WorldWideScience
1

The mixed waste management facility: Cost-benefit for the Mixed Waste Management Facility at Lawrence Livermore National Laboratory  

International Nuclear Information System (INIS)

The Mixed Waste Management Facility, or MWMF, has been proposed as a national testbed facility for the demonstration and evaluation of technologies that are alternatives to incineration for the treatment of mixed low-level waste. The facility design will enable evaluation of technologies at pilot scale, including all aspects of the processes, from receiving and feed preparation to the preparation of final forms for disposal. The MWMF will reduce the risk of deploying such technologies by addressing the following: (1) Engineering development and scale-up. (2) Process integration and activation of the treatment systems. (3) Permitting and stakeholder issues. In light of the severe financial constraints imposed on the DOE and federal programs, DOE/HQ requested a study to assess the cost benefit for the MWMF given other potential alternatives to meet waste treatment ...

2005-10-01

2

Mixed Waste Management Facility (MWMF) groundwater monitoring report, second quarter 1992  

Energy Technology Data Exchange (ETDEWEB)

During second quarter 1992, tritium, trichloroethylene, tetrachloroethylene, chloroethene, antimony, 1,1-dichloroethylene, lead, nonvolatile beta, radium-228, thorium-228, or total alpha-emitting radium (radium-226 and radium-228) exceeded the US Environmental Protection Agency Primary Drinking Water Standards (PDWS) in groundwater samples from monitoring wells at the Mixed Waste Management Facility (MWMF) and adjacent facilities. Tritium and trichloroethylene were the most widespread constituents; 55 (48%) of the 115 monitored wells contained elevated tritium activities, and 23 (20%) wells exhibited elevated trichloroethylene concentrations. Sixty-three downgradient wells screened in Aquifer Zone IIB2 (Water Table), Aquifer Zone IIB[sub 2] (Barnwell/McBean), and Aquifer Unit IIA (Congaree) contained concentrations of tritium, trichloroethylene, tetrachloroethylene, chloroethene, antimony, 1,1-dichloroethylene, lead, ...

1992-09-01

3

Interim safety basis for fuel supply shutdown facility  

Energy Technology Data Exchange (ETDEWEB)

This ISB in conjunction with the new TSRs, will provide the required basis for interim operation or restrictions on interim operations and administrative controls for the Facility until a SAR is prepared in accordance with the new requirements. It is concluded that the risk associated with the current operational mode of the Facility, uranium closure, clean up, and transition activities required for permanent closure, are within Risk Acceptance Guidelines. The Facility is classified as a Moderate Hazard Facility because of the potential for an unmitigated fire associated with the uranium storage buildings.

1995-05-23

4

Hanford facility dangerous waste permit application, general information portion  

Energy Technology Data Exchange (ETDEWEB)

The `Hanford Facility Dangerous Waste Permit Application` is considered to be a single application organized into a General Information Portion (this document, DOE/RL-91-28) and a Unit- Specific Portion. The scope of the General Information Portion includes information that could be used to discuss operating units, units undergoing closure, or units being dispositioned through other options. Documentation included in the General Information Portion is broader in nature and could be used by multiple treatment, storage, and/or disposal units. A checklist indicating where information is contained in the General Information Portion, in relation to the Washington State Department of Ecology guidance documentation, is located in the Contents Section. The intent of the General Information Portion is: (1) to provide an overview of the Hanford Facility; and (2) to assist in streamlining efforts associated with treatment, storage, ...

1996-07-29

5

Interim Safety Basis for Fuel Supply Shutdown Facility  

Energy Technology Data Exchange (ETDEWEB)

This ISB, in conjunction with the IOSR, provides the required basis for interim operation or restrictions on interim operations and administrative controls for the facility until a SAR is prepared in accordance with the new requirements or the facility is shut down. It is concluded that the risks associated with tha current and anticipated mode of the facility, uranium disposition, clean up, and transition activities required for permanent closure, are within risk guidelines.

2000-09-07

6

Closure of Off-Site Telnet  

CERN Document Server

Closure of Off-Site Telnet

2002-01-01

7

Streamlined Approach for Environmental Restoration (SAFER) Plan for Corrective Action Unit 118: Area 27 Super Kukla Facility, Nevada Test Site, Nevada, Rev. No.: 1  

Energy Technology Data Exchange (ETDEWEB)

This Streamlined Approach for Environmental Restoration (SAFER) plan addresses closure for Corrective Action Unit (CAU) 118, Area 27 Super Kukla Facility, identified in the ''Federal Facility Agreement and Consent Order''. Corrective Action Unit 118 consists of one Corrective Action Site (CAS), 27-41-01, located in Area 27 of the Nevada Test Site. Corrective Action Site 27-41-01 consists of the following four structures: (1) Building 5400A, Reactor High Bay; (2) Building 5400, Reactor Building and access tunnel; (3) Building 5410, Mechanical Building; and (4) Wooden Shed, a.k.a. ''Brock House''. This plan provides the methodology for field activities needed to gather the necessary information for closing the CAS. There is sufficient information and process knowledge from historical documentation and site confirmation data collected in 2005 and 2006 to ...

2006-09-01

8

Closure Report for Corrective Action Unit 543: Liquid Disposal Units, Nevada Test Site, Nevada  

Energy Technology Data Exchange (ETDEWEB)

This Closure Report (CR) documents closure activities for Corrective Action Unit (CAU) 543, Liquid Disposal Units, according to the Federal Facility Agreement and Consent Order (FFACO, 1996) and the Corrective Action Plan (CAP) for CAU 543 (U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office [NNSA/NSO], 2007). CAU 543 is located at the Nevada Test Site (NTS), Nevada (Figure 1), and consists of the following seven Corrective Action Sites (CASs): CAS 06-07-01, Decon Pad; CAS 15-01-03, Aboveground Storage Tank; CAS 15-04-01, Septic Tank; CAS 15-05-01, Leachfield; CAS 15-08-01, Liquid Manure Tank; CAS 15-23-01, Underground Radioactive Material Area; CAS 15-23-03, Contaminated Sump, Piping; and CAS 06-07-01 is located at the Decontamination Facility in Area 6, adjacent to Yucca Lake. The remaining CASs are located at the former U.S. Environmental Protection Agency (EPA) ...

2008-01-01

9

A study on the design method of multi tunnels in geological disposal facility  

International Nuclear Information System (INIS)

In the geological disposal facility of the high-level radioactive waste, a group of galleries is designed in parallel at the depth of more than 300 m below surface. This is an unprecedented structure in the field of conventional engineering, and it is necessary to take this characteristic into consideration in the design of the galleries. In the geological disposal facility, as well as ensuring the dynamic stability of the gallery during construction and operational periods, it is necessary to evaluate the EDZ adequately for long-term stability after the closure. In this study, analysis of the 'multi tunnels model' which represents the whole gallery group was performed and the results about the outbreak behavior of EDZ were summarized. (author)

2008-01-01

10

CLOSURE OF THE FAST FLUX TEST FACILITY (FFTF) HISTORY & STATUS & FUTURE PLANS  

Energy Technology Data Exchange (ETDEWEB)

In 1993, the US Department of Energy (DOE) decided to shut down the Fast Flux Test Facility (FFTF) due to lack of national missions that justified the annual operating budget of approximately $88M/year. The initial vision was to ''deactive'' the facility to an industrially and radiologically safe condition to allow long-term, minimal surveillance storage until approximately 2045. This approach would minimize near term cash flow and allow the radioactive decay of activated components. The final decontamination and decommissioning (D and D) would then be performed using then-current methodology in a safe and efficient manner. the philosophy has now changed to close coupling the initial deactivation with final D and D. This paper presents the status of the facility and focuses on the future challenge of sodium removal.

2006-02-24

11

Summary of the Waste Management Programs at uranium recovery facilities as they relate to the 40 CFR Part 192 standards  

International Nuclear Information System (INIS)

This study evaluates the degree to which surface impoundments at licensed facilities comply with significant changes in NRC requirements initiated by enactment of EPA's final environmental standards for uranium recovery facilities (40 CFR Part 192). Impoundment liner requirements, ground-water protection standards, ground-water monitoring and corrective action programs, and site closure standards are the most significant regulatory modifications. The compliance status of 30 conventional mills and 31 in-situ mines is determined from a review of Nuclear Regulatory Commission and agreement state docket files through November, 1983. Results of this review show that a majority of conventional uranium mill tailings management systems are deficient with respect to liner requirements for new impoundments or proposed expansions to existing impoundments, as well as with respect to some aspects of ground-water monitoring and ...

12

FULL CLOSURE MOTOR FOR DRIVING VEHICLE  

J-STORE (Japan)

Full Text Available

2007-11-02

13

Challenges for Lithuania: Ignalina NPP Early Closure  

International Nuclear Information System (INIS)

As a condition of accession into the European Union (EU), Lithuania is committed to the closure and decommissioning of Ignalina NPP comprising two RBMK-1500 reactor units (Fig. 1). It was agreed in a special protocol to the Accession Treaty that, in return for adequate EU financial assistance, Unit 1 would be closed before 2005 and Unit 2 by the end of 2009. The first unit was duly shut down on December 31, 2004. Lithuania, which has borders with Russia (Kaliningrad territory), Poland, Latvia and Belarus, spent fifty years as part of the Soviet Union and was deeply integrated into its economy and electrical infrastructure. At the break-up of the USSR, Lithuania inherited electricity generating capacity designed to supply the north-west region including ownership of Ignalina NPP located in the north-east of the country. Ignalina NPP Unit 1 was commissioned in 1983, Unit 2 in 1987; the planned lifespan of each unit was 30 years. Construction of a third unit was ...

2008-01-01

14

Resource Conservation and Recovery Act corrective measures study: Area 6 decontamination pond facility, corrective action unit no. 92  

Energy Technology Data Exchange (ETDEWEB)

Corrective Action Unit (CAU) No. 92, the Area 6 Decontamination Pond Facility (DPF), is an historic disposal unit located at the Nevada Test Site (NTS) in Nye County, Nevada (Figures 1 - 1, 1-2, and 1-3). The NTS is operated by the U.S. Department of Energy, Nevada Operations Office (DOE/NV), which has been required by the Nevada Division of Environmental Protection (NDEP) to characterize the DPF under the requirements of the Resource Conservation and Recovery Act (RCRA) Part A Permit (NDEP, 1995) for the NTS and Title 40 Code of Federal Regulations (CFR) Part 265 (1996c). The DPF is prioritized in the Federal Facility Agreement and Consent Order (FFACO, 1996) but is governed by the permit. The DPF was characterized through sampling events in 1994, 1996, and 1997. The results of these sampling events are contained in the Final Resource Conservation and Recovery Act Industrial Site Environmental Restoration Site Characterization Report, Area 6 ...

1997-10-01

15

Echocardiographic assessment and percutaneous closure of multiple atrial septal defects  

UK PubMed Central (United Kingdom)

Atrial septal defect closure is now routinely performed using a percutaneous approach under echocardiographic guidance. Centrally located, secundum defects are ideal for device closure but there is...Full Text Available

16

Effect of Stress and Strain Path on Cavity Closure During Hot ...  

Science.gov (United States)

... CLOSURE DURING HOT WORKING OF AN ALPHA/BETA TITANIUM ALLOY (PREPRINT) ... HOT WORKING OF AN ALPHA/BETA TITANIUM ALLOY ...

2007-07-01

17

ESTABLISHING FINAL END STATE FOR A RETIRED NUCLEAR WEAPONS PRODUCTION REACTOR; COLLABORATION BETWEEN STAKEHOLDERS, REGULATORS, AND THE FEDERAL GOVERNMENT - 11052  

Science.gov (United States)

The Savannah River Site (SRS) is a 310-square-mile United States Department of Energy nuclear facility located along the Savannah River (SRS) near Aiken, South Carolina. Nuclear weapons material production began in the early 1950s, utilizing five production reactors. In the early 1990s all SRS production reactor operations were terminated. The first reactor closure end state declaration was recently institutionalized in a Comprehensive Environmental Response and Compensation and Liability Act (CERCLA) Early Action Record of Decision. The decision for the final closure of the 318,000 square foot 105-P Reactor was determined to be in situ decommissioning (ISD). ISD is an acceptable and cost effective alternative to off-site disposal for the reactor building, which will allow for consolidation of remedial action wastes generated from other cleanup activities within the P Area. ISD is considered protective by the regulators, U. ...

2010-11-17

20

Newly developed control and stop valves  

International Nuclear Information System (INIS)

... bwr type reactors closures fluidic control devices operation performance pwr

24

Development of the Decontamination Approach for the West Valley Demonstration Project Decontamination Project Plan  

Energy Technology Data Exchange (ETDEWEB)

This paper details the development of a decontamination approach for the West Valley Demonstration Project (WVDP), Decontamination Project Plan (Plan). The WVDP is operated by West Valley Nuclear Services Company (WVNSCO), a subsidiary of Westinghouse Government and Environmental Services, and its parent companies Washington Group International and British Nuclear Fuels Limited (BNFL). The WVDP is a waste management effort being conducted by the United States Department of Energy (DOE) at the site of the only commercial nuclear fuel reprocessing facility to have operated in the United States. This facility is part of the Western New York Nuclear Service Center (WNYNSC), which is owned by the New York State Energy Research and Development Authority (NYSERDA). As authorized by Congress in 1980 through the West Valley Demonstration Project Act (WVDP Act, Public Law 96-368), the DOE's primary mission at the WVDP is to solidify high-level ...

2002-02-25

25

Effects of morpho dynamics in shallow waters over pipeline facilities; Efeitos da morfodinamica em aguas rasas sobre instalacoes de dutos  

Energy Technology Data Exchange (ETDEWEB)

The success in developing of the oil industry operating in offshore-onshore terminals, connected by pipelines with the facilities of the coastal zone, can be attributed partially to the beach morpho dynamic monitoring. This study represents a solution to the concerns of the technical operations in coastal zones because it minimizes the impact of the petroleum production and it assures the environmental protection associated to the risks of the pipelines breaking. This impact type results mainly of the vertical and horizontal displacements of the beach, from the coastal dunes to the shore face. The mobility of the profile is associated to the magnitude of the sedimentary processes, which reproduce naturally or not, in scale of time that can vary among few days, years or decades. For the monitoring and interpretation of the beach profile mobility the following methods are recommended: calculation of the closure depth with base in the wave data; ...

2003-07-01

26

Conventional Linear versus Purse-string Skin Closure after Loop Ileostomy Reversal: Comparison of Wound Infection Rates and Operative Outcomes  

UK PubMed Central (United Kingdom)

PurposeWound infection after an ileostomy reversal is a common problem. To reduce wound-related complications, purse-string skin closure was introduced as an alternative to conventional...Full Text Available

2011-04-01

27

Regulatory view of the close-out of the uranium ore mine Zirovski Vrh  

International Nuclear Information System (INIS)

The production of the uranium mine Zirovski Vrh ceased in 1990. The main remaining problem of the remadiation are mine and mill tailings. The uranium mine Zirovski Vrh has one mill tailings site Borst and one waste pile Jazbec. According to the Act on protection against ionising radiation and nuclear safety which was adopted by the Parliament in 2002, they are classified as radiation facilities. Slovenian Nuclear Safety Administration (SNSA) is authorised for issuing a mandatory consent to mining work. The SNSA prepared the initial proposal of content of the safety report for the mine waste pile Jazbec. In 2005, according to the detailed content of this document, the public company Zirovski Vrh Ltd prepared the safety report which was examined by an authorised expert for radiation and nuclear safety. After a careful revision of the safety evaluation report, the consensus for mining work shall be issued by the SNSA. After finishing the mining works the SNSA shall ...

2005-09-05

28

Nuclear waste treatment program: Annual report for FY 1987  

Energy Technology Data Exchange (ETDEWEB)

Two of the US Department of Energy's (DOE) nuclear waste management-related goals are to ensure that waste management is not an obstacle to the further development of light-water reactors and the closure of the nuclear fuel cycle and to fulfill its institutional responsibility for providing safe storage and disposal of existing and future nuclear wastes. As part of its approach to achieving these goals, the Office of Remedial Action and Waste Technology of DOE established what is now called the Nuclear Waste Treatment Program (NWTP) at the Pacific Northwest Laboratory during the second half of FY 1982. To support DOE's attainment of its goals, the NWTP is to provide technology necessary for the design and operation of nuclear waste treatment facilities by commercial enterprises as part of a licensed waste management system and problem-specific treatment approaches, waste form and treatment process adaptations, equipment ...

1988-09-01

29

Fuzzy multi-objective decision making on a low and intermediate level waste repository safety assessment  

Energy Technology Data Exchange (ETDEWEB)

Low and intermediate waste disposal facilities safety assessment is comprised of several steps from site selection , construction and operation to post-closure performance assessment. This is a multidisciplinary and complex task , and can not be analyzed by one expert only. This high complexity can lead to ambiguity and vagueness in information and consequently in the decision making process. In order to make the decision process clear and objective, there is the need to provide the decision makers with a clear and comprehensive picture of the whole process and, at the same time, simple and easily understandable by the public. This paper suggests the development of an inference system based on fuzzy decision making methodology. Fuzzy logic tools are specially suited to deal with ambiguous data by using language expressions. This process would be capable of integrating knowledge from various fields of environmental sciences. It has an advantage ...

2002-07-01

30

On the fatigue threshold behaviour of two ferrite-pearlite microalloyed steels  

Energy Technology Data Exchange (ETDEWEB)

Long crack fatigue threshold ({delta} K{sub th}) and crack closure behaviour of two thermomechanically processed microalloyed (MA) ferrite-pearlite steels are reported. {delta} K{sub th} and crack closure were measured using a dynamic compliance measurement technique. Crack closure was observed at low load ratios (R < 0.5) and the fatigue thresholds decreased with increasing load ratio. In both steels, the closure-free intrinsic threshold ({delta} K{sub eff} {sub th}) was found to be independent of the load ratio. (orig.)

2000-07-01

31

The closure operator in a multivalued logic based on functional equations  

British Library Electronic Table of Contents (United Kingdom)

An operator of FE-closure is introduced on the set of functions of a multivalued logic based on the systems of functional equations. It is proved that, for every k ? 2, the FE-closure operator generates a finite classification on the set P k of functions of k-valued logic. The least class in this classification is shown to be the class H k of all homogeneous functions. Also a series of corollaries are obtained concerning the finite FE-generating sets in the FE-closed classes.

2011-01-01

32

Description of work vadose drilling at the 1301-N and 1325-N facilities, 100-NR-1 operable unit  

Energy Technology Data Exchange (ETDEWEB)

This description of work (DOW) details the field activities associated with the sampling of the vadose zone soils beneath the 1301-N and 1325-N cribs and trenches and will serve as a field guide for those performing the work. These activities are undertaken pursuant to the Hanford Federal Facility Agreement and Consent Order (Ecology et al., 1994a) Milestone M-16-94-01H-Tl and the June 30, 1994 Milestone Change Request M-16-94-02 (Ecology et al., 1994b). Three vadose zone borings, 1301-N-1, 1301-N-2, and 1325-N-1, will be constructed to investigate the vertical and horizontal distribution of radionuclide contamination in sediments beneath the cribs and trenches. The boreholes are also intended to intersect subsurface areas that may have been contaminated by dangerous wastes, i.e., metals, in effluent disposed during past operation of the facilities. This limited field investigation will provide data for the evaluation of remedial alternatives. ...

1994-08-01

33

Chalon/Saint-Marcel manufacturing plant; L'usine de Chalon/Saint-Marcel  

Energy Technology Data Exchange (ETDEWEB)

AREVA is the world leader in the design and construction of nuclear power plants, the manufacture of heavy components, and the supply of nuclear fuel and nuclear services such as maintenance and inspection. The Equipment Division provides the widest range of nuclear components and equipment, manufactured at its two facilities in Jeumont, northern France, and St. Marcel, in Burgundy. The St. Marcel plant, set on 35 ha (87.5 acres) near Chalon-sur-Saone, was established in 1973 in a region with a long history of specialized metalworking and mechanical activities to meet the demand for non-military nuclear requirements in France. The site offers two advantages: - excellent facilities for loading and transporting heavy components on the Saone river, - it's proximity to other group sites. Since its completion in 1975, the Chalon/St. Marcel facility has manufactured all the heavy components for French pressurized water ...

2008-07-01

34

Amchitka Mud Pit Sites 2006 Post-Closure Monitoring and Inspection Report, Amchitka Island, Alaska, Rev. No.: 0  

Energy Technology Data Exchange (ETDEWEB)

In 2001, the U.S. Department of Energy (DOE), National Nuclear Security Administration (NNSA/NSO) remediated six areas associated with Amchitka mud pit release sites located on Amchitka Island, Alaska. This included the construction of seven closure caps. To ensure the integrity and effectiveness of remedial action, the mud pit sites are to be inspected every five years as part of DOE's long-term monitoring and surveillance program. In August of 2006, the closure caps were inspected in accordance with the ''Post-Closure Monitoring and Inspection Plan for Amchitka Island Mud Pit Release Sites'' (Rev. 0, November 2005). This post-closure monitoring report provides the 2006 cap inspection results.

2006-09-01

35

Corrective Action Decision Document/Closure Report for Corrective Action Unit 409: Other Waste Sites, Tonopah Test Range, Nevada (Rev. No.: 0, June 2001)  

Energy Technology Data Exchange (ETDEWEB)

This Corrective Action Decision Document/Closure Report (CADD/CR) has been prepared for Corrective Action Unit (CAU) 409: Other Waste Sites, Tonopah Test Range (TTR), Nevada, in accordance with the Federal Facility Agreement and Consent Order. Located near Area 3 on the TTR approximately 140 miles northwest of Las Vegas, Nevada, CAU 409 is comprised of three Corrective Action Sites (CASs): CAS RG-24-001-RGCR, Battery Dump Site; CAS TA-53-001-TAB2, Septic Sludge Disposal Pit (referred to as Septic Sludge Disposal Pit No.1); CAS TA-53-002-TAB2, Septic Sludge Disposal Pit (referred to as Septic Sludge Disposal Pit No.2). This CADD/CR identifies and rationalizes the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Operations Office's (NNSA/NV's) recommendation that no corrective action is deemed necessary for CAU 409. The CADD/CR have been combined into one report based on sample data collected ...

2001-06-12

36

Performance Assessment Monitoring Plan for the Hanford Site Low-Level Burial Grounds  

Energy Technology Data Exchange (ETDEWEB)

The U.S. Department of Energy Order 435.1, Radioactive Waste Management, requires a disposal authorization statement authorizing operation (or continued operation) for low-level waste disposal facilities. In fulfillment of these requirements, a disposal authorization statement was issued on October 25, 1999, authorizing the Hanford Site to transfer, receive, possess, and dispose of low-level radioactive waste at the 200 East Area burial grounds and the 200 West Area burial grounds. One of the conditions is that monitoring plans for the 200 East Area and 200 West Area low-level burial grounds be written and approved by the Richland Operations Office. As a result of a record of decision for the Hanford Site Solid Waste Program and acceptance of the Hanford Site Solid Waste Environmental Impact Statement, the use of the low-level burial ground (LLBG) as a disposal facility for low-level and mixed low-level wastes has been restricted to lined ...

2006-03-30

37

The Waste Isolation Pilot Plant: A Success Story with International Cooperation  

Energy Technology Data Exchange (ETDEWEB)

The U.S. Department of Energy (DOE) Carlsbad Field Office (CBFO) administers and operates the Waste Isolation Pilot Plant (WIPP) site, which hosts a deep geologic repository for safe disposal of U.S. defense-related TRU waste and is located 42 kilometers (km) east of Carlsbad, New Mexico. CBFO also manages the National Transuranic Waste Program (NTP), which oversees TRU waste management from generation to disposal. The WIPP began receiving waste in March 1999. In some areas of broad international interest, the CBFO has developed a leading expertise through its 25-year WIPP repository and TRU waste characterization activities. In addition to participating in relevant and beneficial experiments, the CBFO will provide the international community convenient access to this information by sponsoring and hosting symposia and workshops on relevant topics and by participation in international waste management organizations and topical meetings. In recognition of the successes at WIPP, the Inter ...

2002-02-26

38

The Two-Column Aerosol Project (TCAP) Science Plan  

Energy Technology Data Exchange (ETDEWEB)

The Two-Column Aerosol Project (TCAP) field campaign will provide a detailed set of observations with which to (1) perform radiative and cloud condensation nuclei (CCN) closure studies, (2) evaluate a new retrieval algorithm for aerosol optical depth (AOD) in the presence of clouds using passive remote sensing, (3) extend a previously developed technique to investigate aerosol indirect effects, and (4) evaluate the performance of a detailed regional-scale model and a more parameterized global-scale model in simulating particle activation and AOD associated with the aging of anthropogenic aerosols. To meet these science objectives, the Atmospheric Radiation Measurement (ARM) Climate Research Facility will deploy the ARM Mobile Facility (AMF) and the Mobile Aerosol Observing System (MAOS) on Cape Cod, Massachusetts, for a 12-month period starting in the summer of 2012 in order to quantify aerosol properties, radiation, and ...

2011-07-27

39

tiAtiA ,', - NASA Technical Report Server (NTRS)  

Science.gov (United States)

the nozzle ring, the collector cup, and the impeller fuel-distribution ... sity of the vaned collector cup and the fuel-transfer passages ..... closure ...

40

Military Base Closures and Affected Defense Department Civil ...  

Science.gov (United States)

... System (CSRS) and the Federal Employees Retirement System (FERS). ... retirement, thrift savings plan, annual and sick leave, severance pay and ...

2006-03-07

41

Laser Surface Mapping of the Failed FB-Line Bagless Canister Closure Weld  

Energy Technology Data Exchange (ETDEWEB)

This report details the laser surface mapping activity as described in technical tasks and QA plan 22751-TTQAP-LM.

2000-06-27

42

EUROPEAN SPACE AGENCY Extension of the SOHO Mission  

Science.gov (United States)

closure of the BISON network, GOLF and VIRGO will remain the only instruments ...... Faraday Cup solar wind instrument as described in Ipavich et al (1998). ...

43

Transesophageal echo to help percutaneous closure of ventricular septal defect post acute myocardial infarction  

British Library Electronic Table of Contents (United Kingdom)

Ventricular septal defect after acute myocardial infarction (AMI) is a complication associated with poor outcome in the absence of intervention. We report a case of successful TEE guided transcatheter closure of a post myocardial infarction (MI) ventricular septal defect (VSD) with an Amplatzer occluder in a 79 years old male with cardiogenic shock.

2011-01-01

44

The Risk of Paradoxical Embolism (RoPE) Study: Developing risk models for application to ongoing randomized trials of percutaneous patent foramen ovale closure for cryptogenic stroke  

UK PubMed Central (United Kingdom)

BackgroundDespite the diffusion into practice of percutaneous closure of a patent foramen ovale (PFO) in patients with cryptogenic stroke (CS), the benefits have not been demonstrated,...Full Text Available

45

Effects of Temperature on H+ Secretion and Uptake by Excised Flexor Cells during Dark-Induced Closure of Samanea Leaflets 1  

UK PubMed Central (United Kingdom)

Previous studies reveal that dark-induced closure of Samanea leaflets is accompanied by H+ secretion from flexor motor cells. We now report that flexor tissue excised in...Full Text Available

1987-11-01

46

F-Area Seepage Basins groundwater monitoring report -- third and fourth quarters 1993. Volume 1  

Energy Technology Data Exchange (ETDEWEB)

During the second half of 1993, the groundwater at the F-Area Seepage Basins (FASB) was monitored in compliance with Module 3, Section C, of South Carolina Hazardous Waste Permit SC1-890-008-989, effective November 2, 1992. The monitoring well network is composed of 87 FSB wells screened in the three hydrostratigraphic units that make up the uppermost aquifer beneath the FASB. A detailed description of the uppermost aquifer is included in the Resource Conservation and Recovery Act Part B post-closure care permit application for the F-Area Hazardous Waste Management Facility submitted to the South Carolina Department of Health and Environmental Control (SCDHEC) in December 1990. Beginning in the first quarter of 1993, the standard for comparison became the SCDHEC Groundwater Protection Standard (GWPS) specified in the approved F-Area Seepage Basins Part B permit. Currently and historically, gross alpha, nitrate, nonvolatile beta, and tritium are ...

1994-03-01

47

Ecological risk assessments for protected migratory birds and marine species at Midway Atoll  

Energy Technology Data Exchange (ETDEWEB)

In June 1997, the US Navy plans to close its Naval Air Facility on Sand Island and transfer the atoll to the US Fish and Wildlife Service for use as a National Wildlife Refuge. Midway provides breeding and feeding habitat for migratory seabirds, terrestrial and marine mammals, sea turtles and other reptiles, and a variety of reef fishes and invertebrates. As part of the base closure and transfer process, 36 sites of potential environmental concern were identified on Sand and Eastern islands. These sites include landfills and uncontrolled disposal areas, hazardous materials storage areas, abandoned transformers, sewer outfalls, and other potential hazardous waste sites. Potential contaminants include pesticides, PAHs, PCBs, and heavy metals. A screening ecological risk assessment was performed at each site with a goal of determining whether contaminants could pose any current or future risks to protected migratory bird or marine mammal wildlife ...

1995-12-31

48

Development of a system model for the postclosure assessment of a concept for geological disposal of Canada`s nuclear fuel waste  

Energy Technology Data Exchange (ETDEWEB)

Atomic Energy of Canada has recently submitted for regulatory and public review an Environmental Impact Statement (EIS) on a concept for disposal of Canada`s nuclear fuel waste. The EIS is supported by nine primary references that summarize major aspects of the concept, including a postclosure environmental and safety assessment. The scope of the postclosure assessment is largely determined by the requirements of the Atomic Energy Control Board (AECB) of Canada. These requirements include a quantitative estimate of the annual effective dose equivalent to an individual in the most exposed group of people (the critical group) for 10,000 years following closure of the disposal facility, and a radiological risk criterion with an associated dose rate limit of 0.05 mSv/a. Over this long time frame, a quantitative assessment cannot be based on actual observations, and thus we use scientific arguments and simulations with mathematical models to infer ...

1995-12-01

49

Combined bony closure of oroantral fistula and sinus lift with mandibular bone grafts for subsequent dental implant placement  

British Library Electronic Table of Contents (United Kingdom)

Sinus lifting and reconstruction of localized alveolar defects are often required after closure of a large oroantral fistula (OAF) to allow for subsequent implant installation. This study describes a combined surgical technique that involves sinus lifting, bony closure, and reconstruction of the alveolar defect at the site of an OAF. The sinus membrane was reconstructed as a continuous layer by combining the residual sinus membrane with a rotated part of oral mucosa around the OAF. Autogenous bone from the chin and/or ramus was grafted into the prepared sinus space and alveolar defect, and the graft was covered by a buccal advancement flap. This technique was used to treat 8 patients who had large OAFs in the posterior maxillary region. The treatment was successful in all cases, and the te...

2011-01-01

50

Successful Treatment of Anterior Tracheal Necrosis after Total Thyroidectomy Using Vacuum-Assisted Closure Therapy  

UK PubMed Central (United Kingdom)

Total thyroidectomy involving the adjacent structures of the trachea can cause tracheal damage such as early tracheal necrosis. The authors describe the first case of anterior tracheal necrosis following...Full Text Available

2012-01-01

51

Relationship of Xylem Embolism to Xylem Pressure Potential, Stomatal Closure, and Shoot Morphology in the Palm Rhapis excelsa1  

UK PubMed Central (United Kingdom)

Xylem failure via gas embolism (cavitation) induced by water stress was investigated in the palm Rhapis excelsa (Thumb.) Henry. Xylem embolism in excised stems and petioles was detected...Full Text Available

1986-01-01

52

Prostaglandin-mediated closure of paracellular pathway and not restitution is the primary determinant of barrier recovery in acutely injured porcine ileum  

UK PubMed Central (United Kingdom)

SUMMARYSmall bowel epithelium is at the frontline of intestinal barrier function. Restitution is considered to be the major determinant of epithelial repair as function recovers...Full Text Available

2003-11-01

53

Over-the-scope clip closure of two chronic fistulas after gastric band penetration  

UK PubMed Central (United Kingdom)

Gastrointestinal perforations are conservatively managed at endoscopy by through-the-scope endoclips and covered self expandable stents, according to the size and tissue features of the perforation....Full Text Available

2010-04-07

54

On the internal perceptual structure of distinctive features: The [voice] contrast  

UK PubMed Central (United Kingdom)

Several fixed classification experiments test the hypothesis that F1, f0, and closure voicing covary between intervocalic stops contrasting...Full Text Available

2008-01-01

55

FFTF reactor assembly system technology  

Science.gov (United States)

An overview is presented of the FFTF reactor and plant together with descriptions of core components, core internals, core system, primary and secondary control rod system, reactor instrumentation, reactor vessel and closure head, and supporting test programs. (DG)

1975-11-13

56

FFTF reactor assembly system technology  

International Nuclear Information System (INIS)

An overview is presented of the FFTF reactor and plant together with descriptions of core components, core internals, core system, primary and secondary control rod system, reactor instrumentation, reactor vessel and closure head, and supporting test programs.

1976-03-13

57

Effect of the ASARCO smelter shutdown on the acidity of rainfall in the Puget sound area  

Science.gov (United States)

The influence of the sulfur dioxide emissions from a large copper smelter in Tacoma, Washington, USA, was studied by measuring the chemical composition of rainwater collected upwind and downwind of the source, before and after permanent closure of the smelter in 1985. Data analysis was based on a statistical model that accounted for variability associated with location of 25 sampling sites within three geographic regions, smelter operation, ten individual rain events observed over 2 years, and measurement uncertainty. After smelter closure, the upwind-downwind differences in mean hydrogen ion and excess sulfate ion concentrations within a 600 km/sup 2/ region extending to 25 km downwind of the source had decreased significantly compared to the pre-closure value. No significant decreases in mean ion concentrations were observed farther downwind in the Seattle, urban area. During five events sampled prior to smelter ...

1988-04-01

58

A late presenting congenital diaphragmatic hernia misdiagnosed as spontaneous pneumothorax  

UK PubMed Central (United Kingdom)

Congenital diaphragmatic hernia (CDH) is described as (1) failure of diaphragmatic closure at development, (2) presence of herniated abdominal contents into chest and (3) pulmonary hypoplasia. Usually,...Full Text Available

2010-09-01

59

{Beta} decay and isomeric properties of neutron-rich Ca and Sc isotopes.  

Energy Technology Data Exchange (ETDEWEB)

The isomeric and {beta}-decay properties of neutron-rich {sup 53-57}Sc and {sup 53,54}Ca nuclei near neutron number N = 32 are reported, and the low-energy level schemes of {sup 53,54,56}Sc and {sup 53-57}Ti are presented. The low-energy level structures of the {sub 21}Sc isotopes are discussed in terms of the coupling of the valence 1f{sub 7/2} proton to states in the corresponding {sub 20}Ca cores. Implications with respect to the robustness of the N = 32 subshell closure are discussed, as well as the repercussions for a possible N = 34 subshell closure.

2010-07-21

60

Two-proton excitations at the Z=38 and Z=40 sub-shell closures  

International Nuclear Information System (INIS)

The "8"6Kr("3He,n)"8"8Sr and "8"8Sr("3He,n)"9"0Zr reactions were studied to determine whether significant excited 0"+ strength was observed or whether these nuclei exhibited absence of excited state strength generally seen away from shell closures. Various properties of the levels are considered including angular distributions, spins, parities, interference, and enhancement. It is concluded that neither "8"8Sr nor "9"0Zr exhibit the strong proton pairing vibration expected for a closed proton shell nucleus.

1977-11-01

61

Persistence of the N=28 shell closure far from stability  

Science.gov (United States)

The masses of 16 neutron-rich nuclei in the mass range from 35 to 45 have been measured using a direct time of flight technique following the fragmentation of a {sup 48}Ca beam at 60 MeV/nucleon. The masses of {sup 35,36}Mg, {sup 38}Al, {sup 39,40}Si, {sup 42,43}P and {sup 43,44}S are reported for the first time. Preliminary analysis shows that the N=28 shell closure persists, even if weakened by the large neutron excess.

1998-12-21

62

Persistence of the N=28 shell closure far from stability  

International Nuclear Information System (INIS)

The masses of 16 neutron-rich nuclei in the mass range from 35 to 45 have been measured using a direct time of flight technique following the fragmentation of a "4"8Ca beam at 60 MeV/nucleon. The masses of "3"5","3"6Mg, "3"8Al, "3"9","4"0Si, "4"2","4"3P and "4"3","4"4S are reported for the first time. Preliminary analysis shows that the N=28 shell closure persists, even if weakened by the large neutron excess.

1998-12-21

63

? decay and isomeric properties of neutron-rich Ca and Sc isotopes  

International Nuclear Information System (INIS)

The isomeric and ?-decay properties of neutron-rich 53-57Sc and 53,54Ca nuclei near neutron number N=32 are reported, and the low-energy level schemes of 53,54,56Sc and 53-57Ti are presented. The low-energy level structures of the 21Sc isotopes are discussed in terms of the coupling of the valence 1f7/2 proton to states in the corresponding 20Ca cores. Implications with respect to the robustness of the N=32 subshell closure are discussed, as well as the repercussions for a possible N=34 subshell closure.

2010-07-01

64

Corrective Action Investigation Plan for Corrective Action Unit 409: Other Waste Sites, Tonopah Test Range, Nevada (Rev. 0)  

Energy Technology Data Exchange (ETDEWEB)

This Corrective Action Investigation Plan contains the U.S. Department of Energy, Nevada Operations Office's approach to collect the data necessary to evaluate corrective action alternatives appropriate for the closure of Corrective Action Unit (CAU) 409 under the Federal Facility Agreement and Consent Order. Corrective Action Unit 409 consists of three Corrective Action Sites (CASs): TA-53-001-TAB2, Septic Sludge Disposal Pit No.1; TA-53-002-TAB2, Septic Sludge Disposal Pit No.2; and RG-24-001-RGCR, Battery Dump Site. The Septic Sludge Disposal Pits are located near Bunker Two, close to Area 3, on the Tonopah Test Range. The Battery Dump Site is located at the abandoned Cactus Repeater Station on Cactus Peak. The Cactus Repeater Station was a remote, battery-powered, signal repeater station. The two Septic Sludge Disposal Pits were suspected to be used through the late 1980s as disposal sites for sludge from septic tanks located in ...

2000-10-05

65

University of Central Lancashire - Facilities  

Wastenet

...specialised laboratories for pharmaceutics, tissue culture and molecular biology Excellent Laboratory Facilities Tissue Culture Facilities Molecular Biology Laboratory ...

66

Decomissioning Strategies for Facilities Using Radioactive Material  

CERN Document Server

Decomissioning Strategies for Facilities Using Radioactive Material

2007-01-01

67

Effect of mean stress (stress ratio) and aging on fatigue-crack growth in a metastable beta titanium alloy, Ti-10V-2Fe-3Al  

International Nuclear Information System (INIS)

The effect of mean stress, or the stress ratio (R), on the fatigue-crack growth (FCG) behavior of #alpha#-aged and #omega#-aged microstructures of the beta titanium alloy Ti-10V-2Fe-3Al was investigated. While the mean stress had a negligible effect on the FCG behavior of the #alpha#-aged microstructure, a strong effect was observed in the #omega#-aged microstructure. In particular, the values of the threshold stress-intensity range (#DELTA#K_t_h) exhibited a strong dependence on R in the #omega#-aged microstructure, while this dependence was weak in the #alpha#-aged microstructure. These effects seem to arise primarily from fracture-surface roughness-induced crack closure. The crack closure levels for the #alpha#-aged microstructure were found to be very low compared to those for the #omega#-aged microstructure. Transmission electron microscopy and scanning electron microscopy studies of microstructures and fracture surfaces were performed to ...

2000-03-01

68

Shipping container response to three severe railway accident scenarios  

Energy Technology Data Exchange (ETDEWEB)

The probability of damage and the potential resulting hazards are analyzed for a representative rail shipping container for three severe rail accident scenarios. The scenarios are: (1) the rupture of closure bolts and resulting opening of closure lid due to a severe impact, (2) the puncture of container by an impacting rail-car coupler, and (3) the yielding of container due to side impact on a rigid uneven surface. The analysis results indicate that scenario 2 is a physically unreasonable event while the probabilities of a significant loss of containment in scenarios 1 and 3 are extremely small. Before assessing the potential risk for the last two scenarios, the uncertainties in predicting complex phenomena for rare, high- consequence hazards needs to be addressed using a rigorous methodology.

1998-04-01

69

Laparoscopic Orchiectomy and Subsequent Internal Ring Closure for Extra-abdominal Testicular Nubbin in Children  

British Library Electronic Table of Contents (United Kingdom)

Objectives To present our preliminary experience with laparoscopic groin exploration and subsequent laparoscopic orchiectomy and internal ring closure for testicular nubbin in children and discuss the usefulness of our new treatment strategy. The advantages of laparoscopic orchiopexy for intra-abdominal testis are the ability to start treatment as soon as a diagnosis has been made and to permit minimally invasive surgery. These advantages can apply to laparoscopic orchiectomy for a testicular nubbin. Methods A total of 6 boys with a testicular nubbin (age range 14-76 months, mean age 27.3 months) underwent laparoscopic orchiectomy at our institution from June 2007 to June 2008. We opened the posterior parietal peritoneum by incising the peritoneum lateral to the spermatic vessel, distal to...

2009-01-01

70

Goal-based waste management strategy to reduce persistence of contaminants in leachate at municipal solid waste landfills  

British Library Electronic Table of Contents (United Kingdom)

The required minimum 30-year post-closure care period for municipal solid waste (MSW) landfills can be shortened by reducing or eliminating of MSW components with long-terms effect in gas and leachate. The objectives of this study were to evaluate the relative persistence of landfill gas, leachate quantity, and selected leachate parameters using post-closure monitoring data from a case study landfill in south Florida. The relative persistence of selected decomposition byproducts in leachate were evaluated by both zero order and first order models based on monitoring data from the case study landfill. The analyses show that although gas and leachate production rates diminish very quickly, some contaminants remain in leachate as the decomposition process continues at a slower rate. For the c...

2011-01-01

71

Forward on the N=Z line with GASP  

Energy Technology Data Exchange (ETDEWEB)

The experimental study of the proton-rich nuclei close to the N=Z line is a constant challenge for nuclear spectroscopy, mainly due to the difficulty to produce them with the currently available beam/target combinations. Significant advances on this direction were obtained from experiments performed with the GASP array during the last two years: the yrast line of {sup 84}Mo was extended up to 10{sup +}, {sup 88}Ru observed for the first time, and the N=Z+1 line was mapped from {sup 81}Zr to {sup 95}Ag. These new results allow us to have a more complete image of the transition from the well-deformed shell closure at N,Z=40 to the spherical-shell closure at N,Z=50, and highlights some particular effects that can be observed only in the vicinity of the N=Z line. (orig.)

2004-04-01

72

Forward on the N=Z line with GASP  

International Nuclear Information System (INIS)

The experimental study of the proton-rich nuclei close to the N=Z line is a constant challenge for nuclear spectroscopy, mainly due to the difficulty to produce them with the currently available beam/target combinations. Significant advances on this direction were obtained from experiments performed with the GASP array during the last two years: the yrast line of "8"4Mo was extended up to 10"+, "8"8Ru observed for the first time, and the N=Z+1 line was mapped from "8"1Zr to "9"5Ag. These new results allow us to have a more complete image of the transition from the well-deformed shell closure at N,Z=40 to the spherical-shell closure at N,Z=50, and highlights some particular effects that can be observed only in the vicinity of the N=Z line. (orig.)

2004-04-01

73

Environmental information document: Savannah River Laboratory Seepage Basins  

Energy Technology Data Exchange (ETDEWEB)

This document provides environmental information on postulated closure options for the Savannah River Laboratory Seepage Basins at the Savannah River Plant and was developed as background technical documentation for the Department of Energy`s proposed Environmental Impact Statement (EIS) on waste management activities for groundwater protection at the plant. The results of groundwater and atmospheric pathway analyses, accident analysis, and other environmental assessments discussed in this document are based upon a conservative analysis of all foreseeable scenarios as defined by the National Environmental Policy Act (CFR, 1986). The scenarios do not necessarily represent actual environmental conditions. This document is not meant to be used as a closure plan or other regulatory document to comply with required federal or state environmental regulations.

1987-03-01

74

Containment closure time following loss of cooling under shutdown conditions of YGN units 3 and 4  

Energy Technology Data Exchange (ETDEWEB)

The YGN Units 3 and 4 plant conditions during shutdown operation were reviewed to identify the possible event scenarios following the loss of shutdown cooling. The thermal hydraulic analyses were performed for the five cases of RCS configurations under the worst event scenario, unavailable secondary cooling and no RCS inventory makeup, using the RELAP5/MOD3.2 code to investigate the plant behavior. From the analyses results, times to boil, times to core uncovery and times to core heat up were estimated to determine the containment closure time to prevent the uncontrolled release of fission products to atmosphere. These data provide useful information to the abnormal procedure to cope with the event. 6 refs., 7 figs., 2 tabs. (Author)

1998-12-31

75

A review of 4 norm industries in Ireland  

Energy Technology Data Exchange (ETDEWEB)

Full text: This presentation will review the progress achieved so far by the Irish national regulatory agency, the Radiological Protection Institut e of Ireland (R.P.I.I.) in the investigation of work activities where the presence of natural radiation sources (NORM) could lead to a significant increase in exposure to workers or members of the public which cannot be disregarded from the radiation protection point of view. Since the coming into force in Ma y 2000 of the Radiological Protection Act, 1991 (Ionising Radiation) Order, 2000 (S.I. No. 125 of 2000) which implements the Eu B.S.S. Directive 96/29/EURATOM, four major NORM industries currently active in Ireland have been investigated. According to the literature, they are all considered liable to involve work practices resulting in exposure to NORM. They include: the gas extraction and production industry, the peat- and coal-firing power generation industry and the bauxite/alumina refining industry. For the gas industry, monitoring ...

2006-07-01

77

PPT Slide  

Indian Academy of Sciences (India)

central server with search facility involving all partner journals ...

84

Quenching of the 2psub(1/2)-2psub(3/2) proton spin-orbit splitting in the Sr-Zr region  

Energy Technology Data Exchange (ETDEWEB)

The constancy in excitation energy of the lowest 2/sup +/ state in the Sr isotopes across the N=56 subshell closure is shown to result from a reduction in the 2psub(1/2)-2psub(3/2) proton spin-orbit splitting as the 2dsub(5/2) neutron orbital is filled.

1984-06-14

85

In situ observation of fatigue crack retardation in banded ferrite?pearlite microstructure due to crack branching  

British Library Electronic Table of Contents (United Kingdom)

This paper reports the results of in situ observation of fatigue crack growth in a ferrite?pearlite steel. Stress intensity factor range (?K) decreasing/increasing and constant-?K fatigue tests have been carried out. In banded pearlite orientation, intense crack branching was observed which leads to fatigue crack retardation. Crack closure during the test was monitored to understand the fatigue crack growth behaviour.

2006-01-01

86

Heterogeneous mechanism of nucleation in a superheated cryogenic fluid flow  

Energy Technology Data Exchange (ETDEWEB)

A model of heterogeneous mechanism of nucleation on impurity particles in a fluid volume is proposed. The particle spectrum is reproduced by solving the ''inverse'' problems on stationary outflow of a boiling parahydrogen with the use of experimental data of authors. A relation for a closure of the equation system describing a non-equilibrium outflow is obtained. It is shown that within the investigated parameter range one manages to calculate the characteristics of a stationary outflow with a satisfactory accuracy.

1984-03-01

87

Foshan. A fast track combined cycle for Guangdong  

Energy Technology Data Exchange (ETDEWEB)

To meet growth in the fast developing Pearl River Delta economic zone in China`s Guangdong province, a 270 MW oil-fired combined cycle at Foshan was built and commissioned in only 22 months from financial closure. This article describes the Foshan power station, specifications, design, procurement, construction and operating concerns. 5 figs.

1995-03-01

88

Closure of Off-Site FTP  

CERN Multimedia

To reduce the number of regular break-ins on CERN machines due to passwords exposed on the network in clear text, OFF-SITE FTP ACCESS TO CERN WILL BE BLOCKED in the CERN firewall from: Tuesday 20th January 2004 If you use ftp to access CERN computers from outside CERN then please see the link below for alternative access means and further advice: http://cern.ch/security/ftp Denise Heagerty, CERN Computer Security officer, Computer.Security@cern.ch

2004-01-01

89

Closure of Off-Site FTP  

CERN Document Server

To reduce the number of regular break-ins on CERN machines due to passwords exposed on the network in clear text, OFF-SITE FTP ACCESS TO CERN WILL BE BLOCKED in the CERN firewall from: Tuesday 20th January 2004 If you use ftp to access CERN computers from outside CERN then please see the link below for alternative access means and further advice: http://cern.ch/security/ftp Denise Heagerty, CERN Computer Security officer, Computer.Security@cern.ch

2003-01-01

90

ATP Hydrolysis in Eg5 Kinesin Involves a Catalytic Two-water Mechanism*?  

UK PubMed Central (United Kingdom)

Motor proteins couple steps in ATP binding and hydrolysis to conformational switching both in and remote from the active site. In our kinesin·AMPPPNP crystal structure, closure of the active...Full Text Available

2010-02-19

91

Decommissioning of facility for use of radioisotopes on waste management and disposal facility  

Energy Technology Data Exchange (ETDEWEB)

All the tests have been finished up in the Waste Management and Disposal Facility which has been used for the safety tests of solidified radioactive waste on sea dumping disposal. The decommissioning of this facility was performed for use of radioisotopes. This report describes the plan on decommissioning of facility for use of radioisotopes, the contamination checking methods and measurement of radioactivity, the fore case and practice for amount of generated radioactive wastes, the operation procedures for dismantlement, the safety measures, the expenses for decommissioning and so on. (author)

1999-09-01

92

RCRA closure of the Building 3001 Storage Canal  

Energy Technology Data Exchange (ETDEWEB)

The 3001 Storage Canal is located under portions of Buildings 3001 and 3019 at Oak Ridge National Laboratory (ORNL) and has a capacity of approximately 62,000 gallons of water. The term canal has historically been used to identify this structure, however, the canal is an in-ground reinforced concrete structure satisfying the regulatory definition of a tank. From 1943 through 1963, the canal in Building 3001 was designed to be an integral part of the system for handling irradiated fuel from the Oak Ridge Graphite Reactor. Because one of the main initial purposes of the reactor was to produce plutonium for the chemical processing pilot plant in Building 3019, the canal was designed to be the connecting link between the reactor and the pilot plant. During the war years, natural uranium slugs were irradiated in the reactor and then pushed out of the graphite matrix into the system of diversion plates and chutes which directed the fuel into the deep pit of the canal. After shutdown of the ...

1992-09-01

93

Temporary endovascular control of a bleeding aortoenteric fistula by transcatheter coil embolization.  

Science.gov (United States)

A 67-year-old man presented with gastrointestinal bleeding resulting from a fistula between the aortic stump and the fourth part of the duodenum 14 months after an axillobifemoral bypass, graft excision, and aortic stump closure for aortic graft infection. The patient initially refused any attempt at definitive surgical treatment so coil embolization of the aortic stump was performed via a brachial approach. Coil embolization may be a useful adjunct in the management of such difficult problems. This approach may buy time and allow careful planning of a definitive treatment or may serve as a palliative procedure in inoperable patients. PMID:15947052

2005-06-01

94

Radiological criteria, potential and limitations of ADTT at closing nuclear fuel cycle  

International Nuclear Information System (INIS)

Closure of nuclear fuel cycle is considered as a way to reduce the hazards of nuclear power industry waste. The potential and prospects of different technologies and installations including ADTT in solving this problem are discussed. A new relative criterion is proposed to assess the dangers of the waste. Equilibrium mode approximation is used in the estimates. It is shown that irretrievable losses of actinides do not depend on relative intensity of burning. Neutron economy of accelerator-driven blankets is considered and an expression is derived for transmutation value of 'external' neutrons. 8 refs., 2 tabs.

1996-06-01

95

Modeling of feed water check valves using RELAP5; Modellierung von Speisewasserrueckschlagventilen in RELAP5  

Energy Technology Data Exchange (ETDEWEB)

Westinghouse Electric Germany GmbH has developed fluid dynamic models for medium-actuated armatures using the thermal hydraulic code RELAP5 in order to reach a more realistic description of the armature behavior including fluid-structure interactions in case of transient flow conditions in piping systems. The contribution is concerned with the modeling of damped check valves. The model allows the description of the behavior during opening and closure of a check armature. The calculated results show good agreement with the available measured data.

2009-07-01

96

Grid-controlled plasma cathodes  

International Nuclear Information System (INIS)

Experiments are described on a plasma cathode with biased grids to prevent entry of ions into the electron extraction gap. The cathode has potential applications to the generation of high-current pulsed electron beams. Operation at 20 A/cm"2 is theoretically possible. The source combines the low average power consumption of a plasma cathode with many of the attractive features of thermionic cathodes, such as space-charge-limited extractor gap electron flow, fast turn-on, and no diode closure. Initial experiments are reported at the 2 A/cm"2 level for pulse lengths to 160 #mu#s.

97

Correction of skeletal Class II-anterior deep bite and prominent chin by forced surgical rotation of the mandible  

British Library Electronic Table of Contents (United Kingdom)

The purpose of this paper is to describe a technique of forced surgical rotation of the mandible used in skeletal Class II patients with deep bite and prominent chin. Posterior occlusal composite onlays combined with preoperative orthodontic treatment without anterior intrusion increase the posterior rotational component of the surgical mandibular advancement, when removed during operation. This manoeuvre allows for the surgical closure of the posterior open bite, while anteriorly the deep bite is opened. This technique avoids bimaxillary rotation surgery with dorsal impaction in mild to moderate cases. In any case, a chin setback osteotomy with compromised aesthetics can be avoided.

2010-01-01

98

Aluminum hydroxide issue closure package  

Energy Technology Data Exchange (ETDEWEB)

Aluminum hydroxide coatings on fuel elements stored in aluminum canisters in K West Basin were measured in July and August 1998. Good quality data was produced that enabled statistical analysis to determine a bounding value for aluminum hydroxide at a 99% confidence level. The updated bounding value is 10.6 kg per Multi-Canister Overpack (MCO), compared to the previously estimated bounding value of 8 kg/MCO. Thermal analysis using the updated bounding value, shows that the MCO generates oxygen concentrate that are below the lower flammability limits during the 40-year interim storage period and are, therefore, acceptable.

1998-08-26

99

Occurrence of fecal indicator bacteria in surface waters and the subsurface aquifer in Key Largo, Florida.  

UK PubMed Central (United Kingdom)

Sewage waste disposal facilities in the Florida Keys include septic tanks and individual package plants in place of municipal collection facilities in most locations. In Key Largo, both facilities discharge...Full Text Available

1995-06-01

100

Minimizing energy consumption of accelerators and storage ring facilities  

Science.gov (United States)

The discussion of energy usage falls naturally into three parts. The first is a review of what the problem is, the second is a description of steps that can be taken to conserve energy at existing facilities, and the third is a review of the implications of energy consumption on future facilities.

101

Modeling of turbulent bubbly flows; Modelisation des ecoulements turbulents a bulles  

Energy Technology Data Exchange (ETDEWEB)

The two-phase flows involve interfacial interactions which modify significantly the structure of the mean and fluctuating flow fields. The design of the two-fluid models adapted to industrial flows requires the taking into account of the effect of these interactions in the closure relations adopted. The work developed in this thesis concerns the development of first order two-fluid models deduced by reduction of second order closures. The adopted reasoning, based on the principle of decomposition of the Reynolds stress tensor into two statistically independent contributions turbulent and pseudo-turbulent parts, allows to preserve the physical contents of the second order relations closure. Analysis of the turbulence structure in two basic flows: homogeneous bubbly flows uniform and with a constant shear allows to deduce a formulation of the two-phase turbulent viscosity involving the characteristic scales of bubbly ...

2005-03-15

102

Evaluation of the residual radiation field in the proton accelerator facility of the Proton Engineering Frontier Project (PEFP) in Korea  

British Library Electronic Table of Contents (United Kingdom)

In Korea, the Proton Engineering Frontier Project (PEFP) is building a proton linear accelerator facility with energy up to 100MeV and a beam current of 20mA. In this study, a radiation field after shutdown in the accelerator facility of the PEFP was evaluated for the purpose of the radiation shielding by using MCNPX code. A facility modeling was performed for the accelerator tunnel building, accelerator chain, target rooms and beam experiment hall. And radiation source terms were evaluated in the facility. With this facility, model and radiation source terms, the concentration of 41Ar was evaluated and the cooling time satisfying regulation in Korea was calculated.

2007-01-01

103

Report on progress of researches by common utilization of JAERI nuclear facilities, for fiscal 1996  

Energy Technology Data Exchange (ETDEWEB)

This issue is the collection of the papers on progress of researches by common utilization of JAERI nuclear facilities. The 43 of the papers are indexed individually. (J.P.N.)

1998-01-01

104

Foodstuff Concentrations and Relocation Considerations Following a Tritium Oxide Release from SRS Tritium Facilities  

Energy Technology Data Exchange (ETDEWEB)

The ingestion pathway consequences following an accidental tritium release from the Savannah River Site Tritium Facilities are evaluated.

1999-05-18

105

Evaluation of the Cask Transportation Facility Modifications (CTFM) compliance to DOE order 6430.1A; FINAL  

International Nuclear Information System (INIS)

This report was prepared to evaluate the compliance of Cask Transportation Facility Modifications (CTFM) to DOE Order 6430.1A.

106

Cold vacuum drying facility design requirements; FINAL  

International Nuclear Information System (INIS)

This document provides the detailed design requirements for the Spent Nuclear Fuel Project Cold Vacuum Drying Facility. Process, safety, and quality assurance requirements and interfaces are specified.

107

Facility Effluent Monitoring Plan for Pacific Northwest National Laboratory Balance-of-Plant Facilities  

Energy Technology Data Exchange (ETDEWEB)

The Pacific Northwest National Laboratory (PNNL) operates a number of research and development (R and D) facilities for the Department of Energy on the Hanford Site. According to DOE Order 5400.1, a Facility Effluent Monitoring Plan is required for each site, facility, or process that uses, generates, releases, or manages significant pollutants or hazardous materials. Three of the R and D facilities: the 325, 331, and 3720 Buildings, are considered major emission points for radionuclide air sampling and thus individual Facility Effluent Monitoring Plans (FEMPs) have been developed for them. Because no definition of ''significant'' is provided in DOE Order 5400.1 or the accompanying regulatory guide DOE/EH-0173T, this FEMP was developed to describe monitoring requirements in the DOE-owned, PNNL-operated facilities that do not ...

1999-04-02

109

The ALPHA programs and thermal-hydraulic facilities at PSI  

International Nuclear Information System (INIS)

... J. DREIER, M. HUGGENBERGER, C. AUBERT, TH BANDURSKI, F. DE

1999-12-01

111

Radiation facility with electron accelerator of the Institute for Nuclear Research of Ukraine, Kiev  

International Nuclear Information System (INIS)

Characteristics of the Ukrainian NSA NRI radiation facility for scientific researches and developments of industrial radiation technology are performed. Parts of the facility, design peculiarities of technical tools are described. Biological protection of the facility and radiation protection system, transport line, systems of technical provision and radiation measurements are discussed

2003-02-01

113

On technical opportunity of use of the pactel facility for investigation of coolant phenomenon in horizontal steam generators  

Energy Technology Data Exchange (ETDEWEB)

In this paper the possibility of using the test facility PACTEL concerning the investigations of thermal hydraulic special features of the primary coolant circuit acting under natural circulation is under consideration. It is suggested to study a stratification phenomenon of a coolant in upper plenum of a reactor and also a horizontal steam generator (HSG) hot collector temperature regime. For such investigations the facility must be modified. It is shown that this work is not large and expensive, as the facility is a lightly suitable unit for different researches. (orig.)

2001-07-01

114

On technical opportunity of use of the pactel facility for investigation of coolant phenomenon in horizontal steam generators  

International Nuclear Information System (INIS)

In this paper the possibility of using the test facility PACTEL concerning the investigations of thermal hydraulic special features of the primary coolant circuit acting under natural circulation is under consideration. It is suggested to study a stratification phenomenon of a coolant in upper plenum of a reactor and also a horizontal steam generator (HSG) hot collector temperature regime. For such investigations the facility must be modified. It is shown that this work is not large and expensive, as the facility is a lightly suitable unit for different researches. (orig.)

2001-03-20

115

Monte Carlo design calculations for a neutron imaging facility collimator  

Energy Technology Data Exchange (ETDEWEB)

A thermal neutron imaging facility for computed tomography and real-time neutron radiography is being developed at the University of Texas at Austin. The TRIGA reactor is a graphite-reflected Mark It pool-type research reactor. The neutron imaging facility will use beam port, which is at one end of a through part. Monte Carlo calculations were used to design the neutron collimator for this facility.

1996-12-31

118

FFTF and the ASME Code  

Science.gov (United States)

Photographs are presented of the FFTF reactor facility, components, and some materials.

1978-01-01

120

Dioxins in the Baltic sea  

Wastenet

for municipal waste iron ore sinter plants incinerators for clinical waste facilities of the non-ferrous metal

121

Development of a Standard Data Base and Computer ...  

Science.gov (United States)

... (Author). Descriptors : (*TERMINAL FLIGHT FACILITIES ... PROGRAMMING, HANDLING), QUEUEING THEORY, STOCHASTIC PROCESSES ...

1973-01-01

124

BC  

Wastenet

all Certified ESM facilities capable of receiving used mobile phone waste from non-Annex VII countries.

126

53672  

Science.gov (United States)

... numbers of marine mammals during operation of an offshore liquefied natural gas (LNG) facility in the Massachusetts Bay for ... ...

127

21631  

Science.gov (United States)

... harassment, incidental to construction and operation of an offshore liquefied natural gas (LNG) facility in Massachusetts Bay. Under the ... ...

128

11328  

Science.gov (United States)

... harassment, incidental to construction and operation of an offshore liquefied natural gas (LNG) facility. Under the Marine Mammal Protection ... ...

129

Review of Regulatory Quality Assurance Requirements for the Operation of Nuclear R and D Facilities  

International Nuclear Information System (INIS)

Korea Atomic Energy Research Institute (KAERI) has many R and D facilities in operation, including HANARO research reactor, radioactive waste treatment facility (RWTF), post-irradiation examination facility (PIEF) and irradiated material test facility (IMEF). Recently, nation-wide interest is focused on the safety and security of major industrial facilities. Safe operation of nuclear facilities is imperative because of the consequence of public disaster by radiological release/ contamination, in case of an accident. Recently, Ministry of Science and Technology (MOST) of the Korean government announced amendments of Atomic Energy laws to enforce requirements of the physical protection and radiological emergency. In this paper, the context of amended Atomic Energy laws were reviewed to confirm quality assurance measures and identify additional QA activities, if ...

2005-10-27

130

Automation in a material processing/storage facility  

Energy Technology Data Exchange (ETDEWEB)

The Savannah River Site (SRS) is currently developing a new facility, the Actinide Packaging and Storage Facility (APSF), to process and store legacy materials from the United States nuclear stockpile. A variety of materials, with a variety of properties, packaging and handling/storage requirements, will be processed and stored at the facility. Since these materials are hazardous and radioactive, automation will be used to minimize worker exposure. Other benefits derived from automation of the facility include increased throughput capacity and enhanced security. The diversity of materials and packaging geometries to be handled poses challenges to the automation of facility processes. In addition, the nature of the materials to be processed underscores the need for safety, reliability and serviceability. The application of automation in this facility must, ...

1997-05-01

131

Surge-line thermal stratification: Displacements and fatigue damage computations  

Energy Technology Data Exchange (ETDEWEB)

Slow, unexpected displacements have been experienced in most pressurized water reactor (PWR) surge lines. Sometimes, these displacement lead to gap closure at the pipe whip restraints. These movements occur because of thermal stratification. This movement has the potential to increase stresses to valves, which may exceed the material yield stress. To understand this phenomenon, Framatome, Commissariat a l'Energie Atomique, and Electricite de France have undertaken large programs for the study of (1) thermal-hydraulic tests with a half-scale Plexiglas surge line, (2) thermal-hydraulic computations of permanent states and transients with a two-dimensional model, and (3) mechanical analysis of displacements and computation of fatigue damage due to stratification. This paper deals with the last subject. Avoiding stratification in piping by process modifications is difficult because of the high flow rate needed. Alternative solutions for coping with ...

1989-01-01

132

Phase chemistry and radionuclide retention of high level radioactive waste tank sludges  

Energy Technology Data Exchange (ETDEWEB)

The US Department of Energy (DOE) has millions of gallons of high level nuclear waste stored in underground tanks at Hanford, Washington and Savannah River, South Carolina. These tanks will eventually be emptied and decommissioned. This will leave a residue of sludge adhering to the interior tank surfaces that may contaminate groundwaters with radionuclides and RCRA metals. Experimentation on such sludges is both dangerous and prohibitively expensive so there is a great advantage to developing artificial sludges. The US DOE Environmental Management Science Program (EMSP) has funded a program to investigate the feasibility of developing such materials. The following text reports on the success of this program, and suggests that much of the radioisotope inventory left in a tank will not move out into the surrounding environment. Ultimately, such studies may play a significant role in developing safe and cost effective tank closure strategies.

2000-05-19

133

Omental pedicle flap used to treat a bronchopleural fistula after diaphragma--pericardio-pleuropneumonectomy.  

Science.gov (United States)

In a 47-year-old male patient a bronchopleural fistula was apparent 22 days after extended right-sided diaphragma-pericardio-pleuro-pneumonectomy for pleuramesothelioma. The thoracic cavity was infected. Rethoracotomy was performed and the fistula was closed using an omental pedicle flap. The bronchial stump became tight and the cavity fluid became sterile. No abdominal complications were seen. The patient died 8 months later from malignant pericardial infiltration. The ability of greater omentum to revascularize ischemic tissue, to absorb fluid and to resist local infection is proved and used in several subspecialities of surgery. Nevertheless the use of the greater omentum in the management of bronchopleural fistula has been rarely published. The reported case shows that the closure of a large bronchopleural fistula is possible by using the attributes of the omental tissue. PMID:2264043

1990-10-01

134

Effects of size and spacing of uniformly distributed pearlite particles on fatigue crack growth behavior of ferrite pearlite steels  

British Library Electronic Table of Contents (United Kingdom)

Fatigue crack growth tests of three ferrite-pearlite steels with different size and spacing of pearlite particles, which were uniformly distributed in the ferrite matrix, were carried out to investigate the effect of microstructure on fatigue crack growth behavior in the Paris regime. The fatigue crack growth rates for the three materials did not coincide with each other, even when the crack growth curves were arranged by the effective stress intensity factor range. From in situ observations, crack tip stress shielding phenomena, such as interlocking and branching, were found on the crack wake, which enhanced fatigue crack growth resistance. A small size and spacing of pearlite particle seemed to induce small but frequent crack deflections, which resulted in crack closure phenomena. On the...

2010-01-01

135

Economic-impact analysis of effluent limitations and standards for the battery-manufacturing industry  

Energy Technology Data Exchange (ETDEWEB)

The report identifies and analyzes the economic impacts of water pollution control regulations on the battery manufacturing industry. These regulations include effluent limitations and standards based on BPT (best practical control technology currently available), BAT (best available technology economically achievable), PSES (pretreatment standards existing sources), NSPS (new source performance standards), and PSNS (pretreatment standards new sources), that have been promulgated under authority of Sections 301, 304, 306, 307, 308, and 501 of the Federal Water Pollution Control Act, as Amended (the Clean Water Act). The primary economic impact variables of interest include price changes, plant closures, substitution effects, changes in employment, shifts in the balance of foreign trade, changes in industry profitability, structure, and competition, and impacts on small business.

1984-01-01

136

Economic impact analysis of proposed effluent limitations and standards for the gold placer mining industry  

Energy Technology Data Exchange (ETDEWEB)

The purpose of the study is to analyze the economic impacts that are likely to result from promulgation of the proposed best practicable control technology (BPT), best available technology economically achievable (BAT) and Best Conventional Technology (BCT) effluent limitations and standards on placer mining in the United States. The results of the economic impact analysis will help establish pollution control regulations that are economically achievable. The analysis examines how each of four alternative pollution control technologies affects the financial viability of placer mines in the United States. The impacts examined include reduced profitability, production cutbacks, mine closures, and employment and earning losses, as well as impacts to the local economies.

1985-08-01

137

Decay of very neutron-rich Mn nuclides and vanishing of the N=40 subshell closure in {sup 66}Fe  

Science.gov (United States)

The use of chemically selective laser ionization combined with beta-delayed neutron counting at ISOLDE has permitted identification and half-life measurements for {sup 61}Mn up through {sup 69}Mn. The 14(4)-ms half life for {sup 69}Mn is one of the shortest determined for any nuclide beyond the sd shell. Gamma-ray singles and coincidence spectra have been determined for the decays of {sup 64,66}Mn to levels of {sup 64,66}Fe, revealing strong deformation and vanishing of the N=40 subshell in the Fe isotopes. {copyright} {ital 1998 American Institute of Physics.}

1998-12-01

138

Decay of very neutron-rich Mn nuclides and vanishing of the N=40 subshell closure in "6"6Fe  

International Nuclear Information System (INIS)

The use of chemically selective laser ionization combined with beta-delayed neutron counting at ISOLDE has permitted identification and half-life measurements for "6"1Mn up through "6"9Mn. The 14(4)-ms half life for "6"9Mn is one of the shortest determined for any nuclide beyond the sd shell. Gamma-ray singles and coincidence spectra have been determined for the decays of "6"4","6"6Mn to levels of "6"4","6"6Fe, revealing strong deformation and vanishing of the N=40 subshell in the Fe isotopes.

1998-12-21

139

Cosmic-ray antiprotons, positrons, and gamma rays from halo dark matter annihilation  

Energy Technology Data Exchange (ETDEWEB)

The subject of cosmic ray antiproton production is reexamined by considering other choices for the nature of the Majorana fermion chi other than the photino considered in a previous article. The calculations are extended to include cosmic-ray positrons and cosmic gamma rays as annihilation products. Taking chi to be a generic higgsino or simply a heavy Majorana neutrino with standard couplings to the Z-zero boson allows the previous interpretation of the cosmic antiproton data to be maintained. In this case also, the annihilation cross section can be calculated independently of unknown particle physics parameters. Whereas the relic density of photinos with the choice of parameters in the previous paper turned out to be only a few percent of the closure density, the corresponding value for Omega in the generic higgsino or Majorana case is about 0.2, in excellent agreement with the value associated with galaxies and one which is sufficient to give the halo mass. 52 ...

1988-02-01

140

Circular map for supercavitating flow in a multiply connected domain  

British Library Electronic Table of Contents (United Kingdom)

A nonlinear free boundary-value problem of supercavitating flow past n + 1 hydrofoils is analyzed. To describe the cavities' closure mechanism, the Tulin-Terentev single-spiral-vortex model is employed. The flow domain is considered as the image of an (n + 1)-connected circular domain. The conformal map is constructed in terms of the solutions to two Riemann-Hilbert problems of the theory of symmetric automorphic functions. One of the problems is homogeneous and its coefficients are continuous functions while the second problem is inhomogeneous and has discontinuous coefficients. The exact solutions to the problems are found by using quasiautomorphic and quasimultiplicative analogs of the Cauchy kernel. The case of a single plate is considered in detail and the numerical results are report...

2009-01-01

141

A numerical study on the long term thermo-poroelastic effects of cold water injection into naturally fractured geothermal reservoirs  

British Library Electronic Table of Contents (United Kingdom)

The residing fracture system and the prevailing in situ stresses have a significant impact on fluid flow and heat transfer in crystalline rocks. The long term response of fracture systems to changes in effective stresses, in particular the long term geo-mechanical effects of thermal stresses on reservoir characteristics is of particular interest to the geothermal industry.In this paper, a geothermal reservoir model is presented, in which a thermo-poroelastic finite element module is coupled to a fracture geomechanical module. This describes fracture closure as a function of effective stress and the changes in parameters, such as effective permeability, porosity and discrete fracture apertures. The novelty of this approach lies in its dynamic treatment of the characteristic properties of in...

2011-01-01

142

Advanced conceptual design report: T Plant secondary containment and leak detection upgrades. Project W-259  

Energy Technology Data Exchange (ETDEWEB)

The T Plant facilities in the 200-West Area of the Hanford site were constructed in the early 1940s to produce nuclear materials in support of national defense activities. T Plant includes the 271-T facility, the 221-T facility, and several support facilities (eg, 2706-T), utilities, and tanks/piping systems. T Plant has been recommended as the primary interim decontamination facility for the Hanford site. Project W-259 will provide capital upgrades to the T Plant facilities to comply with Federal and State of Washington environmental regulations for secondary containment and leak detection. This document provides an advanced conceptual design concept that complies with functional requirements for the T Plant Secondary Containment and Leak Detection upgrades.

1995-05-12

143

Wind Characteristics at the Vawt Test Facility.  

Science.gov (United States)

A limited program of field measurements was undertaken in order to define the wind characteristics of the DOE/Sandia vertical axis wind turbine test facility. Because micrometeorological conditions under which a particular wind turbine is tested may have ...

1978-01-01

144

Use of the fast flux test facility for tritium production  

Energy Technology Data Exchange (ETDEWEB)

This report provides the results of a JASON review of the technical feasibility of using the Department of Energy`s (DOE`s) Fast Flux Test Facility (FFTF) to generate tritium needed for the enduring United States nuclear weapons stockpile.

1996-10-25

145

Solar Cogeneration Facility: Cimarron River Station, Central Telephone and Utilities-Western Power. Executive summary  

Energy Technology Data Exchange (ETDEWEB)

A brief overview of the conceptual design of a solar central receiver system integrated with an existing cogeneration facility is provided. A synopsis of the performance and economic evaluation, and an assessment of the concept from the site owner's perspective are given.

1981-08-07

146

Recent Developments in Coal Liquefaction at the Wilsonville Advanced Coal Liquefaction Research and Development Facility.  

Science.gov (United States)

The results of the two most recently completed runs at the Wilsonville Advanced Coal Liquefaction Research and Development Facility are presented. In Run 255, initial screening of operating conditions for the liquefaction of a Texas lignite was completed....

1991-01-01

147

Pulmonary Alveolar Proteinosis in Workers at an Indium Processing Facility  

UK PubMed Central (United Kingdom)

Two cases of pulmonary alveolar proteinosis, including one death, occurred in workers at a facility producing indium-tin oxide (ITO), a compound used in recent years to make flat panel displays. Both...Full Text Available

2010-03-01

148

Heat Cycle Reserch Experimental Program report, FY-84  

Energy Technology Data Exchange (ETDEWEB)

The Heat Cycle Research Facility (HCRF) is an experimental binary-cycle facility used to investigate different concepts and/or components for generating electrical power from a geothermal resource. This report briefly desc

1984-09-01

149

HPA - Radon Calibration Facilities  

Wastenet

... Radon gas concentrations are measured using instruments with calibrations traceable to the UK National Physical Laboratory and PTB, Germany. The primary facility is a 43 m3 walk-in chamber accessed by an airlock. Radon gas is maintained at a level in this chamber that is ...

150

Energy Engineering Analysis Program, Fort Campbell, Kentucky, energy audit of dining facilities; executive summary. Final report  

Science.gov (United States)

This volume is a summary of the results of the final report of the Energy Engineering Analysis Program (EEAP) Study of 30 selected dining facilities at Fort Campbell, Kentucky.

1986-08-01

151

Decontamination of nuclear facilities  

International Nuclear Information System (INIS)

Thirty-seven papers were presented at this conference in five sessions. Topics covered include regulation, control and consequences of decontamination; decontamination of components and facilities; chemical and non-chemical methods of decontamination; and TMI decontamination experience.

1982-09-19

152

Computer code analysis of steam generator in thermal-hydraulic test facility simulating nuclear power plant.  

Science.gov (United States)

In the study three loss-of-feedwater type experiments which were preformed with the PACTEL facility has been calculated with two computer codes. The purpose of the experiments was to gain information about the behaviour of horizontal steam generator in a ...

1995-01-01

153

33 CFR 148.105 - What must I include in my application?  

Science.gov (United States)

...capacity, and ownership of all planned and existing onshore pipelines, storage facilities, refineries, petrochemical...will be served by the port, including: (i) Onshore pipelines; (ii) Storage facilities; (iii)...

2010-07-01

154

Surface and subsurface analysis of Sheep Mountain anticline, Wyoming  

Energy Technology Data Exchange (ETDEWEB)

The Sheep Mountain area, in the southwest Wind River Basin, is the up plunge closure of the Derby Dome-Winkleman Dome producing trend of an echelon folds which comprise the first line of folding down the northeast flank of the Wind River Mountains. The structural style exposed in the Palozoic reservoir rocks of Sheep Mountain may serve as a model for the other structural features in the Wind River Basin. As in the case of the Derby Dome and Winkleman Dome, Sheep Mountain is typically asymmetric to the southwest. Local east-directed thrusts exposed in the core of the anticline place Pennsylvania over Permian age rocks. A major change in the trend of the anticlinal crest within Sheep Mountain, suggests development of separate left-stepping en echelon closures at depth. The northwest end of Sheep Mountain also forms a left-stepping en echelon pattern with Derby Dome. The northwest plunge of Sheep Mountain is facilitated by compartmentalization ...

1988-01-01

155

Disorders of brain development and phakomatosis  

International Nuclear Information System (INIS)

Full text: Disorders of brain development and phakomatosis are resulting from disturbed embryonic-foetal development One third of all major embryological anomalies involve CNS, and over 2000 different anomalies have been described. Anomalies of the brain often cause foetal and neonatal death, and mental and physical retardation in pediatric group. The majority of disorders of brain development and phakomatosis are idiopathic, and most of them are not hereditary or familial. Ultrasonography plays the important role in screening foetal and neonatal brain, but after closure of fontanels it is difficult to find the acoustic window. CT has limited contrast resolution, and disadvantage exposing infant to ionizing radiation. It is helpful to demonstrate the presence of calcifications. MR imaging has proved to be a diagnostic tool of major importance in children with disorders of brain development and phakomatosis. The excellent grey/white matter differentiation and ...

156

Closure relations for the multi-species Euler system. Construction and study of relaxation schemes for the multi-species and multi-components Euler systems; Relations de fermeture pour le systeme des equations d'Euler multi-especes. Construction et etude de schemas de relaxation en multi-especes et en multi-constituants  

Energy Technology Data Exchange (ETDEWEB)

After having recalled the formal convergence of the semi-classical multi-species Boltzmann equations toward the multi-species Euler system (i.e. mixture of gases having the same velocity), we generalize to this system the closure relations proposed by B. Despres and by F. Lagoutiere for the multi-components Euler system (i.e. mixture of non miscible fluids having the same velocity). Then, we extend the energy relaxation schemes proposed by F. Coquel and by B. Perthame for the numerical resolution of the mono-species Euler system to the multi-species isothermal Euler system and to the multi-components isobar-isothermal Euler system. This allows to obtain a class of entropic schemes under a CFL criteria. In the multi-components case, this class of entropic schemes is perhaps a way for the treatment of interface problems and, then, for the treatment of the numerical mixture area by using a Lagrange + projection scheme. Nevertheless, we have to find a good projection ...

2001-07-01

158

The role of CEMs in DOE thermal treatment  

Energy Technology Data Exchange (ETDEWEB)

The Department of Energy (DOE) currently operates four thermal treatment facilities that are permitted under regulations for hazardous waste combustors. As regulations become more stringent and public stakeholders become more influential, permitting these facilities is increasingly difficult. As they become more available, continuous emission monitors (CEMs) may offer the potential to assure regulators and the public of the safe operation of treatment facilities. The Mixed Waste Focus Area (MWFA) has participated in the development and testing of a variety of CEMs that could have application to DOE facilities.

1998-07-01

159

The Application of Simulation Methods to Intra-Airport ...  

Science.gov (United States)

... Descriptors : *Terminal flight facilities, *Traffic ... Ground support, Queueing theory, Passengers ... Delay, Assessment, Stochastic processes, Ground ...

1975-09-01

160

Selenium - Global Change Master Directory (GCMD)  

Science.gov (United States)

This study is an evaluation of the potential environmental impacts of contaminated groundwater from the ASARCO metals refining facility adjacent to the ...

161
162

Review of ion accelerators  

Energy Technology Data Exchange (ETDEWEB)

The field of ion acceleration to higher energies has grown rapidly in the last years. Many new facilities as well as substantial upgrades of existing facilities have extended the mass and energy range of available beams. Perhaps more significant for the long-term development of the field has been the expansion in the applications of these beams, and the building of facilities dedicated to areas outside of nuclear physics. This review will cover many of these new developments. Emphasis will be placed on accelerators with final energies above 50 MeV/amu. Facilities such as superconducting cyclotrons and storage rings are adequately covered in other review papers, and so will not be covered here.

1990-06-01

163

Results of the 2nd periodical inspection of the asphalt solidification facility and the incinerator in Unit 2 of the Sendai Nuclear Power Station  

International Nuclear Information System (INIS)

The 2nd periodical inspection was carried out on the asphalt solidification facility and the incinerator in Unit 2 of the Sendai Nuclear Power Station from November 5 to 28, 1985. Inspection was made in radiation control facility and disposal facility. By external appearance, disassembly, function and performance tests there were observed no abnormalities. The personnel exposure doses during the inspection were below the permissible level. In the inspection, improvement etc. works were not done. (Mori, K.).

1986-01-01

164

Results of regular inspection of No.2 plant in Sendai Nuclear Power Station, Kyushu Electric Power Co., Inc  

International Nuclear Information System (INIS)

The regular inspection of No.2 plant in Sendai Nuclear Power Station was carried out from January 7 to February 8, 1985. The summary of the results of this regular inspection is as follows. The facilities as the object of inspection were radiation control facilities and waste facilities. On these facilities as the object of inspection, the appearance, disassembling, functional, performance and other inspections were carried out, and as the results, abnormality was not found at all. The works related to this regular inspection were accomplished within the range of the allowable radiation dose based on the relevant laws. (Kako, I.).

1986-01-01

165

PowerPoint Presentation  

Wastenet

facilities, building hygienic latrines and introducing regular solid waste collection systems . These methods are constantly being developed and

166

National Ignition Facility Management Descriptions Revision 4  

Energy Technology Data Exchange (ETDEWEB)

The purpose of this document is to describe the NIF Project Organization and the roles and responsibilities of the managers charged with executing the Project.

2000-08-01

169

Mastery of risks: we build the memory of radioactive waste disposal facilities  

International Nuclear Information System (INIS)

The ANDRA, the French national agency of radioactive wastes, is organizing today the information needs of tomorrow. The aim is to allow the future generations to have access to the knowledge of the existence of subsurface radioactive waste facilities and to understand the context and technologies of such facilities. The storage of this information is made on 'permanent paper', a high resistant paper with a lifetime of 600 to 1000 years. An updating of these data is made every 5 years for each waste disposal center. Another project, still in progress, concerns the memory management of deep geologic waste disposal facilities for which the time scale to be considered is of the order of millennia. (J.S.)

170

Los Alamos DP West Plutonium Facility decontamination project  

Energy Technology Data Exchange (ETDEWEB)

The DP West Plutonium Facility operated by the Los Alamos National Laboratory, Los Alamos, New Mexico, was decontaminated between April 1978 and April 1981. The facility was constructed in 1944 to 1945 to produce plutonium metal and fabricate parts for nuclear weapons. It was continually used as a plutonium processing and research facility until mid-1978. Decontamination operations included dismantling and removing gloveboxes and conveyor tunnels; removing process systems, utilities, and exhaust ducts; and decontaminating all remaining surfaces. This report describes glovebox and conveyor tunnel separations, decontamination techniques, health and safety considerations, waste management procedures, and costs of the operation.

1982-01-01

171

Handbook: Approaches for the Remediation of Federal Facility ...  

Science.gov (United States)

... 4-4 UXO disposal operations ... testing of sequencing batch reactor treatment of ... and lead toward the anode compartment ..... ...

1993-09-01

172

Energy and Water Conservation  

Science.gov (United States)

Jet Propulsion Laboratory. California Institute of Technology. Pasadena, California. Energy and Water Conservation. Steve Rigdon. Facilities Energy Manager ...

173

Energy Engineering Analysis Program (EEAP), Cornhusker ...  

Science.gov (United States)

... is to develop a systematic program of energy consumption reductions in compliance with the stated goals of the Army Facilities Energy Plan (AFEP ...

1984-03-01

174

Energy Engineering Analysis (EEA) Program, Europe. ...  

Science.gov (United States)

... projects that will result in the reduction of energy consumption in compliance with the objectives set forth in the Army Facilities Energy Plan, without ...

1983-07-01

175

Details - Night Sky Network - NASA  

Science.gov (United States)

General Meeting: NASA's biggest challenge: Education ... Turn right into the Police Association Facility at the crest of the first hill. ...

176

DOE reports on feasibility of generic oil shale test facility  

Energy Technology Data Exchange (ETDEWEB)

In order to assess whether an oil shale test facility would be of significant use to private sector oil shale developers, the US DOE has studied the past history of oil shale development and its potential for replacing petroleum supplies. A generic test facility's primary function would be to test concepts of mining, retorting, upgrading, and environmental aspects at the engineering scale. This paper summarizes the US oil shale resources, gives a technology analysis, and discusses the potential for a test facility.

1987-03-01

177

Crisis communication on nuclear facilities and addressing media  

International Nuclear Information System (INIS)

Japanese May 2009 p. 386-390 Japan Mitani, Shinji Japan Nuclear Energy

2009-05-01

178

Project quality assurance plant: Sodium storage facility, project F-031  

International Nuclear Information System (INIS)

The Sodium Storage Facility Project Quality Assurance Plan delineates the quality assurance requirements for construction of a new facility, modifications to the sodium storage tanks, and tie-ins to the FFTF Plant. This plan provides direction for the types of verifications necessary to satisfy the functional requirements within the project scope and applicable regulatory requirements determined in the Project Functional Design Criteria (FDC), WHC-SD-FF-FDC-009.

179

Neptunium storage at Hanford  

Energy Technology Data Exchange (ETDEWEB)

A decision must be made regarding whether the United State`s stockpile of neptunium should be discarded into the waste stream or kept for the production of Pu-238. Although the cost of long term storage is not inconsequential, to dispose of the material means the closing of our option to maintain control over our Pu-238 stockpile. Within the Fuels and Materials Examination Facility at Hanford there exists a remotely operated facility that can be converted for neptunium storage. This paper describes the facility and the anticipated handling requirements.

1993-06-01

180

Natural radioactive materials occurrence in oil facilities  

International Nuclear Information System (INIS)

This work presents and describes the natural radioactive occurrence in oil facilities. The origins of the detected radioactivity and the reasons of its settlement are discussed. The measurements results carried out in oil facilities in the Neuquina basin (Argentine) are shown in this work. The aim is to describe the actual situation and to evaluate the magnitude of the problem. Finally, recommendations are proposed to protect the health of the workers, especially of those who carry out the cleaning of the equipment, and to guarantee an appropriate final disposal for the generated radioactive residuals. (author)

2001-06-01

181

High-explosives test facility  

Energy Technology Data Exchange (ETDEWEB)

This report describes a high explosives test facility that makes efficient use of equipment and combines utility, convenience, and safety in a modest amount of space. It is a dedicated facility for exploratory development efforts that previously were conducted in a single room having very limited capabilities. Two explosives testing areas are now available and several projects are supported concurrently.

1982-08-01

182

FLASH-the first soft x-ray free electron laser (FEL) user facility  

Energy Technology Data Exchange (ETDEWEB)

The free electron laser (FEL) FLASH at DESY in Hamburg is the first x-ray FEL ever built. Many new developments were necessary in order to exploit the unique properties of this novel light source for scientific experiments. The facility has constantly been improved and several major upgrades have been made or are currently underway. This paper reviews the main characteristics of the user facility as well as the major developments and upgrades.

2010-10-14

183

Demonstration of neutron radiography and computed tomography at the University of Texas thermal neutron imaging facility  

Energy Technology Data Exchange (ETDEWEB)

A thermal neutron imaging facility for real-time neutron radiography and computed tomography has recently been developed and built at the University of Texas TRIGA reactor. Herein the authors present preliminary results of radiography and tomography test experiments. These preliminary results showed that the beam is of high quality and is suitable for radiography and tomography applications. A more detailed description of the facility is given elsewhere.

1999-09-01

184

Demonstration of neutron radiography and computed tomography at the University of Texas thermal neutron imaging facility  

International Nuclear Information System (INIS)

A thermal neutron imaging facility for real-time neutron radiography and computed tomography has recently been developed and built at the University of Texas TRIGA reactor. Herein the authors present preliminary results of radiography and tomography test experiments. These preliminary results showed that the beam is of high quality and is suitable for radiography and tomography applications. A more detailed description of the facility is given elsewhere

1999-06-06

185

Cold regions hydrology and hydraulics  

Energy Technology Data Exchange (ETDEWEB)

This monograph addresses a narrow aspect of cold regions engineering, namely the effects of cold weather on the traditional civil engineering disciplines of hydrology and hydraulics. Hydrologic and hydraulic considerations in the design, construction, and operation of civil works are very important. Many of the problems encountered in the design and construction of buildings, transportation systems, water supply facilities, waste treatment facilities, and hazardous waste disposal facilities, for example are closely tied to the characteristics of the site hydrology.

1990-01-01

186

About technical possibility to use VEERA facility for investigation of coolant stratification phenomenon in horizontal steam generators  

Energy Technology Data Exchange (ETDEWEB)

The presentation gives a brief insight on possibility of using the VEERA facility in studying the stratification phenomenon. The idea for such experiments is to use the facility upper plenum part to simulate the conditions in upper part of horizontal steam generator hot collector. The upper part of steam generator hot collector is one of the locations where the stratification can take part during natural circulation mode. 4 refs.

1997-12-31

187

Waste Receiving and Processing Facility Module 2A: Advanced Conceptual Design Report. Volume 1  

Energy Technology Data Exchange (ETDEWEB)

This ACDR was performed following completed of the Conceptual Design Report in July 1992; the work encompassed August 1992 to January 1994. Mission of the WRAP Module 2A facility is to receive, process, package, certify, and ship for permanent burial at the Hanford site disposal facilities the Category 1 and 3 contact handled low-level radioactive mixed wastes that are currently in retrievable storage at Hanford and are forecast to be generated over the next 30 years by Hanford, and waste to be shipped to Hanford from about DOE sites. This volume provides an introduction to the ACDR process and the scope of the task along with a project summary of the facility, treatment technologies, cost, and schedule. Major areas of departure from the CDR are highlighted. Descriptions of the facility layout and operations are included.

1994-03-01

188

High-energy x-ray microscopy techniques for laser-fusion plasma research at the National Ignition Facility  

Energy Technology Data Exchange (ETDEWEB)

Multi-kilo-electron-volt x-ray microscopy will be an important laser-produced plasma diagnostic at future megajoule facilities such as the National Ignition Facility (NIF). However, laser energies and plasma characteristics imply that x-ray microscopy will be more challenging at NIF than at existing facilities. We use analytical estimates and numerical ray tracing to investigate several instrumentation options in detail, and we conclude that near-normal-incidence single spherical or toroidal crystals may offer the best general solution for high-energy x-ray microscopy at NIF and similar large facilities. Apertured Kirkpatrick{endash}Baez microscopes using multilayer mirrors may also be good options, particularly for applications requiring one-dimensional imaging over narrow fields of view. {copyright} 1998 Optical Society of America

1998-04-01

189

Economic analysis of effluent limitation guidelines and standards for the centralized waste treatment industry  

Science.gov (United States)

This report estimates the economic and financial effects and the benefits of compliance with the proposed effluent limitations guidelines and standards for the Centralized Waste Treatment (CWT) industry. The Environmental Protection Agency (EPA) has measured these impacts in terms of changes in the profitability of waste treatment operations at CWT facilities, changes in market prices to CWT services, and changes in the quantities of waste management at CWT facilities in six geographic regions. EPA has also examined the impacts on companies owning CWT facilities (including impacts on small entities), on communities in which CWT facilities are located, and on environmental justice. EPA examined the benefits to society of the CWT effluent limitations guidelines and standards by examining cancer and non-cancer health effects of the regulation, recreational benefits, and cost savings to publicly owned ...

1998-12-01

190

Development of electronic imaging system for real time neutron radiography at TRIGA MK-II research reactor of AERE, Savar, Dhaka and utilization for research and industrial applications  

International Nuclear Information System (INIS)

The neutron radiography facility was installed at the tangential beam port of the 3 MW TRIGA MARK-II research reactor. In the facility only direct film neutron radiography method is being used. The project involves development of electronic imaging system for real time neutron radiography in the existing facility with the aim of utilizing it for research and industrial applications. In establishing the electronic imaging system for real time neutron radiography the improvements of existing facility were almost done during this period. In parallel, the former facility was used for the research: (a) A study of wood and wood plastic composites with and without additive by using film neutron radiography and (b) A study of jute reinforced polymer composites by using film neutron radiography technique. (author)

2008-09-01

191

Decree of the Czechoslovak Atomic Energy Commission No. 436/1990 on quality assurance of selected facilities with respect to nuclear safety of nuclear facilities  

International Nuclear Information System (INIS)

The Decree specifies basic quality assurance requirements applicable to machines, their parts and materials, civil engineering structures, means for automated control of technological processes including hardware and software, and electricity supply systems related to nuclear safety of nuclear facilities, and stipulates binding procedures for the implementation of technical and organizational provisions associated with the quality of selected equipment to ensure nuclear safety of nuclear facilities. Safety classes are defined for selected equipment. Requirements laid on safety assurance documentation are specified, and requirements placed on safety assurance programmes, their preparation, finalization and approval are defined. Quality assurance requirements are also specified with respect to the designing, manufacture, construction, operation, repair, modification and decommissioning of nuclear facilities. The Decree ...

1995-02-01

192

Facilities Condition and Hazards Assessment for Materials and Fuel Complex Facilities MFC-799, 799A, and 770C  

Energy Technology Data Exchange (ETDEWEB)

The Materials & Fuel Complex (MFC) facilities 799 Sodium Processing Facility (a single building consisting of two areas: the Sodium Process Area (SPA) and the Carbonate Process Area (CPA), 799A Caustic Storage Area, and 770C Nuclear Calibration Laboratory have been declared excess to future Department of Energy mission requirements. Transfer of these facilities from Nuclear Energy to Environmental Management, and an associated schedule for doing so, have been agreed upon by the two offices. The prerequisites for this transfer to occur are the removal of nonexcess materials and chemical inventory, deinventory of the calibration source in MFC-770C, and the rerouting and/or isolation of utility and service systems. This report provides a description of the current physical condition and any hazards (material, chemical, nuclear or occupational) that may be associated with past operations of these ...

2009-11-01

193

Results of 1st regular inspection of No.2 unit in Sendai Nuclear Power Plant  

International Nuclear Information System (INIS)

This report presents results of the 1st regular inspection of the No.2 unit of the Sendai Nuclear Power Plant. It was carried out during the period from September 22, 1986, to December 24, 1986. The inspection covered the main unit of the nuclear reactor, facilities for the nuclear reactor cooling system, facilities for the instrumentation control system, fuel facilities, radiation control facilities, disposal facilities, nuclear reactor containment facilities, and emergency power generation system. Checking of appearance, disassemblage, leak and functions-performance of these facilities was conducted and no abnormalities were found. All operations involved in the inspection were performed under conditions within the permissible dose as specified in the applicable laws. No major modification work was carried out during the period of the ...

1987-01-01

194

Results of 1st regular inspection of No. 2 unit in Sendai Nuclear Power Plant  

Energy Technology Data Exchange (ETDEWEB)

This report presents results of the 1st regular inspection of the No. 2 unit of the Sendai Nuclear Power Plant. It was carried out during the period from September 22, 1986, to December 24, 1986. The inspection covered the main unit of the nuclear reactor, facilities for the nuclear reactor cooling system, facilities for the instrumentation control system, fuel facilities, radiation control facilities, disposal facilities, nuclear reactor containment facilities, and emergency power generation system. Checking of appearance, disassemblage, leak and functions-performance of these facilities was conducted and no abnormalities were found. All operations involved in the inspection were performed under conditions within the permissible dose as specified in the applicable laws. No major modification work was carried out during the period of the ...

1987-09-01

195

Preparation of high burnup fuel post-irradiation testing facility  

Energy Technology Data Exchange (ETDEWEB)

In the fuel testing facilities of Japan Atomic Energy Research Institute, the post-irradiation test of practical fuel used in nuclear power stations was begun in December, 1979, and the soundness of practical fuel has been confirmed, and the valuable post-irradiation test data on the behavior of fuel have been acquired. Recently, the heightening of fuel burnup has been advanced, and also in fuel testing facilities, the development and preparation of the post-irradiation testing facility required for examining in detail high burnup fuel have been carried out. The course of the installation of the post-irradiation testing facility and the outline of the facility are reported. As the preparation of the post-irradiation testing facility for high burnup fuel, a hyperfine hardness tester that measures dynamic hardness, the measuring instrument for pellet thermal ...

1996-05-01

196

Managing system for mounted parts and spare parts of power source facilities  

Energy Technology Data Exchange (ETDEWEB)

The power source facilities of JT-60 consist of poloidal magnetic coil power source, toroidal magnetic coil power source, the power generation facility for heating, operation power distribution facility and secondary cooling facility, and at the time of the experiment operation of JT-60, they supply 1300 MVA of instantaneous maximum power to loads. The component machinery and equipment of the power source facilities are installed in about 20 indoor and outdoor places, and their mounted parts are about 15,000 kinds. About 3,000 kinds of spare parts are preserved in 15 exclusively used stores. The managing system for mounted parts and spare parts of JT-60 power source facilities which possesses the functions of rapidly and efficiently carrying out the storage of large quantity of information, mutual relating and retrieval by making mounted parts and spare parts ...

1995-07-01

197

Air pollutants emissions from waste treatment and disposal facilities.  

Science.gov (United States)

This study examined the atmospheric pollution created by some waste treatment and disposal facilities in the State of Kuwait. Air monitoring was conducted in a municipal wastewater treatment plant, an industrial wastewater treatment plant established in a petroleum refinery, and at a landfill site used for disposal of solid wastes. Such plants were selected as models for waste treatment and disposal facilities in the Arabian Gulf region and elsewhere. Air measurements were made over a period of 6 months and included levels of gaseous emissions as well as concentrations of volatile organic compounds (VOCs). Samples of gas and bioaerosols were collected from ambient air surrounding the treatment facilities. The results obtained from this study have indicated the presence of VOCs and other gaseous pollutants such as methane, ammonia, and hydrogen sulphide in air surrounding the waste treatment and disposal ...

2006-01-01

198

Nuclear structure of light Ca and heavy Cr isotopes  

Energy Technology Data Exchange (ETDEWEB)

In the present thesis, the shell structure in exotic nuclei has been investigated. The focus of the work was on finding new experimental data in neutron-rich Cr and proton-rich Ca isotopes. The investigation of light Ca isotopes concentrated on the nucleus {sup 36}Ca which was produced in a knockout reaction from a radioactive {sup 37}Ca beam. For {sup 36}Ca, the excitation energy of the first 2{sup +} state has been measured for the first time. Furthermore, momentum distributions were analyzed using a Monte-Carlo simulation of the knockout reaction. This analysis yielded the contributions of neutrons from individual orbitals to the total knockout cross section. In principle, these may be used to calculate spectroscopic factors, but such a calculation is hampered by difficulties of present knockout-reaction models in predicting precise single-particle cross sections. The measured branching ratio to the ground and excited states, on the other hand, is close to the predicted value. A ...

2007-07-01

199

Regulatory quality assurance requirements for the operation of nuclear R and D facilities in Korea  

International Nuclear Information System (INIS)

Full text: Korea Atomic Energy Research Institute (KAERI) has many R and D facilities in operation. including HANARO research reactor, radioactive waste treatment facility (RWTF), post-irradiation examination facility (PIEF) and irradiated material test facility (IMEF). Recently. nation-wide interest is focused on the safety and security of major industrial facilities. Safe operation of nuclear facilities is imperative because of the consequence of public disaster by radiological release/contamination, in case of an accident. Recently, Ministry of Science and Technology (MOST) of the Korean government announced amendments of Atomic Energy laws to enforce requirements of the physical protection and radiological emergency. All provisions on nuclear safety regulation and radiation protection are entrusted to the Atomic Energy Act(AEA). The Act is enacted as the ...

2006-10-15

200

Two-fluid modeling of condensation in the presence of noncondensables in two-phase channel flows  

Energy Technology Data Exchange (ETDEWEB)

Condensing two-phase channel flow occurs in many industrial applications, including heating and refrigeration systems. It can also occur in certain nuclear reactor accidents. For example, during a small-break loss-of-coolant accident in a pressurized water reactor, following the partial depletion of the primary coolant, condensation of steam on the primary side of the steam generator tubes can provide a heat sink for disposal of the decay heat generated in the reactor core. Condensing two-phase flow can also play an important role in the operation of the passive emergency cooling system in the advanced simplified boiling water reactor. Here, steady-state condensation in the presence of a noncondensable in a concurrent two-phase channel flow is analyzed using a two-fluid model. The effect of noncondensables on the combined heat transfer at the liquid-gas mixture interphase is accounted for by using the stagnant film model, and closure relations relevant to the ...

1995-01-01

201

Theoretical and scaling factors methods to calculate the radioactivity in operational waste streams from Unit 1 at Cernavoda NPP  

International Nuclear Information System (INIS)

The main goal of this paper is to present a methodology for calculating the radioactivity in the moderator and heat transport systems of Cernavoda NPP Unit 1, with the intention to improve the knowledge on the radionuclides inventories in the operational waste streams, and to aid the licensing process of new near surface repository. In the present paper we describe our methodology for estimating H-3 and C-14 production rates in the heavy-water moderator and heat transport systems using the capacity factors from 1997 to 2007 years. The radioactivity of the difficult-to-measure nuclides is predicted by scaling method using measured concentration in reference CANDU 6 reactor Gentilly-2. The difficult-to-measure radionuclides of primary interest in this study were those with long half-lives which have a significant role for post-closure safety assessment. The equation used to scale fission products (parents and daughters) is based on the equilibrium solution of the ...

2009-05-27

202

The synthesis of 5-[1-"1"1C]ethyl barbiturates from labelled malonic esters  

International Nuclear Information System (INIS)

The synthesis of ["1"1C]phenobarbital, ["1"1C]pentobarbital and["1"1C]amobarbital labelled in the 5-[1-"1"1C]ethyl position is reported. The malonic esters R- CH(CO_2Et)_2 [R phenyl-, 1-methylbutyl-, and 3- methylbutyl- were alkylated with [1-"1"1C]ethyl iodide prepared from ["1"1C]carbon dioxide. Ring closure of the 2-[1-"1"1C]ethyl-labelled malonic esters with urea afforded 5-[1-"1"1C]ethyl-phenobarbital,-phenobarbital, -pentobarbital and -amobarbital synthesis times of 42-47 min, counted from ["1"1C] carbon dioxide. In typical syntheses starting with 3 GBq pentobarbitol and (81 mCi) ["1"1C]carbon dioxide, 150-215 MBq (4-6 mCi) were produced in 25-30% decay corrected -amobarbital radiochemical yields with radiochemical purities greater than 98%. (author).

203

The prevalence, management and outcome for acute wounds identified in a wound care survey within one English health care district  

British Library Electronic Table of Contents (United Kingdom)

This paper reports the characteristics and local management of 826 acute wounds identified during an audit across all health care providers serving the population of Bradford, UK. Of the wounds encountered 303 were traumatic wounds and 237 primary closures with smaller numbers of other acute wound types. Of the 303 traumatic wounds 174 occurred in women (57.4%). Men predominated in the under 45s (65M:26F), this being largely accounted for by hand and finger trauma (n=62) particularly in patients of working age (M32:F12). Women predominated in the over 65s (50M:130F), this being largely accounted for by lower limb traumatic wounds (M24:F91), the majority of these being in patients 65 and over (M14:F82). In this sub-group of 96 patients 25 had wounds of 6 weeks or longer duration, only 3 had...

2009-01-01

204

Research on Dynamic Neutron Radiography in HANARO  

Energy Technology Data Exchange (ETDEWEB)

Neutron radiography is a non-destructive test method to examine a material by using the dependency of neutron attenuation on the nuclear characteristics of the atoms composing the object material. There are two categories of neutron radiography; static neutron radiography and dynamic neutron radiography. The static neutron radiography is a technique to observe a standing object by using a camera or a film cassette. The dynamic neutron radiography(DNR) is a technique to observe a moving object usually by using a camera. Depending on the camera frame rate, the dynamic neutron radiography is categorized into the real time neutron radiography(RTNR) and the high speed neutron radiography(HSNR). The frame rate for RTNR is 30 frames/s and that for HSNR is usually more that 500 frames/sec. Thus, RTNR is good for observing time-averaged phenomena and HSNR is good for observing instantaneous phenomena. DNR is a powerful tool for fluid visualization as well as the multi-phase flow research. This ...

2005-07-01

205

Research on Dynamic Neutron Radiography in HANARO  

International Nuclear Information System (INIS)

Neutron radiography is a non-destructive test method to examine a material by using the dependency of neutron attenuation on the nuclear characteristics of the atoms composing the object material. There are two categories of neutron radiography; static neutron radiography and dynamic neutron radiography. The static neutron radiography is a technique to observe a standing object by using a camera or a film cassette. The dynamic neutron radiography(DNR) is a technique to observe a moving object usually by using a camera. Depending on the camera frame rate, the dynamic neutron radiography is categorized into the real time neutron radiography(RTNR) and the high speed neutron radiography(HSNR). The frame rate for RTNR is 30 frames/s and that for HSNR is usually more that 500 frames/sec. Thus, RTNR is good for observing time-averaged phenomena and HSNR is good for observing instantaneous phenomena. DNR is a powerful tool for fluid visualization as well as the multi-phase flow research. This ...

2005-10-27

206

Nuclear mass prediction as an image reconstruction problem: can observed pattern determine mass values?  

Energy Technology Data Exchange (ETDEWEB)

Theoretical prediction of nuclear masses is analyzed as a pattern recognition problem on the N-Z plane. A global pattern is observed by plotting the differences between measured masses and Liquid Drop Model (LDM) predictions. After unfolding the data by removing the smooth LDM mass contributions, the remaining microscopic effects have proved difficult to model, although they display a striking pattern. These deviations carry information related to shell closures, nuc]ear deformation and the residual nuclear interactions. In the present work the more than 2000 known nuclear masses are studied as an array in the N-Z plane viewed through a mask, behind which the approximately 7000 unknown unstable nuclei that can exist between the proton and neutron drip lines are hidden. We show here that employing a Fourier transform deconvolution method these by masses can be predicted with similar accuracy than standard methods. We believe that a more general approach needs to be ...

2006-07-01

207

Nuclear mass prediction as an image reconstruction problem: can observed pattern determine mass values?  

International Nuclear Information System (INIS)

Theoretical prediction of nuclear masses is analyzed as a pattern recognition problem on the N-Z plane. A global pattern is observed by plotting the differences between measured masses and Liquid Drop Model (LDM) predictions. After unfolding the data by removing the smooth LDM mass contributions, the remaining microscopic effects have proved difficult to model, although they display a striking pattern. These deviations carry information related to shell closures, nuc]ear deformation and the residual nuclear interactions. In the present work the more than 2000 known nuclear masses are studied as an array in the N-Z plane viewed through a mask, behind which the approximately 7000 unknown unstable nuclei that can exist between the proton and neutron drip lines are hidden. We show here that employing a Fourier transform deconvolution method these by masses can be predicted with similar accuracy than standard methods. We believe that a more general approach needs to be ...

208

News from the world; Echos du monde  

Energy Technology Data Exchange (ETDEWEB)

This document gathers a series of very short articles concerning nuclear industry around the world. Areva company is investing 30 million euros in its Chalon-Saint-Marcel plant, it is the consequence of the extension of service life of nuclear power plants in the Usa. Areva holds 40% of the American market concerning the replacement of steam generators and 50% of that concerning the replacement of closure heads. The Obrigheim nuclear power plant was definitely closed down on may 2004, this decommissioning is a step forward in the German policy of progressively stepping out of nuclear energy. Chinese authorities are willing to construct 40 nuclear reactors in 15 years, despite that, the contribution of nuclear energy to the generation of electricity will reach only 4% in 2020. In 2007 Cea will begin the construction works of a new research reactor (Jules Horowitz reactor) in the Cadarache site. Prices of the yellow cake have been going up during the last years: from ...

2005-04-01

209

Mine stability evaluation of panel 1 during waste emplacement operations at WIPP  

Energy Technology Data Exchange (ETDEWEB)

The specific objectives of the work were defined by the Environmental Evaluation Group (EEG) as follows: (1) assess the stability of panel 1 during the proposed operation of waste emplacement; (2) estimate the amount of time before room closure would be expected to transfer rock loads to the waste packages. The work consisted of (1) an analysis of geotechnical data and a review of the Department of Energy`s (DOE) plans for waste emplacement in panel 1, (2) an evaluation of ground conditions based on data analysis and observations of changes in ground conditions since the first evaluation in 1993 (USBM 1993), and (3) preparation of a report and presentation of the results to EEG staff. Excluded from this study are radiological safety issues and policies. The study is based on data provided by DOE and Westinghouse Electric Corporation (operator of the site) and conversations with DOE and Westinghouse personnel. MTI cannot independently verify the accuracy of the data ...

1998-07-01

210

Integral severe accident analysis of light water nuclear power plants by IMPACT-SAMPSON code  

Energy Technology Data Exchange (ETDEWEB)

The NUclear Power Engineering Corporation (NUPEC) has developed IMPACT-SAMPSON code to analyze integral behavior of light water nuclear power plants under severe accident conditions. IMPACT-SAMPSON's distinguishing features include interconnected hierarchical modules and mechanistic models covering a wide spectrum of scenarios ranging from normal operation to severe accident events, and high-speed simulation on parallel processing computers. The integral plant behaviors of typical PWR and BWR under severe accident conditions have been analyzed with the IMPACT-SAMPSON code. The PWR plant analyzed was the three-loop, steel-dry containment type with 2,440 MWt. The AE accident scenario was supposed, that is, LOCA by 6-inch hot leg failure followed by accumulated water injection, but no ECCS and containment spray activation. The BWR plant analyzed was the 3,293 MWt BWR-5, Mark-II containment type. The TQUV accident scenario was supposed, that is, reactor scram by MSIV ...

2003-07-01

211

Incorporation of Reaction Kinetics into a Multiphase, Hydrodynamic Model of a Fischer Tropsch Slurry Bubble Column Reactor  

Energy Technology Data Exchange (ETDEWEB)

This paper describes the development of a computational multiphase fluid dynamics (CMFD) model of the Fischer Tropsch (FT) process in a Slurry Bubble Column Reactor (SBCR). The CMFD model is fundamentally based which allows it to be applied to different industrial processes and reactor geometries. The NPHASE CMFD solver [1] is used as the robust computational platform. Results from the CMFD model include gas distribution, species concentration profiles, and local temperatures within the SBCR. This type of model can provide valuable information for process design, operations and troubleshooting of FT plants. An ensemble-averaged, turbulent, multi-fluid solution algorithm for the multiphase, reacting flow with heat transfer was employed. Mechanistic models applicable to churn turbulent flow have been developed to provide a fundamentally based closure set for the equations. In this four-field model formulation, two of the fields are used to track the gas phase (i.e., ...

2008-11-01

212

Imaging magnetic domain structure in sub-500 nm thin film elements  

Energy Technology Data Exchange (ETDEWEB)

Magnetic imaging in the transmission electron microscope (TEM) has been used to examine submicron elements with the aim of discovering down to what element size complex domain patterns can form. The elements were squares, circles, triangles, and pentagons in the size range 100{endash}500 nm and were made from 36 nm Co films or 8 nm Ni{sub 80}Fe{sub 20} (NiFe) with in-plane magnetization. The magnetic domain structures in these elements were imaged at high resolution using the differential phase contrast imaging mode in a TEM. Nonuniform magnetization structures were seen in the images. Vortices were present at remanence in all shapes of 36-nm-thick Co elements down to 100 nm size and in circular NiFe elements down to 116 nm diameter. Triangular NiFe elements did not have a vortex state at remanence, instead the magnetization curved round within the element but did not achieve complete flux closure. In simulations of square and circular NiFe elements, it was found ...

2001-06-01

213

Hydrocarbon potential of offshore South Florida basin  

Energy Technology Data Exchange (ETDEWEB)

The results of an extensive, detailed geologic and geophysical evaluation of the offshore South Florida basin show this area to have considerable hydrocarbon exploration potential. Geophysical mapping on six key horizons identified numerous structural closures at Dollar Bay through Bone Island mapping levels. Geologic evaluation indicated at least four viable potential reservoir horizons, including the Sunniland formation - the main producing unit onshore in what is called the Sunniland trend. Mature, organic rich carbonate source rocks are found in several stratigraphic intervals throughout the basin, and extensively developed seals consisting of micritic limestones and anhydrites are also common in the stratigraphic section. All the critical factors for hydrocarbon accumulation - source, reservoir, trap, and seal - appear to be present in the offshore Pulley ridge area of the South Florida basin. Using high-resolution seismic data, additional evaluation of land ...

1986-05-01

214

Groundwater quality assessment plan for single-shell tank waste management Area U at the Hanford Site  

Energy Technology Data Exchange (ETDEWEB)

Waste Management Area U (WMA U) includes the U Tank Farm, is currently regulated under RCRA interim-status regulations, and is scheduled for closure probably post-2030. Groundwater monitoring has been under an evaluation program that compared general contaminant indicator parameters from downgradient wells to background values established from upgradient wells. One of the indicator parameters, specific conductance, exceeded its background value in one downgradient well triggering a change from detection monitoring to a groundwater quality assessment program. The objective of the first phase of this assessment program is to determine whether the increased concentrations of nitrate and chromium in groundwater are from WMA U or from an upgradient source. Based on the results of the first determination, if WMA U is not the source of contamination, then the site will revert to detection monitoring. If WMA U is the source, then a second part of the groundwater quality ...

2000-03-21

215

Ground-state properties of exotic nuclei near Z=40 in the relativistic mean-field theory  

International Nuclear Information System (INIS)

Study of the ground-state properties of Kr, Sr and Zr isotopes has been performed in the framework of the relativistic mean-field (RMF) theory using the recently proposed relativistic parameter set NL-SH. It is shown that the RMF theory provides an unified and excellent description of the binding energies, isotope shifts and deformation properties of nuclei over a large range of isospin in the Z=40 region. It is observed that the RMF theory with the force NL-SH is able to describe the anomalous kinks in isotope shifts in Kr and Sr nuclei, the problem which has hitherto remained unresolved. This is in contrast with the density-dependent Skyrme-Hartree-Fock approach which does not reproduce the behaviour of the isotope shifts about shell closure. On the Zr chain we predict that the isotope shifts exhibit a trend similar to that of the Kr and Sr nuclei. The RMF theory also predicts shape coexistence in heavy Sr isotopes. Several dramatic shape transitions in the ...

216

Generalized Gas Dynamic Equations for Microflows  

CERN Document Server

n an early approach, we proposed a kinetic model with multiple translational temperature [K. Xu, H. Liu and J. Jiang, Phys. Fluids {\\bf 19}, 016101 (2007)], to simulate non-equilibrium flows. In this paper, instead of using three temperatures in $x-$, $y-$, and $z$-directions, we are going to further define the translational temperature as a second-order symmetric tensor. Based on a multiple stage BGK-type collision model and the Chapman-Enskog expansion, the corresponding macroscopic gas dynamics equations in three-dimensional space will be derived. The zeroth-order expansion gives the 10 moment closure equations of Levermore [C.D. Levermore, J. Stat. Phys {\\bf 83}, pp.1021 (1996)]. To the 1st-order expansion, the derived gas dynamic equations can be considered as a regularization of Levermore's 10 moments equations. The new gas dynamic equations have the same structure as the Navier-Stokes equations, but the stress strain relationship in the Navier-Stokes ...

2008-01-01

217

Fuel cycle options and sustainability for new nuclear build in the UK  

International Nuclear Information System (INIS)

After a long period of stagnation in the UK, Europe and the USA, there is now a real expectation that new nuclear plants will be under construction shortly. Several factors have contributed to this change of position in the UK: the growing realisation that effective action is needed to offset greenhouse gas emissions; higher prices for fossil fuels; increasing reliance on overseas supplies of oil and gas; the limitations of wind and wave power and distribution; security of supply; the gradual realisation in the deregulated electricity generation market that nuclear power is competitive and the pending closure of most of the UK's nuclear fleet within less than 15 years. All these factors have led to a reversal of the UK Government's attitude to nuclear power, which has now ruled in favour of allowing a new generation of nuclear plants being built. This paper summarises some of the arguments that have led to this decision and the ramifications of it. In particular, ...

2008-09-14

218

Fluid dynamics analysis of a Ranque-Hilsch vortex tube  

International Nuclear Information System (INIS)

Fluid dynamic analysis of a commercial, counter-flow Ranque-Hilsch Vortex Tube (Rh vt), Ex air 25 s cfm, has been performed in this work both experimentally and numerically; in particular Rh vt cooling power and temperature separation performances have been tested in both direct cooling employment (jet impingement) and indirect cooling employment (supplying cold plates). Experimental techniques, used in this work, revealed several difficulties to produce detailed information about velocity and temperature fields inside the tube and at both the exits. Hence numerical simulation of the flow inside the tube has been conducted using the commercial Cfd code Fluent 6.3.26. Compressible, turbulent, high swirling flow inside Rh vt has been simulated by using both Rans and Les approaches. In particular several turbulence closures have been used in the Rans simulations and results have been compared with Les ones. Large Eddy Simulations have been performed using Smagorinsky ...

2008-05-01

219

Effect of drought and abscisic acid application on the osmotic adjustment of four wheat cultivars  

International Nuclear Information System (INIS)

The accumulation of osmolytes in leaf tissues and the abscisic acid-induced stomatal closure are well-recognized mechanisms associated with drought tolerance in crop plants. We determine the response in terms of osmotic potential and the contents of leaf proline, glycine betaine and soluble sugar at booting and grain filling stages of four wheat (Triticum aestivum L.) cultivars to drought and exogenously applied abscisic acid (ABA) in a pot study. Leaf sample were collected 3, 6 and 9 days after drought induction and at 48 and 72 h of re-watering (recovery). Marked decreases in osmotic potential associated with the accumulation of proline, glycine betaine and soluble sugars occurred under conditions of drought stress Accession 011320 was most sensitive to drought and showed the largest decrease in osmotic potential and least accumulation of proline, sugar and glycine betaine The inhibitory effects of drought stress were ameliorated by exogenous application of ABA. ...

2010-02-01

220

Demonstration of innovative monitoring technologies at the Savannah River Integrated Demonstration Site  

Energy Technology Data Exchange (ETDEWEB)

The Department of Energy`s Office of Technology Development initiated an Integrated Demonstration Program at the Savannah River Site in 1989. The objective of this program is to develop, demonstrate, and evaluate innovative technologies that can improve present-day environmental restoration methods. The Integrated Demonstration Program at SRS is entitled ``Cleanup of Organics in Soils and Groundwater at Non-Arid Sites.`` New technologies in the areas of drilling, characterization, monitoring, and remediation are being demonstrated and evaluated for their technical performance and cost effectiveness in comparison with baseline technologies. Present site characterization and monitoring methods are costly, time-consuming, overly invasive, and often imprecise. Better technologies are required to accurately describe the subsurface geophysical and geochemical features of a site and the nature and extent of contamination. More efficient, nonintrusive characterization and monitoring techniques ...

1993-12-31

221

Crack tip oxidation of a superalloy in molten nitrate salt  

Energy Technology Data Exchange (ETDEWEB)

Alloy 800 has been proposed for use in the receiver tube panel arrays of advanced solar central receiver (SCR) designs. In this application the alloy will be exposed to a molten mixture of sodium and potassium nitrate salts at temperatures ranging up to approximately 600/sup 0/C While these salts are routinely used in a variety of applications including metal heat treating and process heat transfer, common industrial experience has been limited to maximum temperatures of 400/sup 0/C - 450/sup 0/C. There is, therefore, considerable interest in the compatibility of these salts with containment alloys at the higher temperatures associated with SCR designs. Additionally, the containment alloy may be subject to thermally induced fatigue damage resulting from intermittent cloud cover and diurnal cycling. Previous work has found that slower near-threshold fatigue crack growth rates (FCGR) in Alloy 800 result when it is tested in molten nitrate salt at 600/sup 0/C (relative to air). This ...

1983-04-01

222

Consistency of the phenomenological theories of wave-type heat transport with the hydrodynamics of a phonon gas  

International Nuclear Information System (INIS)

Various phenomenological theories of wave-type heat transport, which can be interpreted as the models of an isotropic rigid heat conductor with an internal vector state variable, have been proposed in the literature with the objective to describe the second sound propagation in dielectric crystals. The aim of this paper is to analyze the relation between these phenomenological approaches and the phonon gas hydrodynamics. The four-moment phonon gas hydrodynamics based on the maximum entropy closure of the moment equations with nonlinear isotropic phonon dispersion relation is considered for this purpose. We reformulate the equations of this hydrodynamics in terms of energy and quasi-momentum as the primitive fields and subsequently demonstrate that, from the macroscopic point of view, they can be understood as describing the reference model of an isotropic rigid heat conductor with quasi-momentum playing the role of the internal vector state variable. This model is ...

2010-09-24

223

CT appearances of unilateral cleft palate 20 years after bone graft surgery  

Energy Technology Data Exchange (ETDEWEB)

Purpose: To describe CT appearances in patients with unilateral cleft lip and palate (CLP) 20 years after bone graft surgery. Material and Methods: Eighteen consecutive patients with unilateral CLP were examined. All patients had been treated with primary closure, both in infancy and early childhood, supplemented with bone grafting at the age of around 10 years. The CT examination of the upper jaw included a dental CT program. The CT appearances of the cleft side were compared with those of the untreated non-cleft side. Results: Abnormal CT appearances included skew nasal aperture (n=17), nasal septal deviation (n=17), low floor of nasal aperture (n=15) at or towards the cleft side, and deviation of anterior nasal spine towards the non-cleft side (n=18). The posterior part of the bone cleft was visible in all patients, and the dental arch was V-shaped in 8. Conclusion: Although adherence to the present treatment protocol is considered to give satisfactory ...

2002-11-01

224

CT appearances of unilateral cleft palate 20 years after bone graft surgery  

International Nuclear Information System (INIS)

Purpose: To describe CT appearances in patients with unilateral cleft lip and palate (CLP) 20 years after bone graft surgery. Material and Methods: Eighteen consecutive patients with unilateral CLP were examined. All patients had been treated with primary closure, both in infancy and early childhood, supplemented with bone grafting at the age of around 10 years. The CT examination of the upper jaw included a dental CT program. The CT appearances of the cleft side were compared with those of the untreated non-cleft side. Results: Abnormal CT appearances included skew nasal aperture (n=17), nasal septal deviation (n=17), low floor of nasal aperture (n=15) at or towards the cleft side, and deviation of anterior nasal spine towards the non-cleft side (n=18). The posterior part of the bone cleft was visible in all patients, and the dental arch was V-shaped in 8. Conclusion: Although adherence to the present treatment protocol is considered to give satisfactory ...

2002-11-01

225

BWR containment vessel drywell head bolt de-tensioning during noble metal chemical application  

Energy Technology Data Exchange (ETDEWEB)

Implementation of Noble Metal Chemical Application (NMCA) in a Boiling Water Reactor (BWR) requires injection of a noble metal compound while the reactor is idle at hot shutdown conditions. In order to minimize outage time, utilities are very pro-actively finding ways to reduce the number of critical path tasks. One of these tasks is to remove some containment vessel drywell head bolts during the NMCA idle time. This, thereby, saves the utilities outage time, or they can perform other tasks as desired. Using design basis conditions and state-of-the-art analytical techniques, detailed finite element stress analyses of the closure region are performed. Two acceptance criteria are evaluated. The first is that contained within Section III of the ASME Code for allowable stresses. The second relates to leak tightness, i.e., with bolt removal the joint must still remain leak tight. This paper describes the activities performed to justify bolt removal during the noble ...

2001-07-01

226

Accident impact of a spent fuel dry storage package: Analytical/experimental comparison  

Energy Technology Data Exchange (ETDEWEB)

Packages used for the storage and transportation of radioactive spent fuel must demonstrate the ability to withstand severe impact scenarios such as those established by the Atomic Energy Control Board (AECB) in Canada and the International Atomic Energy Agency (IAEA). One such package is the Dry Storage Container (DSC) for transporting and storing used fuel. The DSC model is comprised of several interactive components with materials such as high density concrete and polyurethane foam. To accurately model these materials, experimental studies were performed in order to provide material properties for the in-house finite element analysis code used. Structural assessments of the package design subject to postulated impact scenarios included a 9 meter center of gravity over corner drop, a 1 meter pin drop over the welded lid closure and a 1 meter center of gravity over lid pin drop. Simulations were carried out using full scale analytical models with validation by a ...

1996-12-31

227

A new visitor centre for CMS  

CERN Multimedia

At the inauguration of the new CMS visitor centre. The CMS experiment inaugurated a new visitor centre at its Cessy site on 14 June. This will allow the thousands of people who come to CERN each year to follow the construction of one the Laboratory's flagship experiments first-hand. CERN receives over 20,000 visitors each year. Until recently, many of them were taken on a guided tour of one of the LEP experiments. With the closure of LEP, however, trips underground are no longer possible, and the Visits' Service has put in place a number of other itineraries (Bulletin 46/2000). Since the CMS detector will be almost entirely constructed in a surface hall, it is now taking a big share of the limelight. The CMS visitor centre has been built on a platform overlooking CMS construction. It contains a set of clear descriptive posters describing the experiment, along with a video projection showing animations and movies about CMS construction. In the coming weeks, a ...

2001-01-01

228

Comprehensive Approaches to Multiphase Flows in Geophysics - Application to nonisothermal, nonhomogenous, unsteady, large-scale, turbulent dusty clouds I. Hydrodynamic and Thermodynamic RANS and LES Models  

Energy Technology Data Exchange (ETDEWEB)

The objective of this manuscript is to fully derive a geophysical multiphase model able to ''accommodate'' different multiphase turbulence approaches; viz., the Reynolds Averaged Navier-Stokes (RANS), the Large Eddy Simulation (LES), or hybrid RANSLES. This manuscript is the first part of a larger geophysical multiphase project--lead by LANL--that aims to develop comprehensive modeling tools for large-scale, atmospheric, transient-buoyancy dusty jets and plume (e.g., plinian clouds, nuclear ''mushrooms'', ''supercell'' forest fire plumes) and for boundary-dominated geophysical multiphase gravity currents (e.g., dusty surges, diluted pyroclastic flows, dusty gravity currents in street canyons). LES is a partially deterministic approach constructed on either a spatial- or a temporal-separation between the large and small scales of the flow, whereas RANS is an entirely probabilistic ...

2005-09-05

229

Sensor test facilities and capabilities at the Nevada Test Site  

Energy Technology Data Exchange (ETDEWEB)

Sandia National Laboratories has recently developed two major field test capabilities for unattended ground sensor systems at the Department of energy`s Nevada Test Site (NTS). The first capability utilizes the NTS large area, varied terrain, and intrasite communications systems for testing sensors for detecting and tracking vehicular traffic. Sensor and ground truth data can be collected at either of two secure control centers. This system also includes an automated ground truth capability that consists of differential Global Positioning Satellite (GPS) receivers on test vehicles and live TV coverage of critical road sections. Finally there is a high-speed, secure computer network link between the control centers and the Air Force`s Theater Air Command and Control Simulation Facility in Albuquerque NM. The second capability is Bunker 2-300. It is a facility for evaluating advanced sensor systems for monitoring activities in underground ...

1996-12-31

230

New neutron simulation capabilities provided by the Sandia Pulse Reactor (SPR-III) and the Upgraded Annular Core Pulse Reactor (ACPR)  

Science.gov (United States)

The paper briefly describes the nuclear reactor facilities at Sandia Laboratories which are used for simulating nuclear weapon produced neutron environments. These reactor facilities are used principally in support of continuing R and D programs for the Department of Energy/Office of Military Application (DOE/OMA) in studying the effects of radiation on nuclear weapon systems and components. As such, the reactors are available to DOE and DOD agencies and their contractors responsible for the radiation hardening of advanced nuclear weapon systems. Emphasis is placed upon two new reactor simulation sources; the Sandia Pulse Reactor-III (SPR-III) Facility which enhances the neutron exposure volume capabilities over those presently available with the existing SPR-II Facility, and the Upgraded Annular Core Pulse Reactor (ACPR) Facility which enhances the neutron exposure capabilities ...

1978-07-01

231

Maintenance implementation plan for the B Plant/WESF. Revision 4  

Energy Technology Data Exchange (ETDEWEB)

This Maintenance Implementation Plan (MIP) has been developed for maintenance functions associated with the B Plant/WESF (Waste Encapsulation Storage Facility) complex. The objective of this plan is to provide baseline information for establishing and identifying 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 B Plant/WESF. The B Plant WESF facility complex consists of three main facilities and several support structures located in the 200 East Area of the Hanford site. B Plant is a transition facility that is required to ensure safe storage and management of WESF (operating facility) cesium and strontium capsules. B Plant/WESF also contains substantial radiological inventory from previous campaigns. ...

1996-01-01

232

Hazard analysis for 300 Area N Reactor Fuel Fabrication and Storage Facilty  

Energy Technology Data Exchange (ETDEWEB)

This hazard analysis (HA) has been prepared for the 300 Area N Reactor Fuel Fabrication and Storage Facility (Facility), in compliance with the requirements of Westinghouse Hanford Company (Westinghouse Hanford) controlled manual WHC-CM-4-46, Nonreactor Facility Safety Analysis Manual, and to the direction of WHC-IP-0690, Safety Analysis and Regulation Desk Instructions, (WHC 1992). An HA identifies potentially hazardous conditions in a facility and the associated potential accident scenarios. Unlike the Facility hazard classification documented in WHC-SD-NR-HC-004, Hazard Classification for 300 Area N Reactor Fuel Fabrication and Storage Facility, (Huang 1993), which is based on unmitigated consequences, credit is taken in an HA for administrative controls or engineered safety features planned or in place. The HA is the foundation for the accident analysis. The ...

1994-01-25

233

Utilization of the HANARO  

Energy Technology Data Exchange (ETDEWEB)

Radioisotope facilities were operated to support research, development and production of radioisotopes. Irradiation facilities were operated to offer irradiation service to the clients. Even though intensive periodical checks and some essential maintenance had been carried out the results of RI facility maintenance seemed to be not much satisfactory due mainly to the shortage of skilled manpower and maintenance expenses. High intensity {gamma} irradiator was normally operated 426 times for overall 3,440 hrs, and the low intensity {gamma} irradiator was operated 157 times for overall 11,092 hrs, respectively. (author)

1998-12-01

234

Universal Basic Education in Nigeria: Availability of Schools' Infrastructure for Effective Program Implementation  

Science.gov (United States)

This paper examines the availability and adequacy of schools' infrastructural facilities for implementation of the Universal Basic Education program in Nigeria. Adopting the "ex post facto" design, the researchers used existing school data on physical facilities, including a survey of key stakeholders in the education sector. Data analysed revealed inadequacy of physical facilities for effective implementation of the UBE program. It was accordingly recommended that government at the national, state and local levels show better commitment to the implementation of the Universal Basic Education program. (Contains 3 figures and 4 tables.)

2008-02-01

235

Summary on experimental facilities and future developments at SINQ  

Energy Technology Data Exchange (ETDEWEB)

With 13 experimental facilities under construction to become available during the first year of SINQ operation, a nearly complete suite of options for users will be made available to carry out research with neutrons at PSI. Three more facilities are under design and will come on line somewhat later. To complete the suite, three more specialized instruments are being evaluated. SINQ being a novel neutron source concept, significant scope for improvement is also seen on the source side. It is a major goal of PSI to exploit these opportunities and to make - among others - use of neutron instruments to carry out the necessary research. (author) 9 figs., 1 tab., 11 refs.

1996-11-01

236

Statement of Work (SOW) for services provided by the Waste Sampling and Characterization Facility for the Effluent and Environmental Monitoring Program during calendar year 1998  

Energy Technology Data Exchange (ETDEWEB)

This document defines the services the Waste Sampling and Characterization Facility (WSCF) shall provide the Effluent and Environmental Monitoring Program (EEM) throughout the calendar year for analysis. The purpose of the EEM Program is to monitor liquid and gaseous effluents, and the environment immediately around the facilities which may contain radioactive and hazardous materials. Monitoring data are collected, evaluated, and reported to determine their degree of compliance with applicable federal and state regulations and permits.

1998-10-22

237

Risk evaluation system for facility safeguards and security planning  

International Nuclear Information System (INIS)

The Risk Evaluation System (RES) is an integrated approach to determining safeguards and security effectiveness and risk. RES combines the planning and technical analysis into a format that promotes an orderly development of protection strategies, planning assumptions, facility targets, vulnerability and risk determination, enhancement planning, and implementation. In addition, the RES computer database program enhances the capability of the analyst to perform a risk evaluation of the facility. The computer database is menu driven using data input screens and contains an algorithm for determining the probability of adversary defeat and risk. Also, base case and adjusted risk data records can be maintained and accessed easily.

1987-07-12

238

Radiological performance assessment for the E-Area Vaults Disposal Facility  

Energy Technology Data Exchange (ETDEWEB)

This report is the first revision to ``Radiological Performance Assessment for the E-Area Vaults Disposal Facility, Revision 0'', which was issued in April 1994 and received conditional DOE approval in September 1994. The title of this report has been changed to conform to the current name of the facility. The revision incorporates improved groundwater modeling methodology, which includes a large data base of site specific geotechnical data, and special Analyses on disposal of cement-based wasteforms and naval wastes, issued after publication of Revision 0.

2000-04-11

239

Neutron radiography at the University of Michigan's Phoenix Memorial Laboratory  

International Nuclear Information System (INIS)

Real-time neutron radiography (RTNR) is rapidly becoming a valuable tool for nondestructive testing and basic research with a wide variety of applications. The Phoenix Memorial Laboratory (PML) at the University of Michigan has developed an RTNR facility and has been using this facility to study several phenomena of interest to researchers in many areas. These phenomena include imaging of the internal fluid flow in gas turbine engine nozzles and coking and debris deposition in several gas turbine nozzles. This paper presents a summary of the technique and facilities involved in these applications.

1990-06-10

240

Maintenance implementation plan for T Plant. Revision 2  

Energy Technology Data Exchange (ETDEWEB)

This document is a Maintenance Implementation Plan (MIP) for the T Plant Facility complex located in the 200 West Area of the Hanford Reservation in Washington state. This plan has been developed to provide a disciplined approach to maintenance functions and to describe how the T Plant facility will implement and comply with the regulations according to US DOE order 4330.4B, entitled Maintenance Management Program, Chapter 2.0 {open_quotes}Nuclear Facilities{close_quotes}. Physical structures, systems, processes, as well as all associated equipment specifically assigned to these groups are included in the MIP.

1995-05-01

241

Low-level and transuranic waste transportation, disposal, and facility decommissioning cost sensitivity analysis  

Energy Technology Data Exchange (ETDEWEB)

The Systems Design Study (SDS) identified technologies available for the remediation of low-level and transuranic waste stored at the Radioactive Waste Management Complex's Subsurface Disposal Area at the Idaho National Engineering Laboratory. The SDS study intentionally omitted the costs of transportation and disposal of the processed waste and the cost of decommissioning the processing facility. This report provides a follow-on analysis of the SDS to explore the basis for life-cycle cost segments of transportation, disposal, and facility decommissioning; to determine the sensitivity of the cost segments; and to quantify the life-cycle costs of the 10 ex situ concepts of the Systems Design Study.

1992-05-01

242

Low-level and transuranic waste transportation, disposal, and facility decommissioning cost sensitivity analysis  

Energy Technology Data Exchange (ETDEWEB)

The Systems Design Study (SDS) identified technologies available for the remediation of low-level and transuranic waste stored at the Radioactive Waste Management Complex`s Subsurface Disposal Area at the Idaho National Engineering Laboratory. The SDS study intentionally omitted the costs of transportation and disposal of the processed waste and the cost of decommissioning the processing facility. This report provides a follow-on analysis of the SDS to explore the basis for life-cycle cost segments of transportation, disposal, and facility decommissioning; to determine the sensitivity of the cost segments; and to quantify the life-cycle costs of the 10 ex situ concepts of the Systems Design Study.

1992-05-01

243

Interim explosives detection alternatives  

Energy Technology Data Exchange (ETDEWEB)

There is a general concern with insiders smuggling bomb quantities of explosives into sensitive facilities such as nuclear facilities. At this time, there is no single explosives detection device that is suitable for monitoring personnel and their packages for explosives in an operational facility environment. However, there are techniques combining available commercial technologies with procedures and threat analysis that can significantly increase the insiders risk and reduce the population of adversaries. This paper describes the available applicable explosives detection technologies and discusses the techniques that could be implemented on an interim basis. It is important that these techniques be considered, so that some interim level of security against the explosives threat can be established until more sophisticated equipment that is under development becomes available.

1991-01-01

244

Initial electron-beam characterizations for the Los Alamos APEX Facility  

Energy Technology Data Exchange (ETDEWEB)

The ongoing upgrade of the Los Alamos Free-Electron Laser (FEL) Facility involves the addition of a photoelectric injector (PEI) and acceleration capability to about 40 MeV. The electron-beam and high-speed diagnostics provide key measurements of charge, beam position and profile, divergence emittance, energy (centroid, spread, slew, and extraction efficiency), micropulse duration, and phase stability. Preliminary results on the facility include optical transition radiation interferometer measurements of divergence (1 to 2 mrad), FEL extraction efficiency (0.6 {plus minus} 0.2%), and drive laser phase stability (< 2 ps (rms)). 10 refs.

1991-01-01

245

Initial electron-beam characterizations for the Los Alamos APEX Facility  

Energy Technology Data Exchange (ETDEWEB)

The ongoing upgrade of the Los Alamos Free-Electron Laser (FEL) Facility involves the addition of a photoelectric injector (PEI) and acceleration capability to about 40 MeV. The electron-beam and high-speed diagnostics provide key measurements of charge, beam position and profile, divergence emittance, energy (centroid, spread, slew, and extraction efficiency), micropulse duration, and phase stability. Preliminary results on the facility include optical transition radiation interferometer measurements of divergence (1 to 2 mrad), FEL extraction efficiency (0.6 {plus_minus} 0.2%), and drive laser phase stability (< 2 ps [rms]). 10 refs.

1991-12-31

246

Imaging Automation and Volume Tomographic Visualization at Texas Neutron Imaging Facility  

Energy Technology Data Exchange (ETDEWEB)

A thermal neutron imaging facility for real-time neutron radiography and computed tomography has been developed at the University of Texas reactor. The facility produced good-quality radiographs and two-dimensional tomograms. Further developments have been recently accomplished. A computer software has been developed to automate and expedite the data acquisition and reconstruction processes. Volume tomographic visualization using Interactive Data Language (IDL) software has been demonstrated and will be further developed. Volume tomography provides the additional flexibility of producing slices of the object using software and thus avoids redoing the measurements.

1999-11-14

247

ICDF Complex Operations Waste Management Plan  

Science.gov (United States)

This Waste Management Plan functions as a management and planning tool for managing waste streams generated as a result of operations at the Idaho CERCLA Disposal Facility (ICDF) Complex. The waste management activities described in this plan support the selected remedy presented in the Waste Area Group 3, Operable Unit 3-13 Final Record of Decision for the operation of the Idaho CERCLA Disposal Facility Complex. This plan identifies the types of waste that are anticipated during operations at the Idaho CERCLA Disposal Facility Complex. In addition, this plan presents management strategies and disposition for these anticipated waste streams.

2006-12-01

248

High Exposure Facility Technical Description  

Energy Technology Data Exchange (ETDEWEB)

The High Exposure Facility is a collimated high-level gamma irradiator that is located in the basement of the 318 building. It was custom developed by PNNL back in 1982 to meet the needs for high range radiological instrument calibrations and dosimeter irradiations. At the time no commercially available product existed that could create exposure rates up to 20,000 R/h. This document is intended to pass on the design criteria that was employed to create this unique facility, while maintaining compliance with ANSI N543-1974, "General Safety Standard for Installations Using Non-Medical X-Ray and Sealed Gamma-Ray Sources, Energies up to 10 MeV."

2008-02-12

249

Gamma Radiation Detectors of the TA-55 Waste Line Monitoring System  

Energy Technology Data Exchange (ETDEWEB)

This report covers the gamma detectors, measurement instrumentation, and testing results of a system developed at Los Alamos National Laboratory. This system monitors the process liquid waste streams at the Plutonium Facility (TA-55) for the presence of radioactive contamination. The detectors are at various points on the acid, caustic, and industrial waste lines. Two of the detectors are on the sanitary sewer lines from the facility. A custom interface unit associated with these two detectors furnishes the facility operation center with a notification of the detection of material. All of the detectors furnish measurement information to a central computer system for storage and trending.

1999-06-01

250

Facility Safety Plan B360 Complex Biohazardous Operations CMLS-412r0  

Science.gov (United States)

This Addendum to the Facility Safety Plan (FSP) 360 Complex describes the safety requirements for the safe conduct of all biohazardous research operations in all buildings within the 360 complex program areas. These requirements include all the responsibilities and authorities of building personnel, operational hazards, and environmental concerns and their controls. In addition, this Addendum prescribes facility-specific training requirements and emergency controls, as well as maintenance and quality assurance requirements for ES&H-related building systems.

2007-01-08

251

Department of Nuclear Safety Research and Nuclear Facilities annual report 1995  

Energy Technology Data Exchange (ETDEWEB)

The report presents a summary of the work of the Department of Nuclear Safety Research and Nuclear Facilities in 1995. The department`s research and development activities are organized in three research programmes: Radiation Protection, Reactor Safety, and Radioanalytical Chemistry. The nuclear facilities operated by the department include the Research Reactor DR3, the Isotope Laboratory, the Waste Treatment Plant, and the Educational Reactor DR1. Lists of staff and publications are included together with a summary of the staff`s participation in national and international committees. (au) 5 tabs., 21 ills.

1996-03-01

252

An overview of FFTF [Fast Flux Test Facility] contributions to Liquid Metal Reactor Safety  

International Nuclear Information System (INIS)

The Fast Flux Test Facility has provided a very useful framework for testing the advances in Liquid Metal Reactor Safety Technology. During the licensing phase, the switch from a nonmechanistic bounding technique to the mechanistic approach was developed and implemented. During the operational phase, the consideration of new tests and core configurations led to use of the anticipated-transients-without-scram approach for beyond design basis events and the move towards passive safety. The future role of the Fast Flux Test Facility may involve additional passive safety and waste transmutation tests. 26 refs.

1990-11-11

253

Wood energy in Alaska--case study evaluations of selected facilities  

Science.gov (United States)

Sep 1, 2011 ... Recent wildfires in interior Alaska have left substantial volumes of burned timber, potentially usable for biomass energy. Motivated,in part, by ...

256

United States Domestic Research Reactor Infrastrucutre TRIGA Reactor Fuel Support  

Energy Technology Data Exchange (ETDEWEB)

The United State Domestic Research Reactor Infrastructure Program at the Idaho National Laboratory manages and provides project management, technical, quality engineering, quality inspection and nuclear material support for the United States Department of Energy sponsored University Reactor Fuels Program. This program provides fresh, unirradiated nuclear fuel to Domestic University Research Reactor Facilities and is responsible for the return of the DOE-owned, irradiated nuclear fuel over the life of the program. This presentation will introduce the program management team, the universities supported by the program, the status of the program and focus on the return process of irradiated nuclear fuel for long term storage at DOE managed receipt facilities. It will include lessons learned from research reactor facilities that have successfully shipped spent fuel elements to DOE receipt facilities.

2011-03-01

257

Toxicity and Bioavailability of Metals in the Missouri River ...  

Science.gov (United States)

contaminated groundwater from the ASARCO metals refining facility ... ditch or creek crossing the ASARCO property at its northern end) and one at its ...

258

The duke XUV FEL storage ring facility  

Energy Technology Data Exchange (ETDEWEB)

In this paper we present status and developments of the Duke storage ring facility. The Duke storage ring facility provides the unique combination of phase-locked light sources ranging from high power OK-4 XUV FEL to quasimonochromatic {gamma}-ray beam and IR/X-ray spontaneous radiation. The XUV OK-4 FEL, which is collaborative project with BlNP, Novosibirsk, is in operation since November, 1996. The OK-4 UV FEL is also used for production of nearly monochromatic {gamma}-ray s with tunable energy. We present the results of UV lasing with the OK4 FEL and selected results of its applications. We will discuss our future plans for extension of this source and status of the construction of dedicated used facility adjacent to the FEL building. (author)

1998-11-01

259

The PANDA facility and first test results  

International Nuclear Information System (INIS)

The PANDA test facility at the Paul Scherrer Institute is used to study the long-term performance of the Simplified Boiling Water Reactor's passive containment cooling system. The PANDA tests demonstrate performance on a larger scale than previous tests and examine the effects of any non-uniform spatial distributions of steam and non-condensable gases in the system. The facility is in 1:1 vertical scale and 1:25 scale for volume, power etc. Extensive facility characterization tests and steady-state passive containment condenser performance tests are presented. The results of the base case test of a series of transient system behaviour tests are reviewed. The first PANDA tests exhibited reproducibility, and indicated that the Simplified Boiling Water Reactor's containment is likely to be favorably responsive and highly robust to changes in the thermal transport patterns. (orig.).

261

Test Planning Guide for ASF Facilities  

Science.gov (United States)

15 to 75% of the gun barrel diameter. Similarly, model masses typically vary from 0.01 to 100 .... taining acceptable levels of gun barrel erosion. The ...

262

Summary of NSF Workshop on Research Opportunities in Manufacturing in the Process Industries  

Science.gov (United States)

... and facilities; the physical processing of materials into products; and processes associated with ... area of bulk silicon prod! uction as wafer material has been omitted, in keeping with current ...

263

Status of PACTEL facility  

Energy Technology Data Exchange (ETDEWEB)

Since 1976, the Nuclear Engineering Laboratory of the Technical Research Centre of Finland and Lappeenranta University of Technology have cooperated in the field of nuclear reactor thermal-hydraulics. During these years, a series of experimental facilities (REWET-I, -II, -III, VEERA) simulating pressurized water reactors (PWRs) have been built. The newest facility, PACTEL (Parallel Channel Test Loop), is an experimental out-of-pile facility designed to simulate the major components and system behaviour of a commercial PWR during postulated small and medium size break loss-of-coolant accidents (LOCAs), natural circulation and operational transients. A PACTEL natural circulation experiment has been carried out as an OECD/NEA international standard problem ISP 33. (2 refs., 3 figs., 2 tabs.).

1993-12-31

264

Solid Waste & Financial Assistance Program  

Science.gov (United States)

This program deals with solid waste disposal with topics/services covering: Reusable Building Materials and Large Household Items Exchange, Beneficial Use Determination, Biosolids, Certification, Compost Facil...

265

Savannah River Laboratory monthly report, November 1991  

Energy Technology Data Exchange (ETDEWEB)

This document details monthly activities at the Savannah River Laboratory. Topics addressed are reactor operation; tritium facilities and production; separation operations; environmental concerns; and waste management. (FI)

1991-01-01

266

Savannah River Laboratory monthly report, November 1991  

Energy Technology Data Exchange (ETDEWEB)

This document details monthly activities at the Savannah River Laboratory. Topics addressed are reactor operation; tritium facilities and production; separation operations; environmental concerns; and waste management. (FI)

1991-12-31

268

Program for personnel protection from oxygen deficiency in a Fast Breeder Reactor Test Facility (FFTF)  

Science.gov (United States)

The FFTF reactor is described. Procedures and equipment used to protect personnel from potential hazards of oxygen deficient environments are described.

1979-12-12

269

Operation of the Wilsonville Advanced Coal Liquefaction R and D Facility, 1981. Annual report  

Science.gov (United States)

This report summarizes the 1981 operating and test data obtained at the six ton per day Advanced Coal Liquefaction Research and Development Facility in Wilsonville, Alabama. Special emphasis is placed on data accumulated during the fourth quarter of 1981. The Wilsonville R and D Facility was in operation 71% of 1981 (70% of the fourth quarter) with scheduled shutdowns accounting for 23% of the downtime (28% during the fourth quarter). Kentucky 9 coal from the Fies mine was processed in all runs conducted during 1981 (Runs 222 through 235). The hydrotreater (HTR) unit was brought on stream successfully in May 1981. The three process units of the Wilsonville facility were operated in a non-integrated mode during the second half of 1981. Significant data was obtained and is summarized.

1984-08-01

270

Neonatal Sepsis and Neutrophil Insufficiencies  

UK PubMed Central (United Kingdom)

Sepsis has continuously been a leading cause of neonatal morbidity and mortality despite current advances in chemotherapy and patient intensive care facilities. Neonates are at high risk for...Full Text Available

2010-06-01

271

Mixed waste disposal facility at the Nevada Test Site  

Energy Technology Data Exchange (ETDEWEB)

This report provides a brief overview of the history and planning for a proposed mixed waste disposal site on the Nevada Test Site. 8 figs.

1987-01-01

272

LOREM IPSUM DOLOR SIT AMET CONSECTETUER - NASA IV&V Facility  

Science.gov (United States)

Austria, Belgium, Czech Republic,. Denmark, Finland, France, Germany, .... Another study on ESA industry and partners: in relation with sustainability of ...

273

Is It Time To Give The US Engineer Battalion (Combat) (Heavy ...  

Science.gov (United States)

... revetment construction, water well drilling, mobile facility assets construction using ... five days, and establish site layout for the follow-on RH ... modules. ...

2001-02-01

274

Hot Cell Facility (HCF) Safety Analysis Report  

Energy Technology Data Exchange (ETDEWEB)

This Safety Analysis Report (SAR) is prepared in compliance with the requirements of DOE Order 5480.23, Nuclear Safety Analysis Reports, and has been written to the format and content guide of DOE-STD-3009-94 Preparation Guide for U. S. Department of Energy Nonreactor Nuclear Safety Analysis Reports. The Hot Cell Facility is a Hazard Category 2 nonreactor nuclear facility, and is operated by Sandia National Laboratories for the Department of Energy. This SAR provides a description of the HCF and its operations, an assessment of the hazards and potential accidents which may occur in the facility. The potential consequences and likelihood of these accidents are analyzed and described. Using the process and criteria described in DOE-STD-3009-94, safety-related structures, systems and components are identified, and the important safety functions of each SSC are described. Additionally, information which describes the safety ...

2000-11-01

275

Greenversations » What you can do  

Science.gov (United States)

where I was in El Paso, I could always look up and see the smokestacks of the old Asarco smelter looming. The facility affected the city in more ways than that constant visual...

2011-10-07

276

Greenversations » Water  

Science.gov (United States)

where I was in El Paso, I could always look up and see the smokestacks of the old Asarco smelter looming. The facility affected the city in more ways than that constant visual...

2011-10-07

277

Greening EPA | US EPA  

Science.gov (United States)

strives to reduce our "environmental footprint" in the following areas: EPA Facilities Energy Conservation Requirements | Goals and Strategies | Results | Reports Green Power...

2011-08-16

278

Floristic Inventories of Confined Disposal Facilities in the ...  

Science.gov (United States)

... perennials; the dominant species included, in order of their relative importance, Polygonum lapathifolium (C = 0 Heartsease), Arctium minus (C = 0 ...

2005-09-01

279

Federal Energy Management Program: Interagency Coordination  

Science.gov (United States)

Program Plans, Implementation, & Results Energy Management at Federal Facilities Energy Management at DOE Fleet Management Interagency Coordination Interagency Energy...

2011-08-21

280

Fast Flux Test Facility performance monitoring management information, April 1988  

Energy Technology Data Exchange (ETDEWEB)

The purpose of this report is to provide management with performance data on key performance indicators selected from the FFTF Early Warning System performance indicators.

1988-05-01

281

Experiences of simulated tracer dispersal studies using effluent discharges at Tarapur aquatic environment  

International Nuclear Information System (INIS)

The nuclear complex in Tarapur, Maharashtra is a multi facility nuclear site comprising of power reactors and research facilities. Each facility has independent liquid effluent discharge line to Arabian Sea. Experimental studies were conducted to evaluate dilution factors in the aquatic environment using liquid effluent releases as tracer from one of the facilities. 3H and 137Cs radioisotopes present in the routine releases were used as simulated tracer nuclides. The dilution factors(D.F) observed for tritium were in the range of 20-20000 in a distance range of 10 m to 1500 m respectively and for 137Cs the D.F. were in the range of 50 to 900 over a distance range of 10-200 m. The paper describes the analytical methodology and sampling scenarios and the results of dilution factors obtained for Tarapur aquatic environment. (author)

2007-06-05

282

Evaluation of Commercial Magnetic Descalers.  

Science.gov (United States)

With the increased costs of maintaining boilers and chillers entrepreneurs around the country have offered magnetic and similar devices to facilities as viable alternatives to their maintenance program. This report gives a brief history of some of the pre...

1984-01-01

284

Emergencies > Oil Spills > Facility Response Plan | Browse EPA...  

Science.gov (United States)

Accidents Accident Preparedness, Accident Prevention, Chemical Accidents, Radiation Accidents Characterization Contingency Plans National Contingency Plan (NCP), Oil Removal...

2011-01-20

285

Development of calibration facility for radiation protection monitoring instruments  

International Nuclear Information System (INIS)

Exposure control at the operating Nuclear Power Station is a major concern. The challenging task of meeting the International standards in the field of radiation protection is the calibration of the radiation monitoring instruments and interpretation of personnel and area monitoring results. Correct interpretation is based on accurate calibration of radiation measuring instruments. The reliability and accuracy of the measurements are also partly based on the procedures applied in calibration. Inadequate calibration can cause large errors in dose estimation in complete dose rate range and energy range. Semiautomatic calibration facility established at TAPS 3 and 4 for radiation monitoring instruments. Objective of calibration facility is (a) Ensure instruments are working properly (b) calibration adjustment and (c) in case without calibration adjustment to reveal the error involved. The calibration facility and calibration ...

2008-11-19

286

Demonstration drop test and design enhancement of the CANDU spent fuel storage basket in dry storage facility  

British Library Electronic Table of Contents (United Kingdom)

A dry interim storage facility has been constructed at the Wolsung power plant in Korea. This dry storage facility has seven separated modules. There are 40 long slender cylinders in one module. In one cylinder, ten baskets where sixty CANDU spent fuel bundles are loaded are stacked and stored. For this dry storage facility, analyses and tests for hypothetical accident conditions that might occur while moving and storing the baskets into a cylinder were performed. In a demonstration test, one of test basket models did not satisfy one of the safety-related requirements. Thus, the revised basket designs were generated using a structural evaluation based on finite element analyses and specimen tests. Among these revised designs, one design was chosen as a final revised basket design. The fina...

2011-01-01

287

Cost Sensitivity Analysis for Radiology Department Planning  

UK PubMed Central (United Kingdom)

Two complementary computer programs have been developed for forecasting the demands and evaluating the costs of proposed radiographic facilities. The models are employed here in analyses of the sensitivity...Full Text Available

1971-01-01

288

Coastal Food Storage Locations- Kenai Fjords National Park  

Science.gov (United States)

This layer represents the different food storage facilities available at backcountry campsites along the coast of Kenai Fjords National Park. Site locations ... ...

289

Cartridge Cases.  

Science.gov (United States)

This report provides procedures for evaluating metal, consumable, and combustible cartridge cases. It identifies supporting tests, facilities, and equipment required. Subtests include weapon and ammunition preparation, initial inspection, ammunition chara...

1980-01-01

290

Brief summary of reactor core component welding for the Fast Flux Test Facility (FFTF)  

International Nuclear Information System (INIS)

Included are descriptions of welding methods and joint design, welding equipment, and qualification tests.

1974-04-25

291

Bioremediation  

Science.gov (United States)

from a military fuel storage facility released about 80,000 gallons of kerosine-based jet fuel. Immediate and extensive recovery measures managed to contain the spill, but...

2011-10-08

292

Bioremediation  

Science.gov (United States)

from a military fuel storage facility released about 80,000 gallons of kerosine-based jet fuel. Immediate and extensive recovery measures managed to contain the spill, but...

2011-08-27

293

Assessment of radiological safety of Wolsung site at site boundary considering crack impact  

British Library Electronic Table of Contents (United Kingdom)

The number of spent fuel storage facilities in the world continues to increase because of "Wait and See" policies and delay of a permanent disposal plan. The temporary spent fuel storage concept is changing to a pre-disposal storage concept. Strengthened safety concepts are required for expanded spent fuel storage facilities and sites. The Korea Hydro and Nuclear Power Company is planning to construct a reinforced concrete MACSTOR-400 facility at Wolsung. In concrete dry spent fuel storage structures, cracks can occur due to radiant heat and environmental chloride. The likelihood of cracking increases over time. Research on changes in shielding performance from one collinear crack in the surface of a concrete facility has been carried out. However there is no research about public radiolog...

2010-01-01

294

Assessment of RELAP5/MOD2 against natural circulation experiments performed with the REWET-III facility  

Energy Technology Data Exchange (ETDEWEB)

Natural circulation experiments carried out in the REWET-III facility in 1985 have been used for RELAP5/MOD2 assessment. The REWET-III facility is a scaled-down model of VVER-440 type reactors. The facility consists of a pressure vessel in which the downcomer is simulated with an external pipe assembly, hot and cold legs with loop seals and a horizontal steam generator. The volume scaling factor compared to the reference reactor is 1:2333. The present paper summarizes the experiences gained in the RELAP5/MOD2 calculations of selected REWET-III single- and two-phase natural circulation experiments. The code's ability to represent the main phenomena of experiments in both cases was satisfactory.

1992-04-01

295

Assessment of RELAP5/MOD2 against natural circulation experiments performed with the REWET-III facility  

Energy Technology Data Exchange (ETDEWEB)

Natural circulation experiments carried out in the REWET-III facility in 1985 have been used for RELAP5/MOD2 assessment. The REWET-III facility is a scaled-down model of VVER-440 type reactors. The facility consists of a pressure vessel in which the downcomer is simulated with an external pipe assembly, hot and cold legs with loop seals and a horizontal steam generator. The volume scaling factor compared to the reference reactor is 1:2333. The present paper summarizes the experiences gained in the RELAP5/MOD2 calculations of selected REWET-III single- and two-phase natural circulation experiments. The code`s ability to represent the main phenomena of experiments in both cases was satisfactory.

1992-04-01

296

Assessment of RELAP5/MOD2 against natural circulation experiments performed with the REWET-III facility  

International Nuclear Information System (INIS)

Natural circulation experiments carried out in the REWET-III facility in 1985 have been used for RELAP5/MOD2 assessment. The REWET-III facility is a scaled-down model of VVER-440 type reactors. The facility consists of a pressure vessel in which the downcomer is simulated with an external pipe assembly, hot and cold legs with loop seals and a horizontal steam generator. The volume scaling factor compared to the reference reactor is 1:2333. The present paper summarizes the experiences gained in the RELAP5/MOD2 calculations of selected REWET-III single- and two-phase natural circulation experiments. The code's ability to represent the main phenomena of experiments in both cases was satisfactory.

1992-01-01

297

Applications and benefits of the FFTF IEM cell training facility  

Energy Technology Data Exchange (ETDEWEB)

The Interim Examination and Maintenance (IEM) Cell is located within the Fast Flux Test Facility (FFTF) Reactor Containment Building. This cell is a complex vertical hot cell whose purpose is to process reactor experiments and to perform maintenance on reactor and refueling components. Because access to this very complex cell is limited, a mock-up called the IEM Training Facility (IEMTF) has been developed. The IEMTF provides the IEM cell with many valuable benefits. Four of these benefits are: (1) development of alternate processing methods; (2) hands-on evaluation of equipment problems; (3) a ready source of verified parts, and (4) training facilities for IEM Cell technicians.

1982-05-01

298

Advanced Neutron Source: Plant Design Requirements  

Energy Technology Data Exchange (ETDEWEB)

The Advanced Neutron Source will be a new world-class facility for research using hot, thermal, cold, and ultra-cold neutrons. The heart of the facility will be a 330-MW (fission), heavy-water cooled and heavy-water moderated reactor. The reactor will be housed in a central reactor building, with supporting equipment located in an adjoining reactor support building. An array of cold neutron guides will fan out into a large guide hall, housing about 30 neutron research stations. Appropriate office, laboratory, and shop facilities will be included to provide a complete facility for users. The ANS is scheduled to begin operation at the Oak Ridge National Laboratory early in the next decade. This PDR document defines the plant-level requirements for the design, construction, and operation of ANS. It also defines and provides input to the individual System Design Description (SDD) documents. Together, this ...

1990-07-01

299

A Study of Airbase Facility/Utility Energy R and D ...  

Science.gov (United States)

... 73 DOE/SANDIA 34-Meter VAWT Test Bed ..... ... 8 OPERATING CHARACTERISTICS OF DOE/SANDIA 34 METER VAWT ..... ...

1992-04-01

300

A - Z Index : Environmental Energy Technologies Division  

Science.gov (United States)

Buildings Energy-Efficient Research Laboratories Energy Efficiency in Federal Facilities Energy Efficiency Standards Group Energy Efficient Windows Collaborative Energy &...

2011-07-15

301

-!23(!,, - The Marshall Star - NASA  

Science.gov (United States)

Dec 6, 2007 ... provided cleaning services to numerous Marshall facilities over .... Two Schwinn Missle FS battery-powered scooters, $75. 683-4758 ...

302

Work plan for the Isotopes Facilities Deactivation Project at Oak Ridge National Laboratory  

Energy Technology Data Exchange (ETDEWEB)

The purpose of the Isotopes Facilities Deactivation Project (IFDP) is to place former isotopes production facilities at the Oak Ridge National Laboratory in a safe, stable, and environmentally sound condition; suitable for an extended period of minimum surveillance and maintenance (S&M) and as quickly and economical as possible. Implementation and completion of the deactivation project will further reduce the risks to the environment and to public safety and health. Furthermore, completion of the project will result in significant S&M cost savings in future years. The IFDP work plan defines the project schedule, the cost estimate, and the technical approach for the project. A companion document, the IFDP management plan, has been prepared to document the project objectives, define organizational relationships and responsibilities, and outline the management control systems to be employed in the management of the project. The project has ...

1995-05-01

303

Subcriticality calculations for the FFTF reverse approach to critical experiment  

Science.gov (United States)

The reverse approach to critical (RAC) experiments were performed in the ZPR-IX critical facility at Argonne National Laboratory. One of the major objectives of this project is to determine the adequacy of the low-level flux monitor (LLFM) detectors for initial loading of the Fast Flux Test Facility (FFTF). 5 references. (auth)

1975-01-01

304

Self installable: floating production facility requires only light support craft  

Energy Technology Data Exchange (ETDEWEB)

An integrated multiwell floating production, storage, and offloading (FPSO) facility was successfully installed at the Tazerka field offshore Tunisia in 1982. Because there is good reason to believe that the installation techniques developed for the Tazerka FPSO can be applied to even larger systems in deeper waters, this paper presents the design and step-by-step installation procedures developed at Tazerka.

1983-05-01

305

Remote participation technical infrastructure for the JET facilities under EFDA  

Energy Technology Data Exchange (ETDEWEB)

The new collaborative exploitation of the JET Facilities requires suitable technical tools and infrastructure measures to enable the Remote Participation of scientists from all European Fusion labs. Such measures are being gradually introduced. They comprise of a toolkit for Remote Data Access, Remote Computer Access and for teleconferencing, and of infrastructure measures that address network connectivity, network security, shared documentation and technical support.

2001-10-01

306

Recent developments in two-stage coal liquefaction at Wilsonville  

Energy Technology Data Exchange (ETDEWEB)

This paper presents results from the Advanced Coal Liquefaction R and D Facility at Wilsonville, Alabama. The primary sponsors are the US Department of Energy (DOE) and the Electric Power Research Institute (EPRI). Amoco Corporation became a sponsor in 1984 through an agreement with EPRI. The facility is operated by Catalytic, Inc., under the management of Southern Company Services, Inc.

1986-04-01

307

Reactor component inventory system at FFTF  

International Nuclear Information System (INIS)

A reliable inventory control system was developed at the Fast Flux Test Facility (FFTF) to keep track of the occupancy of 900 refueling facility locations, to compile historical data on the movement of each reactor assembly, and to simulate assembly moves. The simulate capability is valuable because it allows verification of documents before they are issued for use in the plant, and eliminates the possibility of planning illegal or impossible moves. The system is installed on a UNIVAC 1100 computer and is maintained using a data base management system by Sperry Univac called MAPPER.

1985-09-08

308

Radionuclide buildup in FFTF [Fast Flux Test Facility] heat transport system cells  

International Nuclear Information System (INIS)

The purpose of the work reported in this paper was to measure the radionuclide buildup in primary heat transport system cell No. 3 at the Fast Flux Test Facility (FFTF) and to compare the results with predicted values from a model based on experimental studies and experience at similar reactors. The information obtained is used for maintenance planning and to enhance ability to assess radionuclide buildup in the future at FFTF and in other reactors.

1989-11-26

309

Radioactive and mixed waste management plan for the Lawrence Berkeley Laboratory Hazardous Waste Handling Facility  

Energy Technology Data Exchange (ETDEWEB)

This Radioactive and Mixed Waste Management Plan for the Hazardous Waste Handling Facility at Lawrence Berkeley Laboratory is written to meet the requirements for an annual report of radioactive and mixed waste management activities outlined in DOE Order 5820.2A. Radioactive and mixed waste management activities during FY 1994 listed here include principal regulatory and environmental issues and the degree to which planned activities were accomplished.

1995-01-01

310

Quality assurance requirements for the design of nuclear fuel reprocessing facilities  

International Nuclear Information System (INIS)

Requirements and guidance are provided for a quality assurance program for the design of nuclear fuel reprocessing facilities involving structures, systems and components whose satisfactory performance is required to prevent accidents that could cause undue risk to the health and safety of the public, or to mitigate the consequences of such accidents if they were to occur. The standard is to be used in conjunction with ANSI N46.2.

311

Quality assurance requirements for control of procurement items and services for nuclear fuel reprocessing facilities  

International Nuclear Information System (INIS)

Requirements and guidelines are provided for the control of activities to be exercised during procurement of items and services which affect the quality of nuclear facilities. These requirements and guidelines apply to procurement activities for items and services such as designing, purchasing, fabricating, handling, shipping, storing, cleaning, constructing, erecting, installing, inspecting, texting, maintaining and modifying.

312

Problems of development and putting into education process an electronic textbook on special discipline 'General theory and construction of heat-and-power engineering facilities'  

International Nuclear Information System (INIS)

The results of work of making the electronic textbook of special discipline ('General theory and construction of heat-and-power engineering facilities' are brought. The principles and requirements, presented towards literature of such type, are outlined. (author)

2005-01-01

313

Power density distribution by gamma scanning of fuel rods measurement technique in RA-8 critical facility  

International Nuclear Information System (INIS)

Power density measurements in the critical facility RA-8 are presented. These measurements were the first systematic use of the reactor. A measurement system was designed, built and proved for this goal. Power profiles are showed and the results are compared with calculated values. (author)

1999-10-26

314

Offshore: North Sea facility gets the CETCO solution  

British Library Electronic Table of Contents (United Kingdom)

CETCO Oilfield Services, suppliers of environmental systems, have undertaken a project to treat contaminated water returns on a Floating, Production, Storage and Offloading (FPSO) facility in the North Sea. The solution sees fluids treated during oil well clean-up operations, reducing the potential for overboard oil discharges, and resulting production upsets.

2006-01-01

315

Measurement of the fast neutron component in the beam of the NPL Thermal Neutron Column using a Bonner sphere spectrometer  

Energy Technology Data Exchange (ETDEWEB)

Following a recent refurbishment of the NPL Thermal Neutron Facility, the spectrum of the epithermal and fast neutron component of the beam produced by the thermal column of this facility was measured over the energy range from thermal to 20 MeV using a Bonner sphere spectrometry system. The effect of the presence of epithermal and fast neutrons on the measured response of commonly-used thermal neutron dosemeters was calculated. (author)

1999-05-01

316

Measurement of the fast neutron component in the beam of the NPL Thermal Neutron Column using a Bonner sphere spectrometer  

International Nuclear Information System (INIS)

Following a recent refurbishment of the NPL Thermal Neutron Facility, the spectrum of the epithermal and fast neutron component of the beam produced by the thermal column of this facility was measured over the energy range from thermal to 20 MeV using a Bonner sphere spectrometry system. The effect of the presence of epithermal and fast neutrons on the measured response of commonly-used thermal neutron dosemeters was calculated. (author)

317

Measurement of the K?/K? ratio for muon alpha sticking X-rays in muon catalyzed d-t fusion at the RIKEN-RAL Muon Facility  

International Nuclear Information System (INIS)

At the RIKEN-RAL Muon Facility, ?- to ? sticking K? X-rays were observed for the first time taking advantage of the pulsed beam structure. The precision of the present measurements was insufficient to distinguish between theoretical models, however the observed K?/K? X-ray intensity ratio tends to be smaller than most of these theoretical predictions.

1999-06-01

318

Krypton recovery pilot plant  

Energy Technology Data Exchange (ETDEWEB)

A krypton recovery pilot plant has been completed for the Power Reactor and Nuclear Fuel Development Corporation. This is the first industrial facility in the world to make practical use of development results for offgas treatment and storage from nuclear facilities. The cryogenic distillation process was adopted as a proven and reliable method to separate krypton and xenon, and to reduce gas effuents to a level so low that the decontamination factor amounts to more than 1000.

1983-01-01

319

Institutional models for nuclear fuel cycle facilities  

International Nuclear Information System (INIS)

The possibility of having properly designed multinational fuel cycle agreements which would contribute to public acceptance of nuclear energy are explored. The advantages of existing international cooperation in the field of uranium enrichment and nuclear waste disposal and reprocessing are discussed. The possible forms of multinational co-operation under an international organisation, committed the non-proliferation and operating under international law and covering storage facilities, security of raw materials and the nuclear fuel cycle are summarised in model form. (U.K.).

320

High temperature materials experience at the Central Receiver Test Facility  

Science.gov (United States)

During four years of operation at the Central Receiver Test Facility (CRTF) ceramics have performed well in cyclic solar flux densities of less than 30 W/cm/sup 2/. Above 100 W/cm/sup 2/, serious limitations exist. Important application considerations include: the geometry, cyclic and long time exposures, flux density gradients, thermal shock, weathering, and soiling.

1982-01-01

321

Green design focus: Energy efficiency and environmental responsibility  

Energy Technology Data Exchange (ETDEWEB)

This case study illustrates how an existing building can be transformed into a sustainable, green facility through teamwork. This multi-purpose building comprises office space, combustion testing facilities, and microwave communications center. The paper discusses internal systems design, indoor air quality, commissioning, economics, operations and maintenance, and monitoring.

1998-02-01

322

Federal Facilities Compliance Act, Draft Site Treatment Plan: Compliance Plan Volume. Part 2, Volume 2  

Energy Technology Data Exchange (ETDEWEB)

This document presents the details of the implementation of the Site Treatment Plan developed by Ames Laboratory in compliance with the Federal Facilities Compliance Act. Topics discussed in this document include: implementation of the plan; milestones; annual updates to the plan; inclusion of new waste streams; modifications of the plan; funding considerations; low-level mixed waste treatment plan and schedules; and TRU mixed waste streams.

1994-08-31

323

Facility for studying photon-neutron reactions under a beam of braking radiation  

International Nuclear Information System (INIS)

A facility for studying photon-neutron reactions under a braking #gamma#-beam with an energy of up to 26 MeV from a betratron includes Saratov-2, SM-4A, and IBM AT-386 microcomputers. Neutron detectors, pulsed braking radiation dosimeters, and the devices to control the betatron energy are described.

324

FFTF: an outstanding engineering achievement  

International Nuclear Information System (INIS)

The Fast Flux Test Facility on the federal reservation at Hanford, Washington, has become a bright star in the universe of nuclear science and engineering technologies. The entire FFTF enterprise is now a success story, and this is particularly significant in these days when good news about nuclear power is scarce. The reactor, its testing capabilities and associated test facilities are described.

325

Explosion protection in nuclear power plants with LWR and HTR reactors. As of August 14, 1989. Explosionsschutz in Kernkraftwerken mit Leichtwasser- und Hochtemperaturreaktoren (allgemeine und fallbezogene Anforderungen). Vom 14. August 1989  

Energy Technology Data Exchange (ETDEWEB)

The technical rule intends to maintain the function of the safety facilities in case of explosion hazards resulting from materials capable of generating explosive atmospheres or forming explosive mixtures if such materials are brought or released into the nuclear facility or are generated on site. (orig.).

1989-12-07

326

Explosion protection in nuclear power plants with LWR and HTR reactors (general and case depending requirements). Explosionsschutz in Kernkraftwerken mit Leichtwasser- und Hochtemperaturreaktoren (allgemeine und fallbezogene Anforderungen)  

Energy Technology Data Exchange (ETDEWEB)

The technical rule intends to maintain the function of the safety facilities in case of explosion hazards resulting from materials capable of generating explosive atmospheres or forming explosive mixtures if such materials are brought or released into the nuclear facility or are generated on site. (orig.).

1989-01-01

327

Evaluation of the SYNTHOIL process. Volume II. Status of development. [47 refs  

Science.gov (United States)

The Synthoil process for producing heavy desulfurized fuel oil from coal has been under development at Pittsburgh Energy Research Center since 1969. The status of development and technical feasibility of the process are reviewed. This is part of an engineering and economic evaluation based on the conceptual design of a 100,000-bbl/day commercial Synthoil facility. Experimental data are discussed with regard to their adequacy for the formulation of a basis for the process design of such a facility. Potential engineering and equipment problems are analyzed.

1977-06-01

328

Energy Engineering Analysis Program, increments A, B, G, Stratford Army Engine Plant, Stratford, Connecticut. Executive summary  

Energy Technology Data Exchange (ETDEWEB)

The purpose of this analysis is to develop a systematic program of projects that will result in energy consumption reductions in compliance with the stated goals of the Army Facilities Energy Plan for the Stratford Army Engine Plant in Stratford, Connecticut. Reduced energy consumption is a stated goal for the Army Facility Energy Plan.

1983-08-01

329

Emission estimation technique manual for Combustion engines Version 3.0  

Wastenet

...to facilities using - Petrol and diesel industrial engines - Petrol and diesel light vehicles, commercial vehicles and trucks on the facility - Large stationary diesel and dual-fuel engines - Heavy-duty natural gas fired pipeline compressor engines and turbines First published in February 1999 Revised - August 2000 Version 2.3 - ...

330

Electron beam and high-speed optical diagnostics for the Los Alamos HIBAF (High Brightness Accelerator FEL) Facility  

Energy Technology Data Exchange (ETDEWEB)

Characterization of the electron beam's properties will be a major task after the upgrade of the Los Alamos Free-Electron Laser (FEL) Facility with a photoelectric injector (PEI) and increased acceleration capability to 40 MeV. Adjustments to the previous diagnostics package that address the lower beam emittance, higher energy, and wakefield source reduction issues will be discussed. 6 refs., 8 figs., 1 tab.

1989-01-01

331

Drilling on the basis of reliable data. Geothermal exploration; Bohren nach verlaesslichen Planungsdaten. Geothermie  

Energy Technology Data Exchange (ETDEWEB)

Geothermal heat pump systems necessitate a comprehensive approach to geology and building facilities in order to be energetically useful and efficient. Cooperation with geothermal experts should be sought at an early projecting stage in order to obtain reliable data. Geothermal data and the technical facilities of the building must be matched for the project to be both effective and efficient. (orig.)

2008-01-15

332

Comprenhensive Program of Engineering and Geologic Surveys for Designing and Constructing Radioactive Waste Storage Facilities in Hard Rock Massifs  

Energy Technology Data Exchange (ETDEWEB)

Geological, geophysical, and engineering-geological research conducted at the 'Yeniseisky' site obtained data on climatic, geomorphologic, geological conditions, structure and properties of composing rock, and conditions of underground water recharge and discharge. These results provide sufficient information to make an estimate of the suitability of locating a radioactive waste (R W) underground isolation facility at the Nizhnekansky granitoid massif

2002-12-27

333

Commodity storage valuation: A linear optimization based on traded instruments  

British Library Electronic Table of Contents (United Kingdom)

A valuation methodology for commodity storage facilities is proposed. This model utilizes traded instruments to replicate the fundamental derivative components of commodity storage facilities. The methodology is robust to different commodities, physical characteristics, and markets for valuing these types of assets. Two examples using the U. S. natural gas markets are presented.

2006-01-01

334

Cold Vacuum Drying (CVD) Facility Technical Safety Requirements  

Energy Technology Data Exchange (ETDEWEB)

The Technical Safety Requirements (TSRs) for the Cold Vacuum Drying Facility define acceptable conditions, safe boundaries, bases thereof, and management or administrative controls required to ensure safe operation. Controls required for public safety, significant defense-in-depth, significant worker safety, and for maintaining radiological and toxicological consequences below risk evaluation guidelines are included.

1999-12-16

335

Calculation of neutron source strength in Fast Flux Test Facility fuel as a function of irradiation  

Energy Technology Data Exchange (ETDEWEB)

A method of calculating the neutron source strength in irradiated Fast Flux Test Facility (FFTF), fuel has been developed and is presented in this paper. This method has been used to perform calculations in support of the reactivity monitoring of the FFTF reactor by the modified source multiplication method during refueling operations. 31 refs.

1981-08-01

336

Calculated fluence spectra at neutron therapy facilities  

International Nuclear Information System (INIS)

The Monte Carlo transport codes LAHET and MCNP were used to calculate energy fluence spectra at three neutron therapy facilities. The results compare very favourably with measured data. Kerma spectra and the ratio of ICRU muscle tissue kerma to A-150 kerma, along the carbon to oxygen kerma ratio, were determined. Absorbed dose rate calculations are in reasonable agreement with measured values. Use of these codes to study modifications to existing therapy beams is briefly discussed. (author).

1995-11-13

337

Beneficiation-hydroretort processing of US oil shales, engineering study  

Energy Technology Data Exchange (ETDEWEB)

This report describes a beneficiation facility designed to process 1620 tons per day of run-of-mine Alabama oil shale containing 12.7 gallons of kerogen per ton of ore (based on Fischer Assay). The beneficiation facility will produce briquettes of oil shale concentrate containing 34.1 gallons of kerogen per ton (based on Fischer Assay). The beneficiation facility will produce briquettes of oil shale concentrate containing 34.1 gallons of kerogen per ton (based on Fischer Assay) suitable for feed to a hydroretort oil extraction facility of nominally 20,000 barrels per day capacity. The beneficiation plant design prepared includes the operations of crushing, grinding, flotation, thickening, filtering, drying, briquetting, conveying and tailings empoundment. A complete oil shale beneficiation plant is described including all anticipated ancillary facilities. For purposes of determining ...

1988-12-01

338

Basis for Interim Operation (BIO) for the Rework Unit (RW), Du Pont Water (DW) Plant, Moderator Processing Facility (MPF), and Technical Purification Facility (TPF)  

Energy Technology Data Exchange (ETDEWEB)

The mission of the Heavy Water portion of D Area (or 400 Area) at SRS is to purify the site inventory of heavy water for storage in the Reactor Areas for future DOE missions.

1996-01-01

339

An Experimental Study of Oil / Water Flow in Horizontal Pipes  

Energy Technology Data Exchange (ETDEWEB)

The purpose of this thesis is to study the behaviour of the simultaneous flow of oil and water in horizontal pipes. In this connection, two test facilities are used. Both facilities have horizontal test sections with inner pipe diameters equal to 2 inches. The largest facility, called the model oil facility, has reservoirs of 1 m{sub 3} of each medium enabling flow rates as high as 30 m{sub 3}/h, which corresponds to mixture velocities as high as 3.35 m/s. The flow rates of oil and water can be varied individually producing different flow patterns according to variations in mixture velocity and input water cut. Two main classes of flows are seen, stratified and dispersed. In this facility, the main focus has been on stratified flows. Pressure drops and local phase fractions are measured for a large number of flow conditions. Among the instruments used are differential pressure ...

2001-07-01

340

Waste sampling and characterization facility (WSCF) maintenance implementation plan  

Energy Technology Data Exchange (ETDEWEB)

This Maintenance Implementation Plan (MIP) is written to satisfy the requirements of the US Department of Energy (DOE) Order 4330.4B, Maintenance Management Program that specifies the general policy and objectives for the establishment of the DOE controlled maintenance programs. These programs provide for the management and performance of cost effective maintenance and repair of the DOE property, which includes facilities. This document outlines maintenance activities associated with the facilities operated by Waste Management Hanford, Inc. (WMH). The objective of this MIP is to provide baseline information for the control and execution of WMH Facility Maintenance activities relative to the requirements of Order 4330.4B, assessment of the WMH maintenance programs, and actions necessary to maintain compliance with the Order. Section 2.0 summarizes the history, mission and description of the WMH ...

1997-08-13

341

Waste sampling and characterization facility (WSCF)  

Energy Technology Data Exchange (ETDEWEB)

The Waste Sampling and Characterization Facility (WSCF) complex consists of the main structure (WSCF) and four support structures located in the 600 Area of the Hanford site east of the 200 West area and south of the Hanford Meterology Station. WSCF is to be used for low level sample analysis, less than 2 mRem. The Laboratory features state-of-the-art analytical and low level radiological counting equipment for gaseous, soil, and liquid sample analysis. In particular, this facility is to be used to perform Resource Conservation and Recovery Act (RCRA) of 1976 and Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) of 1980 sample analysis in accordance with U.S. Environmental Protection Agency Protocols, room air and stack monitoring sample analysis, waste water treatment process support, and contractor laboratory quality assurance checks. The samples to be analyzed contain very low concentrations of radioisotopes. The ...

1994-10-01

342

Results of third regular inspection of No. 2 plant in Sendai Nuclear Power Station, Kyushu Electric Power Co. , Inc  

Energy Technology Data Exchange (ETDEWEB)

The third regular inspection of No.2 plant in Sendai Nuclear Power Station was carried out from December 27, 1988 to May 25, 1989. The parallel operation was resumed on April 28, 1989, 123 days after the parallel off. The facilities which were the object of inspection were the reactor proper, reactor cooling system, measurement and control system, fuel facilities, radiation control facilities, waste facilities, reactor containment installation and emergency electric power generation system. On the facilities which were the object of inspection, the appearance, disassembling, leak, function, performance and other inspections were carried out. As the results, significant in indication was observed in 8 bolts for fixing the flow-changing vanes of primary coolant pumps, and broken valve spindles were found, but other abnormality was not found. The works related to this regular ...

1990-03-01

343

Results of second regular inspection of No.2 plant in Sendai Nuclear Power Station, Kyushu Electric Power Co., Inc  

International Nuclear Information System (INIS)

The second regular inspection of No.2 plant in Sendai Nuclear Power Station was carried out from October 5, 1987 to January 8, 1988. the parallel operation was resumed on December 8, 1987, 65 days after the parallel off. The facilities as the object of inspection were the reactor proper, reactor cooling system, measurement and control system, fuel facilities, radiation control facilities, waste facilities, reactor containment installation, and emergency power generation system. On these facilities as the object of inspection, the appearance, disassembling, leak, function, performance and other inspections were carried out, and abnormality was not found at all. The works related to this regular inspection were accomplished within the range of allowable dose based on the relevant laws. The main reconstruction works carried out during the period of this regular inspection were the ...

1988-01-01

344

Results of second regular inspection of No. 2 plant in Sendai Nuclear Power Station, Kyushu Electric Power Co. , Inc  

Energy Technology Data Exchange (ETDEWEB)

The second regular inspection of No.2 plant in Sendai Nuclear Power Station was carried out from October 5, 1987 to January 8, 1988. the parallel operation was resumed on December 8, 1987, 65 days after the parallel off. The facilities as the object of inspection were the reactor proper, reactor cooling system, measurement and control system, fuel facilities, radiation control facilities, waste facilities, reactor containment installation, and emergency power generation system. On these facilities as the object of inspection, the appearance, disassembling, leak, function, performance and other inspections were carried out, and abnormality was not found at all. The works related to this regular inspection were accomplished within the range of allowable dose based on the relevant laws. The main reconstruction works carried out during the period of this regular inspection were the ...

1988-08-01

345

Research and development of neutron radiography in IAERU  

Energy Technology Data Exchange (ETDEWEB)

In the Institute for Atomic Energy, Rikkyo University, just after the TRIGA-2 research reactor of 100 kW has attained the criticality, the cylindrical box for neutron radiography (NR) irradiation was made in the attached pool, and the research on NR was started in 1961. Thereafter in 1985, the vertical irradiation pipe was installed in the reactor tank, and the experiment for collecting the basic data was begun. In 1986, based on the obtained data, the NR irradiation facility on full scale was installed in No. 2 tangential horizontal experimental hole. As the main NR irradiation facilities, the vertical neutron irradiation pipe, the use of which is stopped now, the NR facility using the horizontal experimental hole (RUR/N2), the irradiation facility and ancillary facilities such as beam shutter, beam catcher and hoist are described. As the main equipments for NR, the imaging ...

1995-03-01

346

Preliminary assessment of existing experimental data for validation ofreactor physics codes and data for NGNP design and analysis.  

Energy Technology Data Exchange (ETDEWEB)

The Next Generation Nuclear Plant (NGNP), a demonstration reactor and hydrogen production facility proposed for construction at the INEEL, is expected to be a high-temperature gas-cooled reactor (HTGR). Computer codes used in design and safety analysis for the NGNP must be benchmarked against experimental data. The INEEL and ANL have examined information about several past and present experimental and prototypical facilities based on HTGR concepts to assess the potential of these facilities for use in this benchmarking effort. Both reactors and critical facilities applicable to pebble-bed and prismatic block-type cores have been considered. Four facilities--HTR-PROTEUS, HTR-10, ASTRA, and AVR--appear to have the greatest potential for use in benchmarking codes for pebble-bed reactors. Similarly, for the prismatic block-type reactor design, two experiments have been ranked as having ...

2005-10-25

347

OPERATION OF A PUBLIC GEOLOGIC CORE AND SAMPLE REPOSITORY IN HOUSTON TEXAS  

Energy Technology Data Exchange (ETDEWEB)

In the spring of 2002, the Department of Energy provided an initial 1-year grant to the Bureau of Economic Geology (BEG) at The University of Texas at Austin (UT). The grant covered the one-year operational expenses of a worldclass core and cuttings facility located in Houston, Texas, that BP America donated to the BEG. The DOE investment of $300,000, matched by a $75,000 UT contribution, provided critical first-year funds that were heavily leveraged by the BP gift of $7.0 million in facilities and cash. DOE also provided a one-month extension and grant of $30,000 for the month of May 2003. A 5-year plan to grow a permanent endowment in order to manage the facility in perpetuity is well under way and on schedule. The facility, named the Houston Research Center, represents an ideal model for a strong Federal, university, and private partnership to accomplish a national good. This report summarizes the ...

2003-06-01

348

Long-term storage of Greater-Than-Class C Low-Level Waste  

Energy Technology Data Exchange (ETDEWEB)

Under Federal law, the Department of Energy (DOE) is responsible for safe disposal of Greater-Than-Class C Low-Level Waste (GTCC LLW) generated by licenses of the Nuclear Regulatory commission (NRC) or Agreement States. Such waste must be disposed of in a facility licensed by the NRC. It is unlikely that licensed disposal of GTCC LLW will be available prior to the year 2010. Pending availability of disposal capacity, DOE is assessing the need for collective, long-term storage of GTCC LLW. Potential risks to public health and safety caused by long-term storage of GTCC LLW at the place of generation will be evaluated to determine if alternative facilities are warranted. If warranted, several options will be investigated to determine the preferred alternative for long-term storage. These options include modification of an existing DOE facility, development of a new DOE facility, or development of a ...

1990-01-01

349

Latest trends in rolling mill facilities toward the 21st century; 21 seiki ni muketa saishin atsuen setsubi no doko  

Energy Technology Data Exchange (ETDEWEB)

Described herein are the latest trends in rolling mill facilities toward the 21st. century and new techniques developed by Hitachi Ltd. These cover hot rolling facilities, such as two-stage twin, high crown control-roll cross mill, roll shaping machine and continuous hot rolling systems; cold rolling facilities, such as pickling line-tandem cold mill and other continuous systems; and fine steel rolling facilities, such as roll mill for very small diameter pipes and others to improve productivity and product quality. The other new techniques include systems to pursue reliability and maintainability, in which electric appliances, instruments and computers are integrated, or equipped with built-in large-capacity inverters and drivers. For hot rolling, the above techniques lead to development of a new system named Hi-HOT, which produces high-quality hot coils at a sufficient speed, while keeping rolled ...

1996-06-01

350

Hydrogeologic investigation of the Advanced Coal Liquefaction Research and Development Facility, Wilsonville, Alabama  

Energy Technology Data Exchange (ETDEWEB)

This document describes the geology and hydrogeology at the former Advanced Coal Liquefaction Research and Development (ACLR&D) facility in Wilsonville, Alabama. The work was conducted by personnel from the Oak Ridge National Laboratory Grand Junction office (ORNL/GJ) for the U.S. Department of Energy (DOE) Pittsburgh Energy Technology Center (PETC). Characterization information was requested by PETC to provide baseline environmental information for use in evaluating needs and in subsequent decision-making for further actions associated with the closeout of facility operations. The hydrogeologic conceptual model presented in this report provides significant insight regarding the potential for contaminant migration from the ACLR&D facility and may be useful during other characterization work in the region. The ACLR&D facility is no longer operational and has been dismantled. The site was ...

1996-09-01

351

Free electron laser facilities employing a 150-MeV linac injector for Saga synchrotron light source  

International Nuclear Information System (INIS)

Free electron laser (FEL) facilities as the FELI FEL Facility are proposed, for which a 150-MeV linac type injector for a Saga synchrotron light source (SLS) is employed in FEL mode. The linac has two operating modes; short macropulse mode a 1 #mu#s at 150 MeV for injection to a 1 - 1.3-GeV third generation type storage ring and long macropulse mode of 12 #mu#s at 100 MeV for four FEL Facilities. The macropulse beam consists of a train of several ps, 0.6 nC microbunches (peak current 100 A) repeating at 89.25 MHz. We are aiming to supply high power level photon beams covering an attractive wavelength range from 0.05 nm (25 keV) to 200 #mu#m (0.006 eV) for scientific researches, bio-medical and industrial applications, using the Saga third generation type SLS with a superconducting wiggler and the proposed four FEL Facilities. (author)

1999-12-01

352

Cost comparison among spent fuel storage techniques  

Energy Technology Data Exchange (ETDEWEB)

Scenarios are developed for spent fuel that is taken out of the nuclear reactor and stored for 20 years before reprocessing, and three storage techniques which use a water pool, dry cask or vault are compared with respect to their costs. The storage price (storage cost per kilogram of spent fuel), which is employed as the economic index, is calculated on the assumption that all the charge is paid when the spent fuel is brought in the storage facilities. Four scenarios are assumed for spent PWR and BWR fuels to be stored in at-reactor (AT) or away-from-reactor (AFR) facilities. The capital costs cover the buildings of the storage facilities, equipment, decommissioning, casks for transportation and storage (for cask storage) and casks for transportation (for water pool or vault storage). Costs for operation and maintenance of the facilities are also considered in evaluating these methods. Evaluation ...

1987-09-01

353

Cost comparison among spent fuel storage techniques  

International Nuclear Information System (INIS)

Scenarios are developed for spent fuel that is taken out of the nuclear reactor and stored for 20 years before reprocessing, and three storage techniques which use a water pool, dry cask or vault are compared with respect to their costs. The storage price (storage cost per kilogram of spent fuel), which is employed as the economic index, is calculated on the assumption that all the charge is paid when the spent fuel is brought in the storage facilities. Four scenarios are assumed for spent PWR and BWR fuels to be stored in at-reactor (AT) or away-from-reactor (AFR) facilities. The capital costs cover the buildings of the storage facilities, equipment, decommissioning, casks for transportation and storage (for cask storage) and casks for transportation (for water pool or vault storage). Costs for operation and maintenance of the facilities are also considered in evaluating these methods. Evaluation ...

354

An interregional hedonic analysis of noxious facility impacts on local wages and property values  

Energy Technology Data Exchange (ETDEWEB)

Claims of property value loss are commonly raised by homeowners when noxious facilities are sited or when new information about the hazards of existing facilities is made public. While the capitalization of externalities into land values is consistent with economic theory, empirical measurement of impacts has not generated consistent results. This is true both for hedonic measurements as well as other types of econometric analyses. While it is well established that job and site risks have similar impacts on regional labor markets, there are no studies relating the presence of a broad range of noxious facilities to local wage premiums. In contrast, this study employs an interregional framework in a hedonic analysis of both wage and property markets and considers eight different facility classifications. This paper discusses the development of the hedonic model employed in this study. It develops more ...

1991-01-01

355

An interregional hedonic analysis of noxious facility impacts on local wages and property values  

Energy Technology Data Exchange (ETDEWEB)

Claims of property value loss are commonly raised by homeowners when noxious facilities are sited or when new information about the hazards of existing facilities is made public. While the capitalization of externalities into land values is consistent with economic theory, empirical measurement of impacts has not generated consistent results. This is true both for hedonic measurements as well as other types of econometric analyses. While it is well established that job and site risks have similar impacts on regional labor markets, there are no studies relating the presence of a broad range of noxious facilities to local wage premiums. In contrast, this study employs an interregional framework in a hedonic analysis of both wage and property markets and considers eight different facility classifications. This paper discusses the development of the hedonic model employed in this study. It develops more ...

1991-12-31

356

A combined cycle engine test facility  

Energy Technology Data Exchange (ETDEWEB)

Rocket-Based Combined-Cycle (RBCC) engines intended for missiles and/or space launch applications incorporate features of rocket propulsion systems operating in concert with airbreathing engine cycles. Performance evaluation of these types of engines, which are intended to operate from static sea level take-off to supersonic cruise or accerlerate to orbit, requires ground test capabilities which integrate rocket component testing with airbreathing engine testing. A combined cycle engine test facility has been constructed in the General Applied Science Laboratories, Inc. (GASL) Aeropropulsion Test Laboratory to meet this requirement. The facility was designed to support the development of an innovative combined cycle engine concept which features a rocket based ramjet combustor. The test requirements included the ability to conduct tests in which the propulsive force was generated by rocket only, the ramjet only and simultaneous rocket and ...

1995-09-01

357

Long-term storage facility for reactor compartments in Sayda Bay - German support for utilization of nuclear submarines in Russia  

Science.gov (United States)

The German-Russian project that is part of the G8 initiative on Global Partnership Against the Spread of Weapons and Materials of Mass Destruction focuses on the speedy construction of a land-based interim storage facility for nuclear submarine reactor compartments at Sayda Bay near Murmansk. This project includes the required infrastructure facilities for long-term storage of about 150 reactor compartments for a period of about 70 years. The interim storage facility is a precondition for effective activities of decommissioning and dismantlement of almost all nuclear-powered submarines of the Russian Northern Fleet. The project also includes the establishment of a computer-assisted waste monitoring system. In addition, the project involves clearing Sayda Bay of other shipwrecks of the Russian navy. On the German side the project is carried out by the Energiewerke Nord GmbH (EWN) on behalf of the Federal Ministry of ...

2007-07-01

358

Fall Chinook Aclimation Project; Pittsburg Landing, Captain John Rapids, and Big Canyon, Annual Report 2001.  

Energy Technology Data Exchange (ETDEWEB)

Fisheries co-managers of U.S. v Oregon supported and directed the construction and operation of acclimation and release facilities for Snake River fall Chinook from Lyons Ferry Hatchery at three sites above Lower Granite Dam. In 1996, Congress instructed the U.S. Army Corps of Engineers (USCOE) to construct, under the Lower Snake River Compensation Plan (LSRCP), final rearing and acclimation facilities for fall Chinook in the Snake River basin to complement their activities and efforts in compensating for fish lost due to construction of the lower Snake River dams. The Nez Perce Tribe (NPT) played a key role in securing funding and selecting acclimation sites, then assumed responsibility for operation and maintenance of the facilities. In 1997, Bonneville Power Administrative (BPA) was directed to fund operations and maintenance (O&M) for the facilities. Two acclimation ...

2004-01-01

359

Reasons for decision in the matter of TransCanada PipeLines Limited. Motifs de decision (relative a) TransCanada Pipelines Limited; Volume 3. Installations, exportations de gaz et demandes deposees en vertu de l'article 71  

Energy Technology Data Exchange (ETDEWEB)

TransCanada Pipelines Limited submitted an application to the National Energy Board for new facilities to increase natural gas deliveries to its domestic and export markets. The proposed facilities consist of 1,590 km of pipeline, 21 new compressor units and two new compressor stations. The total cost of the facilities was estimated at $2,408 million. The Board considered at the hearing 15 applications made pursuant to Part IV of the National Energy Board Act for gas exports at existing delivery points at Emerson and Niagra Falls as well as at proposed new delivery points at Chippawa and Iroquois, Ontario. Twelve of these applications were filed in support of TransCanada's facilities application. Five applications were also filed pursuant to section 71 of the National Energy Board Act for orders requiring TransCanada to receive, transport and deliver natural gas offered by the applicants and to ...

1991-04-01

360

Reasons for decision in the matter of TransCanada PipeLines Limited  

Energy Technology Data Exchange (ETDEWEB)

TransCanada Pipelines Limited submitted an application to the National Energy Board for new facilities to increase natural gas deliveries to its domestic and export markets. The proposed facilities consist of 1,590 km of pipeline, 21 new compressor units and two new compressor stations. The total cost of the facilities was estimated at $2,408 million. The Board considered at the hearing 15 applications made pursuant to Part IV of the National Energy Board Act for gas exports at existing delivery points at Emerson and Niagra Falls as well as at proposed new delivery points at Chippawa and Iroquois, Ontario. Twelve of these applications were filed in support of TransCanada's facilities application. Five applications were also filed pursuant to section 71 of the National Energy Board Act for orders requiring TransCanada to receive, transport and deliver natural gas offered by the applicants and to ...

1991-04-01

361

Full L.A. treatment  

Energy Technology Data Exchange (ETDEWEB)

The high-purity-oxygen activated sludge process will be used to expand secondary treatment capacity and improve water quality in Santa Monica Bay. The facility is operated by the city of Los Angeles Department of Public Works` Bureau of Sanitation. The overall Hyperion Full Secondary Project is 30% complete, including a new headworks, a new primary clarifier battery, an electrical switch yard, and additional support facilities. The upgrading of secondary facilities is 50% complete, and construction of the digester facilities, the waste-activated sludge thickening facility, and the second phase of the three-phase modification to existing primary clarifier batteries has just begun. The expansion program will provide a maximum monthly design capacity of 19,723 L/s(450 mgd). Hyperion`s expansion program uses industrial treatment techniques rarely attempted in a municipal ...

1993-09-01

362

B Plant treatment, storage, and disposal (TSD) units inspection plan  

Energy Technology Data Exchange (ETDEWEB)

This inspection plan is written to meet the requirements of WAC 173-303 for operations of a TSD facility. Owners/operators of TSD facilities are required to inspection their facility and active waste management units to prevent and/or detect malfunctions, discharges and other conditions potentially hazardous to human health and the environment. A written plan detailing these inspection efforts must be maintained at the facility in accordance with Washington Administrative Code (WAC), Chapter 173-303, ``Dangerous Waste Regulations`` (WAC 173-303), a written inspection plan is required for the operation of a treatment, storage and disposal (TSD) facility and individual TSD units. B Plant is a permitted TSD facility currently operating under interim status with an approved Part A Permit. Various operational systems and locations within or under the control of B ...

1996-04-26

363

Thermohydraulic study of a MTR fuel element aimed at the construction of an irradiation facility; Estudo termohidraulico de um elemento combustivel tipo MTR visando a construcao de um dispositivo de irradiacao  

Energy Technology Data Exchange (ETDEWEB)

A thermohydraulic study of MTR fuel element is presented as a basic requirement for the development of an irradiation facility for testing fuel elements. A computer code named 'Thermo' has been developed for this purpose, which can stimulate different working conditions, such as, cooling, power elements and neutron flux, performing all pertinent thermohydraulic calculations. Thermocouples were used to measure the temperature gradients of the cooling fluid throughout the IEAR-1 reactor core. All experimental data are in good agreement with the theoretical model applied in this work. Finally, a draft of the proposed facility and its safety system is presented. (author)

1980-07-01

364

The {sup 234}U neutron capture cross section measurement at the n TOF facility  

Energy Technology Data Exchange (ETDEWEB)

The neutron capture cross-section of {sup 234}U has been measured for energies from thermal up to the keV region in the neutron time-of-flight facility n-TOF, based on a spallation source located at CERN. A 4{pi} BaF{sub 2} array composed of 40 crystals, placed at a distance of 184.9 m from the neutron source, was employed as a total absorption calorimeter (TAC) for detection of the prompt {gamma}-ray cascade from capture events in the sample. This text describes the experimental setup, all necessary steps followed during the data analysis procedure. Results are presented in the form of R-matrix resonance parameters from fits with the SAMMY code and compared to the evaluated data of Endf in the relevant energy region, indicating the good performance of the n-TOF facility and the TAC. (authors)

2008-07-01

365

The status of the alpha-project  

International Nuclear Information System (INIS)

A review of the ALPHA project is presented, including a summary of progress and current status. The project comprises the experimental and analytical investigation of the long-term decay heat removal phenomena from the containment of the next generation of ''passive'' Advanced Light Water Reactors. The effects of aerosols that may result from hypothetical severe accidents are also considered. The construction of the major ALPHA experimental facilities, PANDA, LINX-2 and AIDA, has been completed. First steady-state tests have been performed on PANDA. The other facilities are now in their commissioning phases. Scaling studies have guided the design of the experimental facilities. Several small-scale experimental and studies have already produced valuable results which can be used to direct the experimental work, as well as the design of the passive ALWRs. (author). 23 refs, 6 figs.

1996-04-01

366

The first PANDA tests  

International Nuclear Information System (INIS)

The PANDA test facility at PSI in Switzerland is used to study the long-term Simplified Boiling Water Reactor (SBWRT) Passive Containment Cooling System (PCCS) performance. The PANDA tests demonstrate performance on a larger scale than previous tests and examine the effects of any non-uniform spatial distributions of steam and noncondensables in the system. The PANDA facility is in 1:1 vertical scale, and 1:25 'system' scale (volume, power, etc.). Steady-state PCCS condenser performance tests and extensive facility characterization tests have already been conducted. A series of transient system behavior tests have been completed by end of 1995. Results from the first three transient tests (M3 series) are reviewed. The first PANDA tests exhibited reproducibility, and indicated that the SBWR containment is likely to be favorably responsive and highly robust to changes in the thermal transport patterns. (author) 6 figs., 11 ...

367

The PANDA tests for SBWR certification  

International Nuclear Information System (INIS)

The ALPHA project is centered around the experimental and analytical investigation of the long-term decay heat removal from the containments of the next generation of open-quotes passiveclose quotes ALWRs. The project includes integral system tests in the large-scale (1:25 in volume) PANDA facility as well as several other series of tests and supporting analytical work. The first series of experiments to be conducted in PANDA have become a required experimental element in the certification process for the General Electric Simplified Boiling Water Reactor (SBWR). The PANDA general experimental philosophy, facility design, scaling, and instrumentation are described. Steady-state PCCS condenser performance tests and extensive facility characterization tests were already conducted. The transient system behavior tests are underway; preliminary results from the first transient test M3 are reviewed.

1996-03-01

368

Technological trends in facility management; Technologische Trends in der Gebaeudetechnik  

Energy Technology Data Exchange (ETDEWEB)

The contribution attempts a definition of the concepts of ``technical facilities`` and ``facility management``. [Deutsch] Um mit der Ueberschrift zu beginnen: Was ist Gebaeudetechnik? Die Antwort ist nicht ganz einfach. An der TU Berlin gibt es einen Ingenieur-Studiengang mit dieser Bezeichnung. Es hat etwas mit dem Gebaeude, aber nicht viel mit Architektur zu tun, wie manchmal faelschlich angenommen wird. Um solche Missverstaendnisse gar nicht erst aufkommen zu lassen, hat sich die Gruppe des Vereins Deutscher Ingenieure, die sich mit der Gebaeudetechnik beschaeftigt, als `VDI-Gesellschaft Technische Gebaeudeausruestung` bezeichnet. (orig.)

1998-12-31

369

TRACE code modeling of the horizontal steam generator of the PACTEL facility and calculation of a loss-of-feedwater experiment  

British Library Electronic Table of Contents (United Kingdom)

This paper describes the modeling of horizontal steam generator with the TRACE code and calculation results of a loss-of-feedwater (LOF-10) experiment at the PACTEL facility. Parallel Channel Test Loop (PACTEL) is an integral test facility for a VVER-440 type nuclear reactor. The main objectives were to prepare a simulation model for its horizontal steam generator with the TRACE thermal hydraulic code and assess different modeling options of the code. PACTEL experiment LOF-10 was chosen for this assessment. The calculation results showed that TRACE is capable in simulating horizontal steam generator behavior both in steady state and during loss-of-feedwater transient. The phenomenon of heat transfer from primary to secondary side, steam superheating and flow reversal in the lowest heat exc...

2010-01-01

370

Status of safety at Areva group facilities. 2007 annual report; Areva, etat de surete des installations nucleaires. Rapport annuel 2007  

Energy Technology Data Exchange (ETDEWEB)

This report describes the status of nuclear safety and radiation protection in the facilities of the AREVA group and gives information on radiation protection in the service operations, as observed through the inspection programs and analyses carried out by the General Inspectorate in 2007. Having been submitted to the group's Supervisory Board, this report is sent to the bodies representing the personnel. Content: 1 - A look back at 2007 by the AREVA General Inspector: Visible progress in 2007, Implementation of the Nuclear Safety Charter, Notable events; 2 - Status of nuclear safety and radiation protection in the nuclear facilities and service operations: Personnel radiation protection, Event tracking, Service operations, Criticality control, Radioactive waste and effluent management; 3 - Performance improvement actions; 4 - Description of the General Inspectorate; 5 - Glossary.

2007-07-01

371

Soft factor 'felt comfort'. Room air quality, an important element; Soft-Factor Wohlbefinden. Raumluftqualitaet als wichtige Grundlage  

Energy Technology Data Exchange (ETDEWEB)

Facility management has long been regarded as a cost reduction measure, but it is also a means of raising the financial worth of a building so that landlords can get higher rents or sell the building at a better price. [German] Lange Zeit wurde Facility Management als eine Massnahme zur Kostensenkung angesehen. Heutzutage zeigt sich immer mehr, dass das Facility Management sehr viel umfassender zu verstehen ist: Der Wert eines Gebaeudes bemisst sich nicht allein an einer niedrigen Kostenquote, sondern er soll umfassend Investoren wie Mietern den hoechst moeglichen Nutzen bringen. Nicht allein der kostenguenstige Betrieb ist entscheidend, sondern der Wert des Gebaeudes muss insgesamt gesteigert werden. (orig.)

2002-07-01

372

Reference equilibrium core with central flux irradiation facility for Pakistan research reactor-1  

International Nuclear Information System (INIS)

In order to assess various core parameters a reference equilibrium core with Low Enriched Uranium (LEU) fuel for Pakistan Research Reactor (PARR-1) was assembled. Due to increased volume of reference core, the average neutron flux reduced as compared to the first higher power operation. To get a higher neutron flux an irradiation facility was created in centre of the reference equilibrium core where the advantage of the neutron flux peaking was taken. Various low power experiments were performed in order to evaluate control rods worth and neutron flux mapping inside the core. The neutron flux inside the central irradiation facility almost doubled. With this arrangement reactor operation time was cut down from 72 hours to 48 hours for the production of the required specific radioactivity. (author)

2008-07-01

373

RADIONUCLIDE DATA PACKAGE FOR PERFORMANCE ASSESSMENT CALCULATIONS RELATED TO THE E-AREA LOW-LEVEL WASTE FACILITY AT THE SAVANNAH RIVER SITE.  

Energy Technology Data Exchange (ETDEWEB)

The Savannah River Site disposes of low-level radioactive waste within on-site engineered disposal facilities. The Savannah River Site must demonstrate that these disposals meet the requirements of DOE Order 435 . 1 through a process known as performance assessment (PA). The objective of this document is to provide the radionuclide -specific data needed for the PA calculations . This work is part of an on-going program to periodically review and update existing PA work as new data becomes available. Revision of the E -Area Low-Level Waste Facility PA is currently underway. The number of radionuclides selected to undergo detailed analysis in the PA is determined by a screening process. The basis of this process is described. Radionuclide-specific data for half-lives, decay modes, daughters, dose conversion factors and groundwater concentration limits are presented with source references and methodologies.

2007-03-20

374

Present status of free electron laser and its utilization research facilities  

International Nuclear Information System (INIS)

The historical back ground of free electron laser (FEL) and the present status of development and utilization research of FEL facilities in the world are explained. Eight facilities such as Stanford Univ., UCSB, Duke Univ., Vanderbilt Univ., LANL AFEL (USA), FOM FELIX (Netherlands), N-lands LURE CLIO (France) and FELI (Japan) can be used. The principle of FEL generation process is that free electrons move in a zigzag direction to generate radio waves which interfere with each other to become monochromatic light and then free electron laser. The benefits of FEL, quality of electron beam, limit of wave length of FEL, problems and development of utilization technologies of FEL are explained. (S.Y.)

1997-11-01

375

Prediction and measurement of the neutron environment in OSURR experimental facilities following conversion to LEU  

International Nuclear Information System (INIS)

Neutron energy spectra were measured for two OSURR experimental facilities. The method of multiple foil activation was used with the SAND-II neutron spectrum unfolding code to obtain spectral data for the Central Irradiation Facility and Rabbit tube. Limited data was obtained for the thermal column using only gold foils. Calculations were made of the neutron environment in various locations using the MORSE code. A shift towards higher neutron energies was observed comparing results for LEU and HEU cores. A slight loss in total thermal neutron flux was measured for all positions. Calculational results show reasonable agreement with measured data.

1993-07-01

376

New thermal neutron imaging facility at the University of Texas reactor  

Energy Technology Data Exchange (ETDEWEB)

A thermal neutron imaging facility for real-time neutron radiography and computed tomography has recently been developed at the University of Texas TRIGA reactor. Extensive Monte Carlo design calculations were used to determine optimal design parameters of the neutron collimator system to avoid costly trial and error. Thermal neutron flux determined by gold foil activation is 5 {times} 10{sup 6} n/cm{sup 2}{center_dot}s at the primary imaging location with beam size of 22.5 cm in diameter. The collimation ratio can be varied from 125 to 235. The neutron-to-gamma ratio is 7.8 {times} 10{sup 6} n/cm{sup 2}{center_dot}mR. The facility has been tested for radiography and tomography applications and is now fully operational.

1999-09-01

377

Negotiating equity for management of DOE wastes  

Energy Technology Data Exchange (ETDEWEB)

One important factor frustrating optimal management of Department of Energy (DOE)-complex wastes is the inability to use licensed and permitted facilities systematically. Achieving the goal of optimal use of DOE`s waste management facilities is politically problematic for two reasons. First, no locale wants to bear a disproportionate burden from DOE wastes. Second, the burden imposed by additional wastes transported from one site to another is difficult to characterize. To develop a viable framework for equitably distributing these burdens while achieving efficient use of all DOE waste management facilities, several implementation and equity issues must be addressed and resolved. This paper discusses stakeholder and equity issues and proposes a framework for joint research and action that could facilitate equity negotiations among stakeholder and move toward a more optimal use of DOE`s waste management capabilities.

1994-09-01

378

Long-term, low-level radwaste volume-reduction strategies. Volume 3. Characterization of low-level radwaste volume-reduction installations. Final report  

Energy Technology Data Exchange (ETDEWEB)

This study characterized selected commercial volume reduction technologies as to performance and associated costs. VR facility designs were developed for each of the reference VR technologies. Associated on-site storage requirements and cost were also determined. Eight VR technologies were selected for consideration: improved compactor; high pressure compactor (supercompactor); incinerator; fluid bed dryer and incinerator; evaporator crystallizer; evaporator extruder; mobile incinerator; and mobile thin-film evaporator. A representative facility design was developed for each VR technology and for several combinations of technologies. Thirteen separate cases are noted in the following table when retrofit and new facilities are considered.

1984-11-01

379

Imaging automation and volume tomographic visualization at Texas Neutron Imaging Facility  

Energy Technology Data Exchange (ETDEWEB)

A thermal neutron imaging facility for real-time neutron radiography and computed tomography has been developed at the University of Texas reactor. The facility produced a good-quality radiographs and two-dimensional tomograms. Further developments have been recently accomplished. Further developments have been recently accomplished. A computer software has been developed to automate and expedite the data acquisition and reconstruction processes. Volume tomographic visualization using Interactive Data Language (IDL) software has been demonstrated and will be further developed. Volume tomography provides the additional flexibility of producing slices of the object using software and thus avoids redoing the measurements.

1999-07-01

380

Facilities evaluation report  

Energy Technology Data Exchange (ETDEWEB)

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.

1992-04-01

381

FFTF [Fast Flux Test Facility] management  

International Nuclear Information System (INIS)

Fuel Management at the Fast Flux Test Facility (FFTF) involves more than just the usual ex-core and in-core management of standard fuel and non-fuel components between storage locations and within the core since it is primarily an irradiation test facility. This mission involves testing an ever increasing variety of fueled and non-fueled experiments, each having unique requirements on the reactor core as well as having its own individual impact on the reload design. This paper describes the fuel management process used by the Westinghouse Hanford Company Core Engineering group that has led to the successful reload design of nine operating cycles and the irradiation of over 120 tests.

1987-09-13

382

ETE-EVAL: a methodology for D and D cost estimation  

International Nuclear Information System (INIS)

In compliance with Article 20 of the sustainable radioactive materials and waste management act dated 28 June 2006, the CEA and AREVA are required every three years to revise the cost of decommissioning their facilities and to provide the necessary assets by constituting a dedicated fund. For the 2007 revision the CEA used ETE-EVAL V5. Similarly, AREVA reevaluated the cost of decontaminating and dismantling its facilities at La Hague, as the previous estimate in 2004 did not take into account the complete cleanup of all the structural work. ETE-EVAL V5 is a computer application designed to estimate the cost of decontamination and dismantling of basic nuclear installations (INB). It has been qualified by Bureau Veritas and audited. ETE-EVAL V5 has become the official software for cost assessment of CEA civilian and AREVA decommissioning projects. It has been used by the DPAD (Decontamination and Dismantling Projects Department) cost assessment ...

383

Dose consequences from a postulated criticality occurring in a low-level waste disposal facility  

Energy Technology Data Exchange (ETDEWEB)

Evaluations were done to determine conditions that could permit nuclear criticality with fissile uranium in low-level waste (LLW) facilities and to estimate potential radiation exposures to personnel if there were such an accident. Simultaneous hydrogeochemical and nuclear criticality studies were done (1) to identity realistic scenarios for uranium migration and concentration increase at LLW disposal facilities, (2) to model groundwater transport of uranium and subsequent concentration via sorption or precipitation, (3) to evaluate the potential for nuclear criticality resulting from potential increases in uranium concentration over disposal limits, and (4) to estimate potential radiation exposures to personnel resulting from criticality consequences. This paper presents the details of the radiation exposure calculations relying on the conditions as determined from the preceding studies detailed in a cited reference.

1997-12-01

384

Diagnostics hardening for harsh environment in Laser Megajoule (invited)  

International Nuclear Information System (INIS)

The diagnostic designs for the Laser Megajoule (LMJ) will require components to operate in environments far more severe than those encountered in present facilities. This harsh environment will be induced by fluxes of neutrons, gamma rays, energetic ions, electromagnetic radiations, and, in some cases, debris and shrapnel, at levels several orders of magnitude higher than those experienced today on existing facilities. The lessons learned about the vulnerabilities of present diagnostic parts fielded mainly on OMEGA for many years, have been very useful guide for the design of future LMJ diagnostics. The present and future LMJ diagnostic designs including this vulnerability approach and their main mitigation techniques will be presented together with the main characteristics of the LMJ facility that provide for diagnostic protection.

2008-10-01

385

Development of in-vessel reflood instrumentation at ORNL  

International Nuclear Information System (INIS)

A program under the sponsorship of the United States Nuclear Regulatory Commission was intiated at the Oak Ridge National Laboratory (ORNL) in late 1977. The program, Advanced Instrumentation for Reflood Studies (AIRS), is charged with developing instrumentation for measurement of in-vessel fluid phenomena in pressurized water reactor reflood facilities. The goal of the ORNL program is to develop techniques and systems for measuring fluid flow in-core, deentrainment in the upper plenum and liquid fallback from the upper plenum into the core. A large portion of the development at ORNL is devoted to the impedance probes for measurement of two-phase flow velocities and void fractions. Film probe development at ORNL is limited to adapting the present techniques to the environment of a reflood facility. As the development progresses on all the measurement techniques, ORNL will fabricate and supply instrument systems to the reflood ...

2004-09-06

386

Coal-liquefaction-process research quarterly report, January 1 - March 31, 1982  

Science.gov (United States)

Objectives of the program are to understand the mechanisms of coal liquefaction, to determine the role of catalysts in the direct conversion of coal to liquids, to determine the mechanism of catalyst deactivation and to explore slurry phase catalyst systems. Specific projects include: short-contact time coal liquefaction, mineral matter effects and catalyst studies. During this period, work was performed on: (1) the stability, at reaction temperature, of a recycle solvent obtained from the Lummus Two Stage Liquefaction facility, (2) reactions of preasphaltenes and asphaltenes prepared under various reaction severities, (3) the evaluation of the catalyst level detector installed at the H-Coal facility, (4) the characterization of oil soluble metal compounds with respect to hydrogenation activity, and (5) characterization, deactivation and regeneration of catalysts obtained from both the H-Coal and Lummus facilities.

1982-10-01

387

Application of probabilistic methods to accident analysis at waste management facilities  

International Nuclear Information System (INIS)

Probabilistic risk assessment is a technique used to systematically analyze complex technical systems, such as nuclear waste management facilities, in order to identify and measure their public health, environmental, and economic risks. Probabilistic techniques have been utilized at the Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico, to evaluate the probability of a catastrophic waste hoist accident. A probability model was developed to represent the hoisting system, and fault trees were constructed to identify potential sequences of events that could result in a hoist accident. Quantification of the fault trees using statistics compiled by the Mine Safety and Health Administration (MSHA) indicated that the annual probability of a catastrophic hoist accident at WIPP is less than one in 60 million. This result allowed classification of a catastrophic hoist accident as ''not credible'' at WIPP per DOE definition. Potential uses of probabilistic ...

388

1 The German National Analysis Facility as a tool for ATLAS analyses  

CERN Document Server

In 2008 the German National Analysis Facility (NAF) at DESY was established. It is attached to and builds on top of DESY Grid infrastructure. The facility is designed to provide the best possible analysis infrastructure for high energy particle physics of the ATLAS, CMS, LHCb and ILC experiments. The Grid and local infrastructure of the NAF is reviewed with a focus on the ATLAS part. Both parts include large scale storage and a batch system. Emphasis is put on ATLAS specific customisation and utilisation of the NAF. This refers not only to the NAF components but also to the di erent components of the ATLAS analysis framework. Experience from operating and supporting ATLAS users on the NAF is presented in this paper. The ATLAS usage of the di erent components are shown including some typical use cases of user analysis. Finally, the question is addressed, if the design of the NAF meets the ATLAS expectations for effcient data analysis in the era ...

2011-01-01

389

hysics Facility - NASA  

Science.gov (United States)

vehicles including the H2-A rocket and the space shuttle. .... The vacuum can's main function is to provide a high vacuum so that the science experiment and its sensors ... EMI-shielded power conversion from the incoming ISS power supply. 4. ...

390

Waste Handeling Building Conceptual Study  

Energy Technology Data Exchange (ETDEWEB)

The objective of the ''Waste Handling Building Conceptual Study'' is to develop proposed design requirements for the repository Waste Handling System in sufficient detail to allow the surface facility design to proceed to the License Application effort if the proposed requirements are approved by DOE. Proposed requirements were developed to further refine waste handling facility performance characteristics and design constraints with an emphasis on supporting modular construction, minimizing fuel inventory, and optimizing facility maintainability and dry handling operations. To meet this objective, this study attempts to provide an alternative design to the Site Recommendation design that is flexible, simple, reliable, and can be constructed in phases. The design concept will be input to the ''Modular Design/Construction and Operation Options Report'', ...

2000-11-06

391

Utility of Recycled Bedding for Laboratory Rodents  

UK PubMed Central (United Kingdom)

Animal facilities generate a large amount of used bedding containing excrement as medical waste. We developed a recycling system for used bedding that involves soft hydrothermal processing. In this...Full Text Available

2009-07-01

392

The cascad spent fuel dry storage facility  

International Nuclear Information System (INIS)

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 ...

1991-04-14

393

Telephone reliability of the Frenchay Activity Index and EQ-5D amongst older adults  

UK PubMed Central (United Kingdom)

BackgroundOlder adults may find it problematic to attend hospital appointments due to the difficulty associated with travelling to, within and from a hospital facility for the purpose...Full Text Available

394

THE EFFECTS OF RESPONSE EFFORT ON SAFE PERFORMANCE BY THERAPISTS AT AN AUTISM TREATMENT FACILITY  

UK PubMed Central (United Kingdom)

The effects of response effort on safe behaviors (i.e., glove wearing, hand sanitizing, and electrical outlet replacement) exhibited by therapists at an autism treatment center were examined. Participants...Full Text Available

2010-01-01

395

THE ANAEROBIC TREATMENT OF WASTES CONTAINING RECALCITRANT AND INHIBITORY COMPOUNDS  

Environmental Research Database

ObjectivesObjectives Not AvailableDescriptionA collaborative study of the anaerobic treatment of wastes containing recalcitrant and inhibitory compounds using the SERC Anaerobic facility, in particular biomass structure, monitoring and control, catabolism and toxicity, pre-acidification and microbial growth and mesophilic and thermophilic lignocellulose degradation.~%~

1995-01-20

396

T Plant secondary containment and leak detection upgrades  

Energy Technology Data Exchange (ETDEWEB)

The W-259 project will provide upgrades to the 2706-T/TA Facility to comply with Federal and State of Washington environmental regulations for secondary containment and leak detection. The project provides decontamination activities supporting the environmental restoration mission and waste management operations on the Hanford Site.

1995-10-19

397

Surprising Alteration of Antibacterial Activity of 5?-Modified Neomycin against Resistant Bacteria  

UK PubMed Central (United Kingdom)

A facile synthetic protocol for the production of neomycin B derivatives with various modifications at the 5″ position has been developed. Structural activity relationship (SAR) against...Full Text Available

2008-12-11

398

Study on the transient piping vibration of power plant. Secondary piping system of Wolsung 1 unit.  

Science.gov (United States)

In order to maintain a safe operation and availability of generating facilities, qualitative and quantitative assessment of piping vibration was performed vibration sources and damages of piping support was identified on the second piping system of Wolsun...

1996-01-01

399

Status of the Lawrence Berkeley Laboratory and Lawrence Livermore National Laboratory free electron laser (FEL)  

Energy Technology Data Exchange (ETDEWEB)

A description of the FEL experiment underway at the 10 kA, 5 MeV Experimental Test Accelerator (ETA) is described. The facility has been designed to investigate the high-gain operation of an FEL.

1983-09-19

400

Software Configuration Management Plan for the Sodium Removal System  

Energy Technology Data Exchange (ETDEWEB)

This document establishers the Software Configuration Management Plan (SCMP) for the software associated with the control system of the Sodium Removal System (SRS) located in the Interim Examination and Maintenance (IEM Cell) Facility of the FFTF Flux Test.

2000-03-06

401

Shield-verification survey of a large hot cell at the FFTF  

Energy Technology Data Exchange (ETDEWEB)

This paper describes a radiation shield verification survey of a large hot cell at the Fast Flux Test Facility (FFTF). The following aspects of the shield test are discussed: description of the FFTF; description of the hot cell; the test procedures; radiation protection, and the test results.

1980-01-01

402

SOW for Services Provided by the Waste Sampling Characterization Facility (WSCF) for the Environmental Compliance Program during CY 2000  

Energy Technology Data Exchange (ETDEWEB)

This document defines analytical services the Waste Sampling and Characterization Facility (WSCF) shall provide the Environmental Compliance Program (ECP) throughout calendar year (CY) 2000. Two organizations within ECP are responsible for monitoring liquid and gaseous effluents and the environment immediately around facilities that contain or may contain radioactive and hazardous materials. Monitoring & Reporting (M&R), of Fluor Hanford Environmental Services, is responsible for effluent monitoring data, and Environmental Monitoring & Investigations (EMI), of Waste Management Technical Services, Inc., for near-facility environmental monitoring data. These organizations serve numerous projects, some of which are managed by other companies such as CH2M HILL and Bechtel Hanford, Inc. Monitoring data are collected and evaluated to determine their state of compliance with applicable federal and state regulations ...

2000-06-01

403

Revised neutron dosimetry results for the MOTA-2A experiment in FFTF  

Energy Technology Data Exchange (ETDEWEB)

Revised neutron fluence and damage values are reported for the MOTA-2A experiment in the Fast Flux Test Facility (FFTF). This revision corrects an error with processing of the {sup 235}U(n,f) reaction. Net corrections are on the order of 5%.

1994-09-01

404

Real-time neutron beam monitor  

Energy Technology Data Exchange (ETDEWEB)

An array of multiwire proportional counters has been employed to image, in 'real-time', a collimated neutron beam produced at an electron linac facility. Test results are presented, along with a discussion of the advantages of this technique.

1983-06-15

405

Radiation hardening of diagnostics  

International Nuclear Information System (INIS)

The world fusion program has advanced to the stage where it is appropriate to construct a number of devices for the purpose of burning DT fuel. In these next-generation experiments, the expected flux and fluence of 14 MeV neutrons and associated gamma rays will pose a significant challenge to the operation and diagnostics of the fusion device. Radiation effects include structural damage to materials such as vacuum windows and seals, modifications to electrical properties such as electrical conductivity and dielectric strength and impaired optical properties such as reduced transparency and luminescence of windows and fiber optics during irradiation. In preparation for construction and operation of these new facilities, the fusion diagnostics community needs to work with materials scientists to develop a better understanding of radiation effects, and to undertake a testing program aimed at developing workable solutions for this multi-faceted problem. A unique ...

406

RCRA Facilities Assessment (RFA)---Oak Ridge National Laboratory  

Energy Technology Data Exchange (ETDEWEB)

US Department of Energy (DOE) facilities are required to be in full compliance with all federal and state regulations. In response to this requirement, the Oak Ridge National Laboratory (ORNL) has established a Remedial Action Program (RAP) to provide comprehensive management of areas where past and current research, development, and waste management activities have resulted in residual contamination of facilities or the environment. This report presents the RCRA Facility Assessment (RFA) required to meet the requirements of RCRA Section 3004(u). Included in the RFA are (1) a listing of all sites identified at ORNL that could be considered sources of releases or potential releases; (2) background information on each of these sites, including location, type, size, period of operation, current operational status, and information on observed or potential releases (as required in Section II.A.1 of the RCRA permit); (3) ...

1987-03-01

407

Quality Assurance Program Plan for spent fuel handling and packaging  

Science.gov (United States)

This plan describes the Quality Assurance Program which will be applied to spent fuel handling and packaging tests conducted at the Area 25 E-MAD facility, Nevada Test Site (NTS).

1979-01-31

408

Pyridinium based amphiphilic hydrogelators as potential antibacterial agents  

UK PubMed Central (United Kingdom)

SummaryThe numerous applications of hydrogelators have led to rapid expansion of this field. In the present work we report the facile synthesis of amphiphilic hydrogelators having a quaternary...Full Text Available

409

Proton storage ring (PSR) diagnostics and control system  

Energy Technology Data Exchange (ETDEWEB)

When any new accelerator or storage ring is built that advances the state of the art, the diagnostic system becomes extremely important in tuning the facility to full specification. This paper will discuss the various diagnostic devices planned or under construction for the PSR and their connection into the control system.

1983-01-01

410

Project resumes: biological effects from electric fields associated with high-voltage transmission lines  

Energy Technology Data Exchange (ETDEWEB)

Abstracts of research projects are presented in the following areas: measurements and special facilities; cellular and subcellular studies; physiology; behavior; environmental effects; modeling, scaling and dosimetry; and high voltage direct current. (ACR)

1980-01-01

411

Process energy management  

Energy Technology Data Exchange (ETDEWEB)

In many facilities, energy management is simply a matter of managing the energy required for lighting and space conditioning. In many others, however, energy management is much more complex and involves large motors and controls, industrial insulation, complex combustion monitoring, unique steam distribution problems, significant amounts of waste heat, etc. Typical facilities offering large energy management opportunities include industrial facilities, large office and commercial operations, government institutions such as schools, hospitals and prisons. Such facilities generally have specialized industrial, commercial or institutional processes that incorporate many of the concepts covered in other chapters. These processes require thorough analytical evaluations to determine the appropriate energy-saving measures. This chapter provides some examples. In this chapter the authors present a suggested ...

1994-12-31

412

Possible explosive compounds in the Savannah River Site waste tank farm facilities  

Energy Technology Data Exchange (ETDEWEB)

This report will be revised upon completion of current testing investigating the radiolytic stability of additional energetic materials and the analysis of tank farm samples for volatile and semi-volatile organic compounds.

2000-04-13

413

Plan and justification for a Proof-of-Concept oil shale facility. Final report  

Energy Technology Data Exchange (ETDEWEB)

The technology being evaluated is the Modified In-Situ (MIS) retorting process for raw shale oil production, combined with a Circulating Fluidized Bed Combustor (CFBC), for the recovery of energy from the mined shale. (VC)

1990-12-01

414

Plan and justification for a Proof-of-Concept oil shale facility  

Energy Technology Data Exchange (ETDEWEB)

The technology being evaluated is the Modified In-Situ (MIS) retorting process for raw shale oil production, combined with a Circulating Fluidized Bed Combustor (CFBC), for the recovery of energy from the mined shale. (VC)

1990-12-01

415

Mound Facility explosives incinerator  

Energy Technology Data Exchange (ETDEWEB)

The design and performance of small incinerators used at the Mound Laboratory for the disposal of explosives are described. These units, which cost less than $1000 each, are about the size of a 55-gal drum, have water jackets for cooling, and have provided a flexible, efficient, and clean burning explosives disposal unit. (LCL)

1980-01-01

416

Mortality of persons resident in the vicinity of electricity transmission facilities.  

UK PubMed Central (United Kingdom)

Several studies have raised the possibility that exposure to electrical and/or magnetic fields may be injurious to health in particular by the promotion or initiation of cancer. To investigate whether...Full Text Available

1986-02-01

417

Ion sources for initial use at the Holifield radioactive ion beam facility  

Energy Technology Data Exchange (ETDEWEB)

The Holifield Radioactive Ion Beam Facility (HRIBF) now under construction at the Oak Ridge National Laboratory will use the 25-MV tandem accelerator for the acceleration of radioactive ion beams to energies appropriate for research in nuclear physics; negative ion beams are, therefore, required for injection into the tandem accelerator. Because charge exchange is an efficient means for converting initially positive ion beams to negative ion beams, both positive and negative ion sources are viable options for use at the facility; the choice of the type of ion source will depend on the overall efficiency for generating the radioactive species of interest. A high-temperature version of the CERN-ISOLDE positive ion source has been selected and a modified version of the source designed and fabricated for initial use at the HRIBF because of its low emittance, relatively high ionization efficiencies and species versatility, and because it has been ...

1994-12-31

418

Ion sources for initial use at the Holifield Radioactive Ion Beam Facility  

Energy Technology Data Exchange (ETDEWEB)

The Holifield Radioactive Ion Beam Facility (HRIBF) now under construction at the Oak Ridge National Laboratory will use the 25-MV tandem accelerator for the acceleration of radioactive ion beams to energies appropriate for research in nuclear physics; negative ion beams are, therefore, required for injection into the tandem accelerator. Because charge exchange is an efficient means for converting initially positive ion beams to negative ion beams, both positive and negative ion sources are viable options for use at the facility; the choice of the type of ion source will depend on the overall efficiency for generating the radioactive species of interest. A high-temperature version of the CERN-ISOLDE positive ion source has been selected and a modified version of the source designed and fabricated for initial use at the HRIBF because of its low emittance, relatively high ionization efficiencies and species versatility, and because it has been ...

1994-05-01

419

Hazard Evaluation and Technical Assistance Report No. TA 76-100, ASARCO, East Helena, Montana.  

Science.gov (United States)

A Hazard Evaluation and Technical Assistance investigation was performed by NIOSH on February 1-4, 1977, at ASARCO, East Helena, Montana, a facility engaged in lead smelting. The survey was prompted by a request from the Regional OSHA Director in referenc...

1977-01-01

420

Guided Cell Migration on Microtextured Substrates with Variable Local Density and Anisotropy  

UK PubMed Central (United Kingdom)

This work reports the design of and experimentation with a topographically patterned cell culture substrate of variable local density and anisotropy as a facile and efficient platform to guide...Full Text Available

2009-02-06

421

Forschungszentrum Juelich, Institut fuer Kernphysik/COSY. Annual report 2004  

Energy Technology Data Exchange (ETDEWEB)

The following topics are dealt with: Detectors at COSY, major physics results at COSY, physics at external facilities, theoretical investigations, COSY operation and developments, preparations for FAIR, technical developments. (HSI)

2005-03-01

422

Fast Flux Test Facility Reactor Vessel Removal Study  

Energy Technology Data Exchange (ETDEWEB)

This study assesses the feasibility of removing the FFTF reactor vessel from its current location in the reactor cavity inside the Containment vessel to a transporter for relocation to a burial pit in the 200 Area.

2002-10-23

423

FELIX Experiments: Measurements of Electromagnetic Effects.  

Science.gov (United States)

Three major series of experiments have been conducted with the FELIX facility at ANL. Experiments on the coupling between eddy currents and angular displacements of loops and plates in crossed constant and changing magnetic fields demonstrated that the co...

1985-01-01

424

Examination of scaling criteria for nuclear reactor thermal-hydraulic test facilities  

International Nuclear Information System (INIS)

Scaling criteria for a natural-circulation loop are examined. The present state of knowledge of scaling to obtain similarity during single- and two-phase flow conditions in a closed loop are reviewed, and an alternative development of two-phase similarity parameters is presented. The loop scaling criteria are the results of analyses in which flow from one component to another is considered. In this work, boundary conditions for the closed loop are developed to obtain scaling criteria for leak flow, injection flow, and heat loss to ambient. The leak scaling criteria are specialized for modeling approaches using prototypic fluid at prototypic or reduced pressures. The derived scaling parameters are examined for their application to two existing scaled test facilities: the Multi-Loop Integral System Test (MIST) facility at Babcock and Wilcox, and the UMCP 2 x 4 facility at the University of Maryland College Park. The heat loss ...

1987-01-01

425

Entombment Using Cementitious Materials: Design Considerations and International Experience  

Energy Technology Data Exchange (ETDEWEB)

Cementitious materials have physical and chemical properties that are well suited for the requirements of radioactive waste management. Namely, the materials have low permeability and durability that is consistent with the time frame required for short-lived radionuclides to decay. Furthermore, cementitious materials can provide a long-term chemical environment that substantially reduces the mobility of some long-lived radionuclides of concern for decommissioning (e.g., C-14, Ni-63, Ni-59). Because of these properties, cementitious materials are common in low-level radioactive waste disposal facilities throughout the world and are an attractive option for entombment of nuclear facilities. This paper describes design considerations for cementitious barriers in the context of performance over time frames of a few hundreds of years (directed toward short-lived radionuclides) and time frames of thousands of years (directed towards longer-lived ...

2002-08-01

426

Entombment Using Cementitious Materials: Design Considerations and International Experience  

Energy Technology Data Exchange (ETDEWEB)

Cementitious materials have physical and chemical properties that are well suited for the requirements of radioactive waste management. Namely, the materials have low permeability and durability that is consistent with the time frame required for short-lived radionuclides to decay. Furthermore, cementitious materials can provide a long-term chemical environment that substantially reduces the mobility of some long-lived radionuclides of concern for decommissioning (e.g., C-14, Ni-63, Ni-59). Because of these properties, cementitious materials are common in low-level radioactive waste disposal facilities throughout the world and are an attractive option for entombment of nuclear facilities. This paper describes design considerations for cementitious barriers in the context of performance over time frames of a few hundreds of years (directed toward short-lived radionuclides) and time frames of thousands of years (directed towards longer-lived ...

2002-05-15

427

Energy Surveys of Army Industrial Facilities Energy ...  

Science.gov (United States)

Page 1. Page 2. Page 3. Page 4. Page 5. Page 6. Page 7. Page 8. Page 9. Page 10. Page 11. Page 12. Page 13. Page 14. Page 15. Page 16. Page ...

1990-11-01

428

Economic Impact Analysis of Proposed Effluent Limitations Guidelines and Standards for the Pesticide Manufacturing Industry.  

Science.gov (United States)

The report details the economic impact of two alternative regulatory options; a Treated Discharge Option and a Zero Discharge Option on facilities that would have to comply with the regulations as part of the reproposal of effluent limitations and standar...

1992-01-01

429

Development on the technology for tritium removal processes (II).  

Science.gov (United States)

In order to decrease tritium exposure to workers, the ratio of which is up to 40% of total exposure, tritium removal facility is getting to be one of the considerable parameters in Korea, due to the next CANDUs to be operated at Wolsung NPP. For investiga...

1993-01-01

430

Development on the cryogenic hydrogen isotopes distillation process technology for tritium removal (Final report).  

Science.gov (United States)

While tritium exposure to the site-workers in Wolsung NPP is up to about 40% of the total personnel exposure, Ministry of Science and Technology has asked tritium removal facility for requirement of post heavy-water reactor construction. For the purpose o...

1995-01-01

431

Development Document for Proposed Effluent Limitations Guidelines and Standards for the Porcelain Enameling Point Source Category.  

Science.gov (United States)

This document is a technical background document for proposed regulations to limit effluent discharges to waters of the United States and introductions of pollutants into publicly owned treatment works from facilities engaged in porcelain enameling. The p...

1981-01-01

432

Developing a Performance Measurement Framework and Indicators for Community Health Service Facilities in Urban China  

UK PubMed Central (United Kingdom)

BackgroundChina has had no effective and systematic information system to provide guidance for strengthening PHC (Primary Health Care) or account to citizens on progress. We report...Full Text Available

433

Design for environment for the National Ignition Facility  

Energy Technology Data Exchange (ETDEWEB)

The National Ignition Facility (NIF) will be a U.S. Department of Energy (DOE) national center for inertial confinement fusion (ICF) and other research into the physics of high temperatures and high densities, and a vital element of the DOE`s nuclear weapons Stockpile Stewardship and Management Program. It will be used by scientists from a numerous different institutions and disciplines to support research advancements in national security, energy, basic science, and economic development. Multiple powerful laser beams will `ignite` small fusion targets, helping liberate more energy than is required to initiate the fusion reactions. This paper discusses the Design for Environment process for NIF, some of the subsequent activities resulting from the initial study, and a few of the lessons learned from this process. Subsequent activities include the development of a Pollution Prevention and Waste Minimization Plan (P2/WMin) for the facility, which ...

1998-05-01

434

Demonstration of Black Liquor Gasification at Big Island  

Energy Technology Data Exchange (ETDEWEB)

This Final Technical Report provides an account of the project for the demonstration of Black Liquor Gasification at Georgia-Pacific LLC's Big Island, VA facility. This report covers the period from May 5, 2000 through November 30, 2006.

2007-04-14

435

Degradation of the Ferric Chelate of EDTA by a Pure Culture of an Agrobacterium sp  

UK PubMed Central (United Kingdom)

A pure culture of an Agrobacterium sp. (deposited as ATCC 55002) that mineralizes the ferric chelate of EDTA (ferric-EDTA) was isolated by selective enrichment from a treatment facility...Full Text Available

1990-11-01

436

Core technologies for Tritium removal processes (I).  

Science.gov (United States)

In case of operating both Wolsung Nuclear Units 1 and 2 without operating tritium removal facilities, it is estimated that tritium in 2013 would be accumulated up to about 30 million Ci that would result in about 2,300 man-rem of tritium exposure to opera...

1992-01-01

437

Core Synthesis Facility: Bridging the Gap between Chemistry and Biology  

UK PubMed Central (United Kingdom)

CF-23“The biggest stumbling block for biological sciences turned out to be synthetic organic chemistry” – Elias A. Zerhouni, Former NIH Director in Chemical...Full Text Available

2010-09-01

438

Conversion of the Midland nuclear station  

Energy Technology Data Exchange (ETDEWEB)

The authors report how the Midland cogeneration venture (MCV) is repowering the incomplete Midland nuclear plant to operate as a gas-fired combined cycle cogeneration facility. They discuss how their company is responsible for performing engineering, procurement, licensing, construction, start-up, training, and operational assistance for this facility. As shown, twelve gas turbine generator sets supply heat to twelve heat recovery steam generators (HRSGs), which are headered together on the steam side to provide energy to either of two existing steam turbine generators. This combination of equipment enables approximately 1,380 MWe of electrical generation capability, while supplying an average steam flow of 629,000 lbs/hr to an adjacent Dow Chemical Company pant. The MCV facility will also provide 60 MW of electric power to Dow. The authors report how the Midland ccogeneration venture (MCV) is repowering the incomplete ...

1988-01-01

439

Computing needs of the superconducting super collider  

Energy Technology Data Exchange (ETDEWEB)

Following a brief description of the SSC, the computing needs are discussed for both the accelerator design and the experimentation. The computing power required is considerably beyond that being used at present facilities, and parallel processing is expected to play an important role in supplying these needs.

1984-01-01

440

Compliance with the new emissions guidelines for existing municipal waste combustion facilities  

Energy Technology Data Exchange (ETDEWEB)

The EPA proposed air emission guidelines for existing Municipal Waste Combustion (MWC) facilities on December 20, 1989. The regulation, 40 CFR Subpart Ca, was eventually issued on February 11, 1991, but Section 129 of the Clean Air Act Amendments of 1990 required the EPA to review and revise the regulations. On October 31, 1995, Subpart Ca was withdrawn and replaced by a more stringent regulation, 40 CFR Subpart Cb. The new guidelines apply to all existing MWC facilities for which construction began before September 20, 1994 and have a capacity to combust over 35 megagrams per day. Most facilities will be required to be in compliance with the new regulations four years from the date Subpart Cb was issued, or by December 19, 1999. Subpart Cb requires significant capital expenditures and increases in operating costs. The major modifications EPA based the guidelines on are summarized. Pollutants of concern include sulfur ...

1996-09-01

441

CASCAD dry storage concept for spent fuel  

International Nuclear Information System (INIS)

Further to a cost-benefit analysis of the various medium-term and long-term and H.L.W. storage possibilities, C.E.A. (French Atomic Energy Commission) and S.G.N. decided to develop an original dry storage process with natural convection cooling that offers many advantages: cut in the total investment and operating costs; high operating safety; natural convection cooling; existence of two containment barriers irrespective of the assumed clad conditions; flexible, modular and compact design. The process was first implemented in the so-called CASCAD Cadarache Facility (vault-type facility) constructed in Cadarache mainly to store fuel from Brennilis heavy water reactor. For the purpose, a large program was set up to develop and validate computer codes, in particular with the use of mockups. On the request of many clients, and owing to the outstanding operating results of the CASCAD Cadarache Facility, SGN was brought to adapt ...

1994-08-01

442

BOOKMARKS:  

Wastenet

Secretariat of the Basel Convention United Nations Office at Geneva ...such as public utilities, waste disposal sites, large energy dependent facilities including factories, institutions (hospitals, ...it provides immediate identification of PCB wastes, informs company officials of any special handling or disposal techniques

443

Assessing the effects of the HIPAA privacy rule on release of patient information by healthcare facilities.  

Science.gov (United States)

The HIPAA privacy rule (HIPAA) has had both positive and negative effects on the release of patient information by healthcare facilities. Although the intention of HIPAA was to protect patient privacy and to promote security and confidentiality of patient information, it has had unintended consequences for facilities. To identify some of these unintended effects, two expert panels of health information management directors from healthcare facilities participated in the nominal group technique meetings. They identified 70 barriers related to release of patient information associated with the implementation of HIPAA. The perceived biggest barriers were increases in the public's misunderstanding about release of patient information, lack of an umbrella policy or regulation defining infractions and enforcement that allows individual institutions to make their own interpretations, and challenges to health information management ...

2007-03-23

444

Application of robotics in remote fuel fabrication operations  

International Nuclear Information System (INIS)

The Secure Automated Fabrication (SAF) line, an automated and remotely controlled manufacturing process, is scheduled for startup in 1987 and will produce mixed uranium/plutonium oxide fuel pins for the Fast Flux Test Facility (FFTF). The application of robotics in the fuel fabrication and supporting operations is described.

445

An outbreak of illness among aerospace workers.  

UK PubMed Central (United Kingdom)

A multispecialty panel of physicians evaluated a case series of 53 composite-materials workers in a large aircraft manufacturing facility who filed workers' compensation claims for illness labeled by...Full Text Available

1990-07-01

446

An investigation of enzootic Glasser's disease in a specific-pathogen-free grower-finisher facility using restriction endonuclease analysis  

UK PubMed Central (United Kingdom)

Enzootic Glassers's disease was investigated to study the epidemiology of the disease strains on a farm where it presented a problem. Restriction endonuclease fingerprinting (REF) analysis technique...Full Text Available

1993-08-01

447

Advanced Neutron Source: Plant Design Requirements. Revision 4  

Energy Technology Data Exchange (ETDEWEB)

The Advanced Neutron Source will be a new world-class facility for research using hot, thermal, cold, and ultra-cold neutrons. The heart of the facility will be a 330-MW (fission), heavy-water cooled and heavy-water moderated reactor. The reactor will be housed in a central reactor building, with supporting equipment located in an adjoining reactor support building. An array of cold neutron guides will fan out into a large guide hall, housing about 30 neutron research stations. Appropriate office, laboratory, and shop facilities will be included to provide a complete facility for users. The ANS is scheduled to begin operation at the Oak Ridge National Laboratory early in the next decade. This PDR document defines the plant-level requirements for the design, construction, and operation of ANS. It also defines and provides input to the individual System Design Description (SDD) documents. Together, this ...

1990-07-01

448

A real-time neutron beam monitor  

International Nuclear Information System (INIS)

An array of multiwire proportional counters has been employed to image, in 'real-time', a collimated neutron beam produced at an electron linac facility. Test results are presented, along with a discussion of the advantages of this technique. (orig.).

1983-06-01

449

40 CFR 63.321 - Definitions.  

Science.gov (United States)

...limited to, emission control devices, pumps, filters, muck cookers, stills, solvent tanks, solvent containers, water separators...facility that meets the conditions of § 63.320(g). Muck cooker means a device for heating perchloroethylene-laden...

2009-07-01

450

32 CFR 552.18 - Administration.  

Science.gov (United States)

...Seeing-eye or guide dogs will remain in guiding...possible agitation of military police working dogs, seeing-eye or guide...allowed in or around working dog kennels and facilities...used for registering military personnel on...

2010-07-01

451

Spectroscopy of /sup 87,88,89/Sr with (n,. gamma. ) and (d,p) reactions  

Science.gov (United States)

Over the recent years the nuclear structure around the N = 50 shell closure, which is very pronounced in the strontium and zirconium isotopes, has been the subject of extensive experimental and theoretical work. On the proton side Z = 38 and Z = 40 provide fairly closed sub-shells. In the strontium isotopes the lg/sub 9/2/ neutron shell is closed at /sup 88/Sr, supplying relatively pure neutron-hole and neutron-particle states with large spectroscopic factors in /sup 87/Sr and /sup 89/Sr, as well as core-coupled states. The mass region is thus ideally suited to examine the transition from a correlated to an uncorrelated (chaotic.) excitational behavior. These two types are characterized e.g. by the density of excited states, the transition strengths, and the spectroscopic factors observed in transfer reactions. We conducted (n,..gamma..) and (d,p) reactions leading to /sup 87,88,89/Sr in addition to /sup 88/Sr(d,t)/sup 87/Sr and 24 keV neutron capture in /sup ...

1988-01-01

452

Spectroscopy of /sup 87,88,89/Sr with (n,#gamma#) and (d,p) reactions  

International Nuclear Information System (INIS)

Over the recent years the nuclear structure around the N = 50 shell closure, which is very pronounced in the strontium and zirconium isotopes, has been the subject of extensive experimental and theoretical work. On the proton side Z = 38 and Z = 40 provide fairly closed sub-shells. In the strontium isotopes the lg/sub 9/2/ neutron shell is closed at "8"8Sr, supplying relatively pure neutron-hole and neutron-particle states with large spectroscopic factors in "8"7Sr and "8"9Sr, as well as core-coupled states. The mass region is thus ideally suited to examine the transition from a correlated to an uncorrelated (chaotic?) excitational behavior. These two types are characterized e.g. by the density of excited states, the transition strengths, and the spectroscopic factors observed in transfer reactions. We conducted (n,#gamma#) and (d,p) reactions leading to /sup 87,88,89/Sr in addition to "8"8Sr(d,t)"8"7Sr and 24 keV neutron capture in "8"8Sr. The vast amounts of data ...

1988-04-24

453

Some important aspects of fragment angular momentum in medium energy fission of {sup 238}U  

Energy Technology Data Exchange (ETDEWEB)

Independent isomeric yield ratios of {sup 131}Te, {sup 133}Te and {sup 134}I have been determined at five different energies in the range of 25-44 MeV alpha particle induced fission of {sup 238}U using radiochemical and gamma spectrometric techniques. From the independent isomeric yield ratios, fragment angular momenta (J{sub rms}) have been deduced using a statistical model analysis. The J{sub rms} were also calculated theoretically based on thermal equilibration of various collective modes after considering the occurrence of multichance fission. These data and the literature data for various fragments in the mass region 126-136 in {sup 238}U ({alpha},f), {sup 238}U (p,f) and {sup 238}U ({gamma},f) show the following important features: (i) Both the entrance channel excitation energy and input angular momentum affect the fragment angular momentum in the exit channel. (ii) There are two groups of fission products from the point of view of change of fragment angular momentum with ...

1999-03-15

454

Penning trap mass spectrometry of neutron-rich Fe and Co isotopes around N=40 with the LEBIT mass spectrometer  

International Nuclear Information System (INIS)

Penning trap mass spectrometry is presented as a complementary tool to nuclear spectroscopy experiments for the study of nuclear structure in the vicinity of N=40, Z=28. High-precision mass measurements of the "6"3"-"6"6Fe and "6"4"-"6"7Co isotopes have been carried out with the Low Energy Beam and Ion Trap (LEBIT) Penning trap mass spectrometer. The newly obtained mass values for "6"6Fe and "6"7Co are presented, together with the previously reported LEBIT mass measurements in this region. In the case of "6"5Fe the existence of a new isomer is reported, and an isomer recently discovered by decay spectroscopy in "6"7Co is confirmed. Relative mass uncertainties as low as 4x10"-"8 are obtained. All mass values are found to be in good agreement with previous experimental results with the exception of "6"4Co, where a 5#sigma# deviation is observed. Using these data the two neutron separation energies S_2_n are calculated. However, the large error bars in the mass values of the neighbor Fe ...

2010-04-01

455

Nuclear Waste Management - A Need to Ensure that the Waste Decays While the Knowledge Does Not  

International Nuclear Information System (INIS)

The unique time scales associated with nuclear waste management require active work to preserve the knowledge associated with programs that can often span long time frames. For example, repository programs are designed and developed for the safe containment of radionuclides with half-lives on the order of 24,000 years (for Pu-239). Performance assessment studies are required to show, by predictive modeling, that these repositories can safely contain the waste for tens of thousands of years, with one million years a reality in the debate. Development of successful repository programs can span several decades. Once operational, a repository is expected to function until closure for a period of 30 to 40 years. Yet, the decision makers at all levels in such a repository program exert influence and authority over much shorter periods of time (e.g., four years for executive appointments). A discontinuous decision-making process and the associated potential for loss of ...

456

Joining of zirconium alloys  

International Nuclear Information System (INIS)

Alloys of zirconium are widely used in various core components of power reactors. Nuclear assemblies require high degree of reliability and integrity for performing in radiation and corrosive atmosphere. The hostile environments of reactor core and inaccessibility for repairs make it mandatory to select only those joining techniques which produce not only superior quality but are also amenable to NDT methods and such other techniques which ensure acceptable performance. The author has worked on various types of welding of zirconium alloys for different applications. Modern techniques in electron beam (EB) welding, resistance welding, GTAW welding and laser welding have been developed for joining Zr alloys components for different types of reactors. Many of these have been standardized and successfully used in production. Several advancements have been made in the welding technologies towards achieving high productivity and increased reliability with economy and adaptability. EB, laser, ...

2002-09-11

457

Horizontal Steam Generator Thermal-Hydraulics at Various Steady-State Power Levels  

Science.gov (United States)

Three-dimensional computer simulation and analyses of the horizontal steam generator thermal-hydraulics of the WWER 1000 nuclear power plant have been performed for 50% and 75% partial loads, 100% nominal load and 110% over-load. Presented results show water and steam mass flow rate vectors, steam void fraction spatial distribution, recirculation zones, swell level position, water mass inventory on the shell side, and other important thermal-hydraulic parameters. The simulations have been performed with the computer code 3D ANA, based on the 'two-fluid' model approach. Steam-water interface transport processes, as well as tube bundle flow resistance, energy transfer, and steam generation within tube bundles are modelled with {sup c}losure laws{sup .} Applied approach implies non-equilibrium thermal and flow conditions. The model is solved by the control volume procedure, which has been extended in order to take into account the 3D flow of liquid ...

2002-07-01

458

Horizontal Steam Generator Thermal-Hydraulics at Various Steady-State Power Levels  

International Nuclear Information System (INIS)

Three-dimensional computer simulation and analyses of the horizontal steam generator thermal-hydraulics of the WWER 1000 nuclear power plant have been performed for 50% and 75% partial loads, 100% nominal load and 110% over-load. Presented results show water and steam mass flow rate vectors, steam void fraction spatial distribution, recirculation zones, swell level position, water mass inventory on the shell side, and other important thermal-hydraulic parameters. The simulations have been performed with the computer code 3D ANA, based on the 'two-fluid' model approach. Steam-water interface transport processes, as well as tube bundle flow resistance, energy transfer, and steam generation within tube bundles are modelled with "closure laws". Applied approach implies non-equilibrium thermal and flow conditions. The model is solved by the control volume procedure, which has been extended in order to take into account the 3D flow of liquid and gas phase. The ...

2002-04-14

459

High-field MR imaging in the follow-up of patients with valvular and composite tubular aortic prostheses  

International Nuclear Information System (INIS)

Eleven patients who had undergone cardiac surgery were studied by means of high-field MR imaging (1.5 T). Six patients had aortic root and valve replaced with a Bjork-Shiley (BS) composite tubular aortic graft prosthesis for acute dissection of ascending aorta. In the other 5 patients with rheumatic calcific aortic disease, the valve had been replaced with a BS prosthesis. As a whole, MR studies were 14. Previous evaluations of magnetic field effects had seem carried out ex vivo on both BS valves and BS composite prostheses, on surgical ligation clips (Tantalium and Stainless) and on stainless wires for sternal closure. In 4 patients (2 BS composite grafts, and 2 BS valves) MRI diagnosed chronic dissection of both arch and descending aorta. In 1 of them, with a bs valve, associated localized acute dissection of ascending aorta was observed. In 3 patients with BS composite grafts, MRI revealed pseudo-aneurysms (including a thrombosed one) at the graft level. In one ...

460

Ground penetrating radar and direct current resistivity evaluation of the desiccation test cap, Savannah River Site  

Energy Technology Data Exchange (ETDEWEB)

The Savannah River Site (SRS) has a variety of waste units that may be temporarily or permanently stabilized by closure using an impermeable cover to prevent groundwater infiltration. The placement of an engineered kaolin clay layer over a waste unit is an accepted and economical technique for providing an impermeable cover but the long term stability and integrity of the clay in non-arid conditions is unknown. A simulated kaolin cap has been constructed at the SRA adjacent to the Burial Ground Complex. The cap is designed to evaluate the effects of desiccation on clay integrity, therefore half of the cap is covered with native soil to prevent drying, while the remainder of the cap is exposed. Measurements of the continuing impermeability of a clay cap are difficult because intrusive techniques may locally compromise the structure. Point measurements made to evaluate clay integrity, such as those from grid sampling or coring and made through a soil cover, may miss ...

1996-04-01

461

Data of spleen-scintiscanning after splenectomy  

International Nuclear Information System (INIS)

In 65 adult rabbits of both sexes (2.5 to 6 kg) the following salvaging procedures were performed after simulated trauma: (1) Continuous suture line; (2) closure with fibrin sealant after temporary clamping; (3) hemisplenectomy with omental wrap; (4) suture fixation of fragments and slices of spleen tissue to the peritoneum; (5) suture fixation of spleen fragments to the omentum; (6) extraperitoneal subcutaneous transposition of spleen cubes. In addition, the likelihood of spontaneous splenosis was examined in a preliminary study involving 5 animals by introducing unattached spleen meal and fragments. Scanning was repeated 4 to 12 weeks postoperatively. The functional competence of minor parenchymal islands was also investigated with well counter measurements of organ and muscle tissue homogenates. Spontaneous splenosis after abdominal injuries was not found to be the rule. Salvaging procedures at the natural vascular hilus by sutures, fibrin sealant and ...

462

Characterization of the corrosion behavior of the carbon steel liner in Hanford Site single-shell tanks  

Energy Technology Data Exchange (ETDEWEB)

Six safety initiatives have been identified for accelerating the resolution of waste tank safety issues and closure of unreviewed safety questions. Safety Initiative 5 is to reduce safety and environmental risk from tank leaks. Item d of Safety Initiative 5 is to complete corrosion studies of single-shell tanks to determine failure mechanisms and corrosion control options to minimize further degradation by June 1994. This report has been prepared to fulfill Safety Initiative 5, Item d. The corrosion mechanisms that apply to Hanford Site single-shell tanks are stress corrosion cracking, pitting/crevice corrosion, uniform corrosion, hydrogen embrittlement, and microbiologically influenced corrosion. The corrosion data relevant to the single-shell tanks dates back three decades, when results were obtained from in-situ corrosion coupons in a few single-shell tanks. Since that time there have been intertank transfers, evaporation, and chemical alterations of the waste. ...

1994-06-01

463

CFD simulation of steam generator tube rupture thermal-hydraulics  

Energy Technology Data Exchange (ETDEWEB)

Several steam generator tube rupture accidents have occurred at plants in the past. In this paper the Computational Multi-Fluid Dynamics (CMFD) investigation of the horizontal steam generator thermal-hydraulics during the tube rupture accident is performed. A guillotine of a steam generator U-tube is assumed with choked flow from the primary to the secondary side of the steam generator. We have computed water and steam velocity fields, steam volume fraction distribution on the steam generator secondary (shell) side, as well as the swell level increase. The simulation results are a support to the safety analyses of the steam generator tube rupture accident. Numerical simulation is performed with the multidimensional multi-fluid modelling approach. The two-phase flow around steam generator tubes in the bundle is modelled by the porous media approach. Interfacial mass, momentum and energy transfer are modelled with the closure laws. The governing equations are solved ...

2004-07-01

464

A simulation of the transport and fate of radon-222 derived from thorium-230 low-level waste in the near-surface zone of the Radioactive Waste Management Site in Area 5 of the Nevada Test Site  

Energy Technology Data Exchange (ETDEWEB)

US Department of Energy (DOE) Order 5820.2A (DOE, 1988) requires performance assessments on all new and existing low-level radioactive waste (LLW) disposal sites. An integral part of performance assessment is estimating the fluxes of radioactive gases such as radon-220 and radon-222. Data needs pointed out by mathematical models drive site characterization. They provide a logical means of performing the required flux estimations. Thorium-230 waste, consisting largely of thorium hydroxide and thorium oxides, has been approved for disposal in shallow trenches and pits at the LLW Radioactive Waste Management Site in Area 5 of the Nevada Test Site. A sophisticated gas transport model, CASCADR8 (Lindstrom et al., 1992b), was used to simulate the transport and fate of radon-222 from its source of origin, nine feet below a closure cap of native soil, through the dry alluvial earth, to its point of release into the atmosphere. CASCADR8 is an M-chain gas-phase radionuclide ...

1993-12-01

465

A complete algorithm for synthesizing modular fixtures for polygonal parts  

Energy Technology Data Exchange (ETDEWEB)

Commercially-available nuclear fixturing systems typically include a square lattice of tapped and bushed holes with precision locating and clamping elements that can be rigidly attached to the lattice using dowel pins or expanding mandrels. Currently, human expertise is required to synthesize a suitable arrangements of these elements to hold a given part. Besides being time consuming, if the set of alternatives is not systematically explored, the designer may fail to find an acceptable fixture or may settle upon a suboptimal fixture. We consider a class of modular fixtures that prevent a part from translating or rotting in the plane using four point contacts on the part`s boundary. These fixtures are based on three round locators, each centered on a lattice point, and one translating clamp. We present an algorithm that accepts a polygonal part shape as input and synthesizes the set of all fixture designs that achieve form closure for the given part. The algorithm ...

1993-11-01

466

Wilsonville Advanced Coal Liquefaction Research and Development Facility, Wilsonville, Alabama. Topical report No. 6, CSD unit - operation and maintenance, 1983  

Energy Technology Data Exchange (ETDEWEB)

A summary of the 1983 Critical Solvent Deashing unit performance at the Wilsonville Advanced Coal Liquefaction R and D Facility is presented. All periods of on feed operation, unscheduled shutdowns, and scheduled shutdowns are accounted for and tabulated. Causes of unscheduled shutdowns are identified and discussed. Details of repeated, major maintenance problems with various pieces of equipment are presented. Where applicable, solutions are discussed. Historical operations and maintenance data are presented and used for comparison purposes in order to better indicate areas of improvement in the unit. 4 references, 7 figures, 3 tables.

1985-03-01

467

Waste Sampling and Characterization Facility (WSCF). Maintenance Implementation Plan  

Energy Technology Data Exchange (ETDEWEB)

This Maintenance Implementation Plan has been developed for maintenance functions associated with the Waste Sampling and Characterization Facility (WSCF). This plan is developed from the guidelines presented by Department of Energy (DOE) Order 4330.4A, Maintenance Management Program (DOE 1990), Chapter II. The objective of this plan is to provide baseline information for establishing and identifying WHC conformance programs and policies applicable to implementation of DOE order 4330.4A guidelines. In addition, this maintenance plan identifies the actions necessary to develop a cost-effective and efficient maintenance program at WSCF.

1993-07-01

468

Waste Management Project fiscal year 1998 multi-year work plan, WBS 1.2  

Energy Technology Data Exchange (ETDEWEB)

The Waste Management Project manages and integrates (non-TWRS) waste management activities at the site. Activities include management of Hanford wastes as well as waste transferred to Hanford from other DOE, Department of Defense, or other facilities. This work includes handling, treatment, storage, and disposal of radioactive, nonradioactive, hazardous, and mixed solid and liquid wastes. Major Waste Management Projects are the Solid Waste Project, Liquid Effluents Project, and Analytical Services. Existing facilities (e.g., grout vaults and canyons) shall be evaluated for reuse for these purposes to the maximum extent possible.

1997-09-23

469

The development of automatic surface dose-rate measuring and recording system for radioactive waste drum  

International Nuclear Information System (INIS)

The system which is performed the transportation and measurement of drum automatically to measure the surface dose-rate of radioactive waste drum and can inspect place of contaminated sources and precise dose-rate within a drum according to measuring many places equally at the same time has been developed. It is expected that the system be used to minimized radiation exposure of workers and manage the drum effectively according to established at the production facilities as well as the radioactive waste treatment facilities. (author). 7 refs., 9 tabs., 16 figs.

470

The Wilsonville Advanced Coal Liquefaction Research and Development Facility, Wilsonville, Alabama  

Energy Technology Data Exchange (ETDEWEB)

This report presents the operating results for Run 255 at the Advanced Coal Liquefaction Research and Development Facility in Wilsonville, Alabama. This run operated in the Close Coupled Integrated Two-Stage Liquefaction mode (CC-ITSL) using Martin Lake Texas lignite. The purpose of this run was to demonstrate unit and system operability with Martin Lake lignite. Run 255 began on 20 March 1988 and continued through 9 June 1988. During this period, 204.4 MF tons of Martin Lake Texas lignite were fed in 1865.5 hours of operation. 70 figs., 21 tabs.

1991-05-01

471

Southern receiver system: Environmental impact assessment status report: Conawapa to Winnipeg Power Transmission Complex  

Energy Technology Data Exchange (ETDEWEB)

The Conawapa-Winnipeg Power Transmission Complex includes five interrelated transmission and conversion facilities. This booklet describes work done on the upgrade of the southern receiver system, one component of the complex. The southern receiver system is composed of a network of high voltage transmission lines and station facilities. The booklet includes a description of the upgrade, the project setting, short and long-term effects and impact management, and the next steps to be taken in the process, including the regulatory process and public consultation.

1992-01-01

472

Radiation control aspects of the civil construction for a high power free electron laser (FEL) facility  

International Nuclear Information System (INIS)

The paper discusses some of the assumptions and methods employed for the control of ionizing radiation in the specifications for the civil construction of a planned free electron laser facility based on a 200 MeV, 5 mA superconducting recirculation electron accelerator. Consideration is given firstly to the way in which the underlying building configuration and siting aspects were optimized on the basis of the early assumptions of beam loss and radiation goals. The various design requirements for radiation protection are then considered, and how they were folded into an aesthetically pleasing and functional building. copyright 1997 American Institute of Physics.

1996-11-06

473

Performance of rubber heat-stable and radiation-stable seals in helium coolant lines  

International Nuclear Information System (INIS)

The integrity of helium circulation loop flanged joints has been attracting recent attention as a design problem, in the development of high-temperature facilities incorporating helium loops (e.g., the VRG-50 pilot nuclear facility). Elevated temperatures and pressures, and the radiation environment, impose additional requirements on sealant materials. This applies first and foremost to rubber seals, which have found widespread favor on account of its excellent elasticity, its ability to spontaneously conform to possible changes in the clearance in the seal assembly, and the low compressive stresses developed in the flange joint assembly.

474

Monte Carlo Uncertainty Analyses of Pulsed Activation in the National Ignition Facility Gunite Shielding  

International Nuclear Information System (INIS)

The global effect of activation cross-section uncertainties on calculated radiological quantities is investigated for the first time using a methodology based on Monte Carlo random sampling. The method is applied to the calculation of the uncertainty in the contact dose rate from the gunite shielding of the National Ignition Facility chamber after 30 yr of pulsed irradiation. Some critical cross section contributing significantly to the overall uncertainty are identified. By a reasonable reduction of the uncertainty in those cross sections, the accuracy in the calculated total contact dose rate is greatly improved.

2003-05-01

475

Materials testing and failure analysis activities at the Wilsonville Advanced Coal Liquefaction Research and Development Facility  

Science.gov (United States)

Oak Ridge National Laboratory (ORNL) has for over ten years provided materials testing and failure analysis services to various coal conversion and utilization facilities in the United States. ORNL was involved in these types of activities at all four of the major coal liquefaction pilot plants. This paper presents a summary of activities at Wilsonville over the past two and one-half years. Some details of these activities are discussed below. Failure analysis of elastomers, stainless steels, and alloys is discussed. 6 refs., 9 figs., 13 tabs.

1989-01-01

476

Information on Hanford site cribs and septic systems  

Energy Technology Data Exchange (ETDEWEB)

This document provides information on septic systems with a design capacity of greater than 14,500 gal/d and cribs submitted as requested by the Washington State Department of Ecology. Data for this submittal were taken from the Waste Information Database System (WIDS) and the Hanford Environmental Compliance Record (HECR) database. The current definition used in WIDS for an ''inactive facility'' is one that either no longer receives waste or plans to in the future. Information concerning the deactivation method for a facility is included when such information is available.

1988-05-01

477

Hyperfine structure studies with the COMPLIS facility  

International Nuclear Information System (INIS)

COMPLIS is an experimental facility designed to carry out spectroscopic studies on radioisotopes produced by disintegration of elements available at CERN's Booster-ISOLDE on-line isotope separator. During recent series of experimental runs, hyperfine structure measurements have yielded information on nuclear moments and deformations of platinum and iridium isotopes. For the first time, population by #alpha#-decay from Hg was exploited to investigate "1"7"8"-"1"8"1Pt--the most neutron-deficient Pt isotopes yet studied. Successful measurements have recently been carried out on "1"8"2"-"1"8"9Ir.

1998-12-16

478

Heber Ethanol Fuel Facility, Imperial Valley, California. Quarterly report No. 2, March 1981-May 1981  

Energy Technology Data Exchange (ETDEWEB)

The purposed project is a commercial-scale ethanol-fuel facility with a capacity of twenty million gallons per year of fuel-grade ethanol. In addition, 70,000 tons per year of distillers dried grains will be produced. The following tasks and issues are addressed: process engineering - process descriptions, plant layout, and design; economics and finance - overview of capital and operating costs; environmental analysis - preliminary project description; and permit processing and legal issues. (MHR)

1981-08-01

479

Hanford Federal Facility Agreement and Consent Order quarterly progress report for the period ending June 30, 1991  

Energy Technology Data Exchange (ETDEWEB)

This is the ninth quarterly report as required by the Hanford Federal Facility Agreement and Consent Order (Ecology et al. 1990), also known as the Tri-Party Agreement, established between the US Department of Energy (DOE), the US Environmental Protection Agency (EPA), and the Washington State Department of Ecology (Ecology). The Tri-Party Agreement sets the plan and schedule for achieving regulatory compliance and cleanup of waste sites at the Hanford Site. This report covers progress for the quarter that ended June 30, 1991. A total of 87 milestones have been completed to date. 39 refs., 1 fig.

1991-08-01

480

Friends of the Earth: Help Paraguay fight the soy invasion : Environmental Justice : Campaign Actions  

Wastenet

...soy, rights, justice, contamination, water, cargill, port soy, rights, justice, contamination, water, cargill, port Friends of the ... The global food giant Cargill has built its own port on the banks of the River Paraguay with plans to expand. It's ...allows Puerto Union, the port facility belonging to the transnational food giant Cargill, to continue operating. This decree was issued despite the ... The Cargill port facility represents a hazard to the water supply of the entire population of the city, and any accident such ...

481

Forthcoming (n, #gamma#) measurements on the Fe and Ni isotopes at CERN n_TOF  

International Nuclear Information System (INIS)

An overview of the past, present and future research activities at the CERN neutron time of flight facility n_TOF is given, with special focus on the astrophysical aspects. During the first campaign (Phase I), neutron capture cross sections of relevance for several aspects of the s-process nucleosynthesis have been measured. A second campaign has recently started (Phase II), aiming at the study of the weak s-process component via accurate (n,#gamma#) measurements of the Fe and Ni isotopes. Some changes in the facility will allow us to perform these measurements with improved experimental conditions.

2010-01-01

482

Estimating the tritiated hydrocarbon decontamination factor by heavy methane  

International Nuclear Information System (INIS)

As part of the start up of Los Alamos National Laboratory's new tritium-handling facility, the efficiency of a catalytic oxidation tritium decontamination system was investigated using deuterated methane. The tests were performed during the start up of the facility to confirm the operability of the system before introducing tritium and to provide a baseline for comparison. Techniques and instruments normally used for atmospheric tracer experiments using deuterated methane were applied virtually without modification. The sensitivity of this method allowed preliminary checks at the sub-ppm (v/v) level.

483

Energy-Smart Building Choices: How School Facilities Managers and Business Officials Are Reducing Operating Costs and Saving Money  

Science.gov (United States)

Most K-12 schools could save 25% of their energy costs by being smart about energy. Nationwide, the savings potential is $6 billion. While improving energy use in buildings and busses, schools are likely to create better places for teaching and learning, with better lighting, temperature control, acoustics, and air quality. This brochure, targeted to school facilities managers and business officials, describes how schools can become more energy efficient.

2001-08-06

484

End user needs for enhanced IAEA Safeguards Information Management Capabilities  

International Nuclear Information System (INIS)

The International Atomic Energy Agency is undertaking a program for strengthening its safeguards on the recognition that safeguards must give assurance not only of the non-diversion of declared material or that declared facilities are not being misused, but also of the absence of any undeclared nuclear activities in States which have signed comprehensive safeguards agreements with the Agency. The IAEA has determined that the detection of undeclared nuclear activities and the creation of confidence in the continuing peaceful use of declared material and facilities is largely dependent on more information being made available to the Agency and on the capability of the Agency to make more effective use of this additional information, as well as existing information.

485

Development of high resolution imaging detectors for X-ray astronomy  

Energy Technology Data Exchange (ETDEWEB)

High (spatial) resolution imaging detectors for X-ray astronomy were developed. Several prototype detectors built and their feasibility and baseline performance were assessed. Two of these detector types are proposed for investigations on the advanced X-ray astrophysics facility (AXAF). The readiness of a new X-ray imaging system, the charge coupled device (CCD) imaging specctrometer is outlined, and state of the art performance parameters for microchannel plate (MCP) and CCD detectors are measured. Laboratory facilities and procedures for coating MCP are developed general high resolution imagery systems are analyzed.

1985-03-01

486

Development of high resolution imaging detectors for X-ray astronomy  

International Nuclear Information System (INIS)

High (spatial) resolution imaging detectors for X-ray astronomy were developed. Several prototype detectors built and their feasibility and baseline performance were assessed. Two of these detector types are proposed for investigations on the advanced X-ray astrophysics facility (AXAF). The readiness of a new X-ray imaging system, the charge coupled device (CCD) imaging specctrometer is outlined, and state of the art performance parameters for microchannel plate (MCP) and CCD detectors are measured. Laboratory facilities and procedures for coating MCP are developed general high resolution imagery systems are analyzed.

1985-01-01

487

Corrosion studies at the Wilsonville, Alabama, coal liquefaction facility during 1983  

Science.gov (United States)

During 1983, Oak Ridge National Laboratory continued a study of materials performance at the Wilsonville, Alabama, Advanced Coal Liquefaction Research and Development Facility. Materials performance was evaluated by exposure and analysis of corrosion coupons and U-bend specimens, chemical analysis of related process streams, and ultrasonic determination of the thickness of walls of various components. The results of these studies are useful to current plant operators and to designers of future large-scale plants. 18 references, 4 figures, 12 tables.

1984-10-01

488

Conceptual design of a nuclear reactor facility for medical and biological purposes  

Energy Technology Data Exchange (ETDEWEB)

Optimal neutron energy for boron neutron capture therapy (BNCT) has been studied. Epithermal neutron is superior to thermal neutrons in treating deep-seated tumors. Design of the epithermal neutron column for BNCT has been performed by using a two-dimensional transport calculation code. Aluminum and heavy water are used as moderation materials. A thermal neutron column is also designed using heavy water as thermalization material. The configuration of the facility for treatment and research of BNCT and also for basic radio-biological studies of neutrons has been presented.

1981-09-01

489

Conceptual design of a nuclear reactor facility for medical and biological purposes  

International Nuclear Information System (INIS)

Optimal neutron energy for boron neutron capture therapy (BNCT) has been studied. Epithermal neutron is superior to thermal neutrons in treating deep-seated tumors. Design of the epithermal neutron column for BNCT has been performed by using a two-dimensional transport calculation code. Aluminum and heavy water are used as moderation materials. A thermal neutron column is also designed using heavy water as thermalization material. The configuration of the facility for treatment and research of BNCT and also for basic radio-biological studies of neutrons has been presented. (author).

490

Capital cost associated with the Trunkline Liquefied Natural Gas Lake Charles Facility  

Energy Technology Data Exchange (ETDEWEB)

The actual cost of constructing the LNG facility was about $589 million, an increase of approximately 258% over the $164 million cost estimate approved by the Federal Power Commission (FPC) in 1977. According to reports submitted by Trunkline LNG, the reasons for the increases included extensive modifications to plant design to ensure safe and reliable construction and greater operating efficiency and compliance with state and federal regulations. Also, extension beyond the original estimated completion date, various labor problems, and general inflation resulted in increased labor and interest costs.

1983-08-31

491

Bechtel Hanford Inc. Network Security Plan for the EnvironmentalRestoration Contract  

Science.gov (United States)

'As part of the Computer Protection Plan, this Network Security Plan identifies the specific security measures used to protect Bechtel Hanford, Inc.'s (BHI's) enterprise network. The network consists of the communication infrastructure and information systems used by BHI to perform work related to the Environmental Restoration Contract (ERC) at the Hanford Site. It provides electronic communication between the ERC-leased facilities in Richland, Washington, and facilities located on the Hanford Site. Network gateways to other site and offsite networks provide electronic communication with the remainder of the Hanford community.'

1999-06-30

492

Analysis of tritium mission FMEF/FAA fuel handling accidents  

Energy Technology Data Exchange (ETDEWEB)

The Fuels Material Examination Facility/Fuel Assembly Area is proposed to be used for fabrication of mixed oxide fuel to support the Fast Flux Test Facility (FFTF) tritium/medical isotope mission. The plutonium isotope mix for the new mission is different than that analyzed in the FMEF safety analysis report. A reanalysis was performed of three representative accidents for the revised plutonium mix to determine the impact on the safety analysis. Current versions computer codes and meterology data files were used for the analysis. The revised accidents were a criticality, an explosion in a glovebox, and a tornado. The analysis concluded that risk guidelines were met with the revised plutonium mix.

1997-11-18

493

Acceptance test report for the Westinghouse 100 ton hydraulic trailer  

Energy Technology Data Exchange (ETDEWEB)

The SY-101 Equipment Removal System 100 Ton Hydraulic Trailer was designed and built by KAMP Systems, Inc. Performance of the Acceptance Test Procedure at KAMP`s facility in Ontario, California (termed Phase 1 in this report) was interrupted by discrepancies noted with the main hydraulic cylinder. The main cylinder was removed and sent to REMCO for repair while the trailer was sent to Lampson`s facility in Pasco, Washington. The Acceptance Test Procedure was modified and performance resumed at Lampson (termed Phase 2 in this report) after receipt of the repaired cylinder. At the successful conclusion of Phase 2 testing the trailer was accepted as meeting all the performance criteria specified.

1995-03-06