CERN Document Server

Guida, Roberto

2016-01-01

The high-luminosity LHC (HL-LHC) upgrade is setting a new challenge for particle detector technologies. The increase in luminosity will produce a higher particle background with respect to present conditions. To study performance and stability of detectors at LHC and future HL-LHC upgrades, a new dedicated facility has been built at CERN: the new Gamma Irradiation Facility (GIF++). The GIF++ is a unique place where high energy charged particle beams (mainly muons) are combined with gammas from a 14 TBq 137Cesium source which simulates the background radiation expected at the LHC experiments. Several centralized services and infrastructures are made available to the LHC detector community to facilitate the different R&D; programs.

Type B investigation report of curium-244 exposure at the ORNL TRU Facility, January 15, 1986

International Nuclear Information System (INIS)

Love, G.L.; Butler, H.M.; Duncan, D.T.; Oakes, T.W.

1986-04-01

This Type B Investigative Report provides an evaluation of relevant events and activities that led to, were a part of, or resulted from the release of curium-244 in the Building 7920 facility at ORNL in January 1986. Impacts have been evaluated with respect to employee exposures and the costs and loss of productivity resulting from increased bioassay analyses and activities of investigative committees. Management systems evaluated include (1) training of employees performing lab analyses, (2) adherence to procedures, and (3) response to unusual circumstances

Safety test facilities - status, needs, future directions

International Nuclear Information System (INIS)

Heusener, G.; Cogne, F.

1979-08-01

A survey is given of the in-pile programs which are presently or in the near future being performed in the DeBeNe-area and in France. Only those in-pile programs are considered which are dealing with severe accidents that might lead to disruption of major parts of the core. By comparing the needs with the goals of the present programs points are identified which are not sufficiently well covered up till now. The future procedure is described: the existing facilities will be used to the largest possible extent. Whenever it is necessary, upgrading and improvement will be foreseen. Studies of a Test Facility allowing the transient testing of large pin bundles should be continued. The construction of such a facility in Europe in the near future however seems premature

Facility approach to tokamak operation

International Nuclear Information System (INIS)

Edmonds, P.H.; Gabbard, W.A.

1981-01-01

In anticipation of the appearance of more advanced tokamaks and other fusion relevant experiments, program has been established at ORNL to systemically identify the requirements of an effective machine operations group. This program is presently applied to the ISX-B experiment. With its continuing development, it is expected to provide major support in the identification of potential problem areas and to assist in the generation of the necessary procedures for forthcoming devices. The present and future generations of large plasma devices will function as facilities, operated by an operations group as service to the plasma physicists and diagnosticians. The purpose of the program discussed here is to develop and to encourage an orderly transition to the facility-like style of operation

Measurement control program at model facility