Preliminary Feasibility Study on the Construction of Steel Hot Cell Facility for Precise Manipulated Examinations

International Nuclear Information System (INIS)

Ahn, Sangbok; Kwon, Hyungmun; Kim, Heemoon; Kim, Dosik; Min, Duckkee; Hong, Kwonpyo

2006-01-01

Hot laboratory is essential facility to research and develop in the nuclear industries to examine radioactive materials. The post irradiation examinations for irradiated fuels and materials should be mainly conducted in the hot cell facility to protect radiations to operators. Hot cells are divided into a concrete hot cell and a steel hot cell according to the wall materials. Usually a concrete hot cell is applied to test for high level radioactive materials like as a fuel assembly, rods, and large structure specimens, and a steel hot cell for comparatively lower level activity materials in fuel fragments, and small structural materials. A steel hot cell has many benefits in a specimen manipulation, construction and maintenance costs. In recent the test for the irradiated materials is more frequently required a small and precise manipulating examination for higher degree tests of research and developments. Unfortunately hot laboratory facilities in domestics have mainly constituted of concrete hot cells, and not ready for techniques in steel hot cells. In this paper the construction feasibility of steel hot cell facility is preliminary reviewed in the points of the status of domestic facilities, the test demand prospect and detailed plans

EDF requirements for hot cells examinations on irradiated fuel

International Nuclear Information System (INIS)

Segura, J.C.; Ducros, G.

2002-01-01

The objectives of increasing French Nuclear Power Plants (NPP) availability while lengthening the fuel irradiation cycle and reaching higher burnups lead EDF to carry out on site and hot cell examinations. The data issued from such fuel behaviour monitoring programmes will be used to ascertain that the design criteria are met. Data are also needed for modelling, development and validation. The paper deals quickly with the logistics linked to the selection and transport of fuel rods from NPP to hot cell laboratory. Hot cell PIEs remain a valuable method to obtain data in such fields as PCI (Pellet-Cladding Interaction), internal pressure, FGR (Fission Gas Release), oxide thickness, metallurgical aspects. The paper introduces burnup determination methods, inner pressure evaluation, preparation of samples for further irradiation such as power ramps for PCI and RIA (Reactivity Initiated Accident) testing. The nuclear microprobe of Perre Suee laboratory is also presented. (author)

Introduction of hot cell facility in research center Rez - Poster

International Nuclear Information System (INIS)

Petrickova, A.; Srba, O.; Miklos, M.; Svoboda, P.

2015-01-01

This poster presents the hot cell facility which is being constructed as part of the SUSEN project at the Rez research center (Czech Republic). Within this project a new complex of 10 hot cells and one semi-hot cell will be built. There will be 8 gamma hot cells and 2 alpha hot cells. In each hot cell a hermetic, removable box made of stainless steel will home different type of devices. The hot cells and semi hot cell will be equipped with devices for processing samples (cutting, welding, drilling, machining) as well as equipment for testing (sample preparation area, stress testing machine, fatigue machine, electromechanical creep machine, high frequency resonance pulsator...) and equipment for studying material microstructure (nano-indenter with nano-scratch tester and scanning electron microscope). An autoclave with water loop, installed in a cell will allow mechanical testing in control environment of water, pressure and temperature. A scheme shows the equipment of each cell. This hot laboratory will be able to cover all the process to study radioactive materials: receiving the material, the preparation of the samples, mechanical testing and microstructure observation. Our hot cells will be close to the research nuclear reactor LVR-15 and new irradiation facility (high irradiation by cobalt source) is planned to be built within the SUSEN project

Radioactive Mapping Contaminant of Alpha on The Air in Space of Repair of Hot Cell and Medium Radioactivity Laboratory in Radio metallurgy Installation

International Nuclear Information System (INIS)

Yusuf-Nampira; Endang-Sukesi; S-Wahyuningsih; R-Budi-Santoso

2007-01-01

Hot cell and space of acid laboratory medium activity in Radio metallurgy Installation are used for the examination preparation of fuel nuclear post irradiation. The sample examined is dangerous radioactive material representing which can disseminate passing air stream. The dangerous material spreading can be pursued by arranging air stream from laboratory space to examination space. To know the performance the air stream arrangement is hence conducted by radioactive mapping contaminant of alpha in laboratory / space of activity place, for example, medium activity laboratory and repair space. This mapping radioactivity contaminant is executed with the measurement level of the radioactivity from sample air taken at various height with the distance of 1 m, various distance and from potential source as contaminant spreading access. The mapping result indicate that a little spreading of radioactive material happened from acid cupboard locker to laboratory activity up to distance of 3 m from acid cupboard locker and spreading of radioactive contaminant from goods access door of the hot cell 104 to repair space reach the distance of 2 m from goods door access. Level of the radioactive contamination in the space was far under maximum limitation allowed (20 Bq / m 3 ). (author)

Design and management of hot-laboratories

International Nuclear Information System (INIS)

1976-09-01

This document is a manual for the design and management of hot-laboratories. It is composed of three parts. The first part is devoted to the design of hot-laboratories. Items included here are; conceptual design; many regulations which must be considered at design stage; design of cave and its shielding; and the design of building, ventilation, and draining. Many examples of specific designs are presented by figures and photographs. The second part is concerned with the methods of operation management. Organizational structure, scheduling of operation, process management, and regulatory problems are discussed with some examples. Technological problems associated with the operation of a hot laboratory (e.g., manipulator, transfer machine, maintenance, and decontamination) are also discussed based on the authors' experiences. An example of the operation manual is presented for reference. The third part is devoted to the safety management and the training of personnel. The regulations by law are briefly explained. Most of this part is devoted to the problem of monitoring radio-activity. Monitoring of control areas, radio-active wastes, and personal dosage is discussed together with many other specific monitoring problems. As for training, the purpose and the present status are explained. (Aoki, K.)

Experience feedback on the refurbishment of the LECA hot laboratory at Cadarache

International Nuclear Information System (INIS)

Grandjean, Jean-Paul; Autran, Bernard; Blanc, Jean-Yves

2007-01-01

Full text: After ten years of renovation work, the LECA hot laboratory refurbishment project has finally been completed which means it is now time to draw a few conclusions. Refurbishment of LECA was needed to enable PIE in this laboratory up to 2015. Improvements were made according to the laboratory safety assessment in March 2001. More than 400,000 working hours were clocked up without any serious accidents. The overall radiological record remained below 0.4 man.Sv for this period despite a high contamination level in the venting system and hot cells. The total fissile mass was decreased by a factor of three, and contamination was also considerably reduced. The project was finalised two years later than expected, mainly due to difficulties with two contracts on civil engineering work to improve seismic resistance and on inserting stainless steel casing into some hot cells. Renovation work on existing structures was underestimated, as was the time required to re-commission the cells. The fact that the total number of external staff working inside the facility at the same time was limited also slowed work down. This delay affected the research programmes mainly over the last two years. On the whole, 85 % of all experimentation activities were nevertheless continued during refurbishment. New steps for refurbishment have already been planned so as to extend the LECA service life once again. A line of lead-shielded cells - not designed to withstand current earthquake standards - will be demolished before the end of 2008, and civil engineering operations have been programmed for 2013-2014 so the facility will be able to withstand a maximum design earthquake. (authors)

Decommissioning program and future plan for research hot laboratory (2)

International Nuclear Information System (INIS)

Koya, Toshio; Nozawa, Yukio; Hanada, Yasushi; Ono, Katsuto; Kanazawa, Hiroyuki; Nihei, Yasuo; Owada, Isao

2010-01-01

The Research Hot Laboratory (RHL) in Japan Atomic Energy Agency (JAEA) was constructed in 1961, as the first one in JAPAN, to perform the examinations of irradiated fuels and materials. RHL consists of 10 heavy concrete cells and 38 lead cells, which had been contributed to research and development program in or out of JAEA for the investigation of irradiation behavior for fuels and nuclear materials. However, RHL is the one of target as the rationalization program for decrepit facilities in former Tokai institute. Therefore the decommissioning works of RHL have been started on April 2003. The decommissioning work will be progressing, dismantling the lead cells and decontamination of concrete caves then release in the regulation of controlled area. The 18 lead cells (including semi-hot cell and junior-cell) had been dismantled. Removal of the applause from the cells, survey of the contamination revel in the lead cells and prediction of radio active waste have been finished as the preparing work for dismantling of the remained 20 lead cells. The future plan of decommissioning work has been prepared to incarnate the basic vision and dismantling procedure. (author)

Implementation of a cabin X-rays in hot cell

International Nuclear Information System (INIS)

Berduola, F.; Caral, L.

2001-01-01

The Fabrice process for the reconstituted short length irradiated rods in a hot cell was developed by the CEA especially for power ramp testing. This technique requires intricate operations in a hot cell with specially adapted equipment and great skill people. And end plug is inserted under pressure and fitted to the opening end of a cladding tube. The meeting surfaces of the en plug and the opening end are welded by a TIG (tunsten inert gas) process. Nevertheless, somo predominate defects may occur in the end plug weld joints, such as lack of penetration and cavity. So, particular attention must be paid to non-destructive examination in particular X-ray control of welding areas. A radioscopy technique has been applied to the control of TIG welds of the end plugs to rod assemblies in a hot cell mock-up to be tested under realistic geometric conditions. This X-rays method enables immediate monitoring of any welding defaults on a TV screen. A remote positioning system for the Fabrice rod is being developed to position fuel rods below a X-ray source. Radioscopy pictures will be recorded during remote positioning of the rod movement. This document presents the modifications achieved by the constructor in cooperation with our laboratory staff, concerning the nuclearization of the apparatus as well as its implementation in the shielded hot cell n paragraph 2 of the CEA-DEC/SLS/LECA Laboratory in Cadarache. Hot operation of the rod positioner is planned for september 2022 because of recent refurbishing works in the plant. (Author)

WESF hot cells waste minimization criteria hot cells window seals evaluation

International Nuclear Information System (INIS)

Walterskirchen, K.M.

1997-01-01

WESF will decouple from B Plant in the near future. WESF is attempting to minimize the contaminated solid waste in their hot cells and utilize B Plant to receive the waste before decoupling. WESF wishes to determine the minimum amount of contaminated waste that must be removed in order to allow minimum maintenance of the hot cells when they are placed in ''laid-up'' configuration. The remaining waste should not cause unacceptable window seal deterioration for the remaining life of the hot cells. This report investigates and analyzes the seal conditions and hot cell history and concludes that WESF should remove existing point sources, replace cerium window seals in F-Cell and refurbish all leaded windows (except for A-Cell). Work should be accomplished as soon as possible and at least within the next three years

Use of a CO2 pellet non-destructive cleaning system to decontaminate radiological waste and equipment in shielded hot cells at the Bettis Atomic Power Laboratory

International Nuclear Information System (INIS)

Bench, T.R.

1997-01-01

This paper details how the Bettis Atomic Power Laboratory modified and utilized a commercially available, solid carbon dioxide (CO 2 ) pellet, non-destructive cleaning system to support the disposition and disposal of radioactive waste from shielded hot cells. Some waste materials and equipment accumulated in the shielded hot cells cannot be disposed directly because they are contaminated with transuranic materials (elements with atomic numbers greater than that of uranium) above waste disposal site regulatory limits. A commercially available CO 2 pellet non-destructive cleaning system was extensively modified for remote operation inside a shielded hot cell to remove the transuranic contaminants from the waste and equipment without generating any secondary waste in the process. The removed transuranic contaminants are simultaneously captured, consolidated, and retained for later disposal at a transuranic waste facility

Current activities in development of PIE techniques in JMTR hot laboratory

International Nuclear Information System (INIS)

Ishii, Toshimitsu; Ohmi, Masao; Shimizu, Michio; Kaji, Yoshiyuki; Ueno, Fumiyoshi

2006-01-01

A wide variety of post-irradiation examinations (PIEs) for research and development of nuclear fuels and materials to be utilized in nuclear field has been carried out since 1971 in three kinds of β-γ hot cells; concrete, lead and steel cells in the JMTR Hot Laboratory (JMTR HL) associated with the Japan Materials Testing Reactor (JMTR). In addition to PIEs, the re-capsuling work including re-instrumentation was also conducted for the power ramping tests of the irradiated LWR fuels using Boiling Water Capsule (BOCA). Recently, new PIE techniques are required for the advanced irradiation studies. In this paper, the irradiation assisted stress corrosion cracking (IASCC) growth test technique of irradiated in-core structural materials and the remote operation technique of the atomic force microscope (AFM) are described as JMTR HL's current activities in the development of new PIE techniques. (author)

Decommissioning of the Risoe Hot Cell facility

International Nuclear Information System (INIS)

Carlsen, H.

1994-02-01

Concise description of progress in hot cell facility decommissioning at Risoe National Laboratory is presented. Removal of the large contaminated equipment has been completed, all the concrete cells have been finally cleaned. The total contamination left on the concrete walls is of the order of 1850 GBq. Preliminary smear tests proved the stack to be probably clean. The delay in project completion seems to be around 7 months, the remaining work being of rather conventional character. (EG)

Decommissioning of the Risoe Hot Cell facility

International Nuclear Information System (INIS)

Carlsen, H.

1991-08-01

Concise descriptions of actions taken in relation to the decommissioning of the hot cell facility at Risoe National Laboratory are presented. The removal of fissile material, removal and decontamination of large cell internals, and of large equipment such as glove boxes and steel boxes, in addition to dose commitments, are explained. Tables illustrating the analysis of smear tests, constants for contamination level examination, contamination and radiation levels after cleaning and total contamination versus measured radiation are included. (AB)

Hot Fuel Examination Facility (HFEF)

Data.gov (United States)

Federal Laboratory Consortium — The Hot Fuel Examination Facility (HFEF) is one of the largest hot cells dedicated to radioactive materials research at Idaho National Laboratory (INL). The nation's...

Development status of post irradiation examination techniques at the JMTR Hot Laboratory

International Nuclear Information System (INIS)

Ohmi, M.; Ohsawa, K.; Nakagawa, T.; Umino, A.; Shimizu, M.; Satoh, H.; Oyamada, R.

1992-01-01

Hot laboratory at Oarai Research Establishment was founded to examine the objects mainly irradiated at JMTR (Japan Materials Testing Reactor) and has been operated since 1971. A wide variety of post-irradiation examinations (PIE) is available using the hot laboratory. Continuous efforts are made to develop new PIE techniques to accommodate the user's requirements. The following are main techniques recently developed in the hot laboratory; 1. Remote capsule assembly including remote weld of irradiated objects for reirradiation in JMTR. 2. Fracture toughness tests of reactor component materials. 3. Creep tests of heat resistance alloys in high temperature conditions. 4. Tests of irradiation assisted stress corrosion cracking (IASCC). 5. Examination techniques of miniaturized test specimens. This report describes an outline of the hot laboratory with main emphasis on the new PIE techniques. (author)

Safety evaluation report of hot cell facilities for demonstration of advanced spent fuel conditioning process

International Nuclear Information System (INIS)

You, Gil Sung; Choung, W. M.; Ku, J. H.; Cho, I. J.; Kook, D. H.; Park, S. W.; Bek, S. Y.; Lee, E. P.

2004-10-01

The advanced spent fuel conditioning process(ACP) proposed to reduce the overall volume of the PWR spent fuel and improve safety and economy of the long-term storage of spent fuel. In the next phase(2004∼2006), the hot test will be carried out for verification of the ACP in a laboratory scale. For the hot test, the hot cell facilities of α- type and auxiliary facilities are required essentially for safe handling of high radioactive materials. As the hot cell facilities for demonstration of the ACP, a existing hot cell of β- type will be refurbished to minimize construction expenditures of hot cell facility. Up to now, the detail design of hot cell facilities and process were completed, and the safety analysis was performed to substantiate secure of conservative safety. The design data were submitted for licensing which was necessary for construction and operation of hot cell facilities. The safety investigation of KINS on hot cell facilities was completed, and the license for construction and operation of hot cell facilities was acquired already from MOST. In this report, the safety analysis report submitted to KINS was summarized. And also, the questionnaires issued from KINS and answers of KAERI in process of safety investigation were described in detail

HOTLAB: European hot laboratories research capacities and needs. Plenary meeting 2004

International Nuclear Information System (INIS)

Oberlaender, B.C.; Jenssen, H.K.

2005-01-01

The report presents proceedings from the 2004 annual HOTLAB plenary meeting at Halden and Kjeller, Norway. The goal of the yearly plenary meeting was to: Exchange experience on analytical methods, their implementation in hot cells, the methodologies used and their application in nuclear research. Share experience on common infrastructure exploitation matters such as remote handling techniques, safety features, QA-certification, waste handling, etc. Promote normalisation and co-operation, e.g. by looking at mutual complementarities. Prospect present and future demands from the nuclear industry and to draw strategic conclusions regarding further needs. The main themes of the five topical oral sessions of the Halden plenary meeting cover: Work package leaders report and specific papers, presentation of PIE facility databases, i.e. one worldwide (IAEA) and one inside the European communities. Reports from present and future needs and on nuclear transports. Refabrication and instrumentation: Available equipment, technical characteristics such as fabrication procedures, hot-cell compatibility, and practical experiences. Post irradiation examination: Updated and new remote techniques and methodologies, new materials such as inert matrix fuels, spallation sources and neutron absorber materials. Refurbishment and decommissioning: reports on refurbishment and decommissioning of PIE facilities. Waste and transport: Hot laboratory waste characteristics and handling, spent fuel research. Several posters are presented

AECL hot-cell facilities and post-irradiation examination services

International Nuclear Information System (INIS)

Schankula, M.H.; Plaice, E.L.; Woodworth, L.G.

1998-04-01

This paper presents an overview of the post-irradiation examination (PIE) services available at AECL's hot-cell facilities (HCF). The HCFs are used primarily to provide PIE support for operating CANDU power reactors in Canada and abroad, and for the examination of experimental fuel bundles and core components irradiated in research reactors at the Chalk River Laboratories (CRL) and off-shore. A variety of examinations and analyses are performed ranging from non-destructive visual and dimensional inspections to detailed optical and scanning electron microscopic examinations. Several hot cells are dedicated to mechanical property testing of structural materials and to determine the fitness-for-service of reactor core components. Facility upgrades and the development of innovative examination techniques continue to improve AECL's PIE capabilities. (author)

AECL hot-cell facilities and post-irradiation examination services

International Nuclear Information System (INIS)

Schankula, M.H.; Plaice, E.L.; Woodworth, L.G.

1995-01-01

This paper presents an overview of the post-irradiation examination (PIE) services available at AECL's hot-cell facilities (HCF). The HCFs are used primarily to provide PIE support for operating CANDU power reactors in Canada and abroad, and for the examination of experimental fuel bundles and core components irradiated in research reactors at the Chalk River Laboratories (CRL) and off-shore. A variety of examinations and analysis are performed ranging from non-destructive visual and dimensional inspections to detailed optical and scanning electron microscopic examinations. Several hot cells are dedicated to mechanical property testing of structural materials and to determine the fitness-for-service of reactor core components. Facility upgrades and the development of innovative examination techniques continue to improve AECL's PIE capabilities. (author)

Annual report on operation and management of hot laboratories and facilities. From April 1, 2006 to March 31, 2007

International Nuclear Information System (INIS)

2008-02-01

This is an annual report in a fiscal year 2006 that describes activities of the Reactor Fuel Examination Facility (RFEF), the Waste Safety Testing Facility (WASTEF), the Research Hot Laboratory (RHL) and the other research hot facilities in the Department of Hot laboratories and facilities. In RFEF, destructive examinations of BWR fuel rods and re-assembly were carried out as PIEs for a fuel assembly irradiated for 5 cycles in the Fukushima-2 Nuclear Power Station Unit-1. Mechanical property measurement of high burn-up fuel rods were performed as spent fuel integrity test for long term dry storage in order to formulate guidelines and technical criteria. In WASTEF, Slow Strain Rate Tests (SSRT) and Uni-axial Constant Load Tensile tests (UCLT) of in-core materials in pressurized high-temperature water condition, stress corrosion cracking tests for high-performance fuel cladding material and calorific value measurement of pulse irradiated fuel in NSRR were carried out. In RHL, equipment un-installations and decontamination were performed to lead cells according to the decommissioning plan. And modification of fuel storage room were started in order to utilize the facility for un-irradiated fuel storage after a fiscal year 2007. In addition, management of the other research hot facilities (No.1 Plutonium Laboratory, No.2 Research Laboratory, No.4 Research Laboratory, Analytical Chemistry Laboratory, Uranium Enrichment Laboratory, (Simulation Test for Environmental Radionuclide Migration (STEM), Clean Laboratory for Environmental Analysis and Research (CLEAR) and fuel storage) were carried out. (author)

A university hot laboratory for teaching and research

International Nuclear Information System (INIS)

Heinonen, O.; Miettinen, J.K.

1976-01-01

In small countries which have limited material and capital resources there is more need for studying and teaching reactor chemistry in universities than there is in countries with special nuclear research and training centres. A new 150-m 2 laboratory of reactor chemistry was added to the premises of the Department of Radiochemistry, University of Helsinki, in October 1975. It contains a hot area with low-pressure air-conditioning, a sanitary room, a low-activity area, and an office area. The main instrument is a mass-spectrometer MI-1309 equipped with an ion counter which is particularly useful for plutonium analysis. The laboratory can handle samples up-to 10Ci gamma-acitivity - which equals one pellet of a fuel rod - in a sealed lead cell which has an interchangeable box for alpha-active work. Pretreated samples are submitted to chemical separations in glove-boxes. Samples for alpha and mass spectroscopy are also prepared in glove-boxes. Also the laboratory is provided with fume hoods suitable for building lead shields. Radiation protection and special features typical to the university environment are discussed. Methods for verfication of contamination and protection against internal and external contamination are applied. These include air monitoring, analysis of excreta, and whole-body counting. (author)

HOTLAB: European hot laboratories research and capacities and needs. Plenary meeting 2004

Energy Technology Data Exchange (ETDEWEB)

Oberlaender, B.C.; Jenssen, H.K. (ed.)

2005-01-01

The report presents proceedings from the 2004 annual HOTLAB plenary meeting at Halden and Kjeller, Norway. The goal of the yearly plenary meeting was to: Exchange experience on analytical methods, their implementation in hot cells, the methodologies used and their application in nuclear research. Share experience on common infrastructure exploitation matters such as remote handling techniques, safety features, QA-certification, waste handling, etc. Promote normalisation and co-operation, e.g. by looking at mutual complementarities. Prospect present and future demands from the nuclear industry and to draw strategic conclusions regarding further needs. The main themes of the five topical oral sessions of the Halden plenary meeting cover: Work package leaders report and specific papers, presentation of PIE facility databases, i.e. one worldwide (IAEA) and one inside the European communities. Reports from present and future needs and on nuclear transports. Refabrication and instrumentation: Available equipment, technical characteristics such as fabrication procedures, hot-cell compatibility, and practical experiences. Post irradiation examination: Updated and new remote techniques and methodologies, new materials such as inert matrix fuels, spallation sources and neutron absorber materials. Refurbishment and decommissioning: reports on refurbishment and decommissioning of PIE facilities. Waste and transport: Hot laboratory waste characteristics and handling, spent fuel research. Several posters are presented.

Hot Chemistry Laboratory decommissioning activities at IPEN/CNEN-SP, Brazil

International Nuclear Information System (INIS)

Camilo, Ruth L.; Lainetti, Paulo E.O.

2009-01-01

IPEN's fuel cycle activities were accomplished in laboratory and pilot plant scale and most facilities were built in the 70-80 years. Nevertheless, radical changes of the Brazilian nuclear policy in the beginning of 90's determined the interruption of several fuel cycle activities and facilities shutdown. Since then, IPEN has faced the problem of the pilot plants decommissioning considering that there was no experience/expertise in this field at all. In spite of this, some laboratory and pilot plant decommissioning activities have been performed in IPEN in the last years, even without previous experience and training support. One of the first decommissioning activities accomplished in IPEN involved the Hot Chemistry Laboratory. This facility was built in the beginning of the 80's with the proposal of supporting research and development in the nuclear chemistry area. It was decided to settle a new laboratory in the place where the Hot Chemistry Laboratory was installed, being necessary its total releasing from the radioactive contamination point of view. The previous work in the laboratory involved the manipulation of samples of irradiated nuclear fuel, besides plutonium-239 and uranium-233 standard solutions. There were 5 glove-boxes in the facility but only 3 were used with radioactive material. The glove-boxes contained several devices and materials, besides the radioactive compounds, such as: electric and electronic equipment, metallic and plastic pieces, chemical reagents, liquid and solid radioactive wastes, etc. The laboratory's decommissioning process was divided in 12 steps. This paper describes the procedures, problems faced and results related to the Hot Chemistry Laboratory decommissioning operations and its reintegration as a new laboratory of the Chemical and Environmental Technology Center (CQMA) - IPEN-CNEN/SP. (author)

Development of welding technique by remote control at the JMTR Hot Laboratory

International Nuclear Information System (INIS)

Shimizu, Michio; Iwamatu, Sigemi; Takada, Humiki

2000-03-01

Several kinds of welding techniques have been systematically developed using the remote controlled procedures in the JMTR Hot Laboratory. These are as follows, (1) re-instrumentation's of FP gas pressure gauge and thermocouple to an irradiated fuel rod for the centerline temperature measurement, (2) welding of the un-irradiated/irradiated specimen and machining process to produce tensile test specimens, (3) fabrication of Co-60 radiation source from materials for reactivity adjustment in JMTR core, (4) re-capsuling of irradiated materials in the different types of irradiation facilities. These research and development of circumferential and sealed welding for capsuling and welding of irradiated specimen for re-irradiation were implemented under the remote-controlled conditions in the Hot Cell. These techniques will be very indispensable for supporting the irradiation experiments to be conducted in the JMTR. (author)

LASER ABLATION-INDUCTIVELY COUPLED PLASMA-ATOMIC EMISSION SPECTROSCOPY STUDY AT THE 222-S LABORATORY USING HOT-CELL GLOVE BOX PROTOTYPE SYSTEM

International Nuclear Information System (INIS)

Lockrem, L.L.; Owens, J.W.; Seidel, C.M.

2009-01-01

This report describes the installation, testing and acceptance of the Waste Treatment and Immobilization Plant procured laser ablation-inductively coupled plasma-atomic emission spectroscopy (LA-ICP-AES) system for remotely analyzing high-level waste samples in a hot cell environment. The 2005-003; ATS MP 1027, Management Plan for Waste Treatment Plant Project Work Performed by Analytical Technical Services. The APD group at the 222-S laboratory demonstrated acceptable turnaround time (TAT) and provide sufficient data to assess sensitivity, accuracy, and precision of the LA-ICP-AES method

Hot laboratory in Saclay. Equipment and radio-metallurgy technique of the hot lab in Saclay. Description of hot cell for handling of plutonium salts. Installation of an hot cell; Laboratoire a tres haute activite de Saclay. Equipement et techniques radiometallurgiques du laboratoire a haute activite de Saclay. Description de cellules pour manipulation de sels de plutonium. Amenagement d'une cellule du laboratoire de haute activite

Energy Technology Data Exchange (ETDEWEB)

Bazire, R; Blin, J; Cherel, G; Duvaux, Y; Cherel, G; Mustelier, J P; Bussy, P; Gondal, G; Bloch, J; Faugeras, P; Raggenbass, A; Raggenbass, P; Fufresne, J [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

1959-07-01

Describes the conception and installation of the hot laboratory in Saclay (CEA, France). The construction ended in 1958. The main aim of this laboratory is to examine fuel rods of EL2 and EL3 as well as nuclear fuel studies. It is placed in between both reactors. In a first part, the functioning and specifications of the hot lab are given. The different hot cells are described with details of the ventilation and filtration system as well as the waste material and effluents disposal. The different safety measures are explained: description of the radiation protection, decontamination room and personnel monitoring. The remote handling equipment is composed of cutting and welding machine controlled with manipulators. Periscopes are used for sight control of the operation. In a second part, it describes the equipment of the hot lab. The unit for an accurate measurement of the density of irradiated uranium is equipped with an high precision balance and a thermostat. The equipment used for the working of irradiated uranium is described and the time length of each operation is given. There is also an installation for metallographic studies which is equipped with a manipulation bench for polishing and cleaning surfaces and a metallographic microscope. X-ray examination of uranium pellets will also be made and results will be compared with those of metallography. The last part describes the hot cells used for the manipulation of plutonium salts. The plutonium comes from the reprocessing plant and arrived as a nitric solution. Thus these cells are used to study the preparation of plutonium fluorides from nitric solution. The successive operations needed are explained: filtration, decontamination and extraction with TBP, purification on ion exchangers and finally formation of the plutonium fluorides. Particular attention has been given to the description of the specifications of the different gloveboxes and remote handling equipment used in the different reaction steps and

Hot laboratory in Saclay. Equipment and radio-metallurgy technique of the hot lab in Saclay. Description of hot cell for handling of plutonium salts. Installation of an hot cell; Laboratoire a tres haute activite de Saclay. Equipement et techniques radiometallurgiques du laboratoire a haute activite de Saclay. Description de cellules pour manipulation de sels de plutonium. Amenagement d'une cellule du laboratoire de haute activite

Energy Technology Data Exchange (ETDEWEB)

Bazire, R.; Blin, J.; Cherel, G.; Duvaux, Y.; Cherel, G.; Mustelier, J.P.; Bussy, P.; Gondal, G.; Bloch, J.; Faugeras, P.; Raggenbass, A.; Raggenbass, P.; Fufresne, J. [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

1959-07-01

Describes the conception and installation of the hot laboratory in Saclay (CEA, France). The construction ended in 1958. The main aim of this laboratory is to examine fuel rods of EL2 and EL3 as well as nuclear fuel studies. It is placed in between both reactors. In a first part, the functioning and specifications of the hot lab are given. The different hot cells are described with details of the ventilation and filtration system as well as the waste material and effluents disposal. The different safety measures are explained: description of the radiation protection, decontamination room and personnel monitoring. The remote handling equipment is composed of cutting and welding machine controlled with manipulators. Periscopes are used for sight control of the operation. In a second part, it describes the equipment of the hot lab. The unit for an accurate measurement of the density of irradiated uranium is equipped with an high precision balance and a thermostat. The equipment used for the working of irradiated uranium is described and the time length of each operation is given. There is also an installation for metallographic studies which is equipped with a manipulation bench for polishing and cleaning surfaces and a metallographic microscope. X-ray examination of uranium pellets will also be made and results will be compared with those of metallography. The last part describes the hot cells used for the manipulation of plutonium salts. The plutonium comes from the reprocessing plant and arrived as a nitric solution. Thus these cells are used to study the preparation of plutonium fluorides from nitric solution. The successive operations needed are explained: filtration, decontamination and extraction with TBP, purification on ion exchangers and finally formation of the plutonium fluorides. Particular attention has been given to the description of the specifications of the different gloveboxes and remote handling equipment used in the different reaction steps and

Removal of an acid fume system contaminated with perchlorates located within hot cell

International Nuclear Information System (INIS)

Rosenberg, K.E.; Henslee, S.P.; Vroman, W.R.; Krsul, J.R.; Michelbacher, J.A.; Knighton, G.C.

1992-09-01

An add scrubbing system located within the confines of a highly radioactive hot cell at Argonne National Laboratory-West (ANL-W) was remotely removed. The acid scrubbing system was routinely used for the dissolution of irradiated reactor fuel samples and structural materials. Perchloric acid was one of the acids used in the dissolution process and remained in the system with its inherent risks. Personnel could not enter the hot cell to perform the dismantling of the acid scabbing system due to the high radiation field and the explosion potential associated with the perchlorates. A robot was designed and built at ANL-W and used to dismantle the system without the need for personnel entry into the hot cell. The robot was also used for size reduction of removed components and loading of the removed components into waste containers

Decommissioning of the Risoe Hot Cell facility

International Nuclear Information System (INIS)

Carlsen, H.

1993-10-01

A concise description of the current status of the decommissioning of the hot cell capacity at Risoe National Laboratory is given in this 6th periodic report covering January 1st to June 30th, 1993. All registered and safeguarded fissile material has been removed and the task of cutting and packing scrap material and experimental equipment from the concrete cell line has been completed. Concrete cells 5 and 6 have been finally cleaned and the master slave manipulators removed from them. The major part of the contamination on the shutters and shutter houses were on their horizontal planes and the main contaminant was 137 Cs. Here the surfaces were cleaned by wiping with wet cloths. The method is described. Tables illustrating the resulting contamination levels are included, the density is now low on the shutters. The method of final inn-cell cleaning is explained, and here again tables represent the resulting contamination levels. The work on ''hot spot'' removal and remote cleaning by vacuuming continues on the remaining cells. A collective dose of ca. 16.3 man-mSv was ascribed to 18 persons in the first half of 1993, arising mainly from in-cell work and waste handling. To sum up, the main results from this period are successful removal of last waste from the cells, remote cleaning of cells 2 and 3, final condition for all shutters and shutter housings and final condition for cells 5 and 6. Tables illustrate measured dose rates in detail. (AB)

Surveillance and radiological protection in the Hot Cell laboratory; Vigilancia y proteccion radiologica en el Laboratorio de Celdas Calientes

Energy Technology Data Exchange (ETDEWEB)

Ramirez, J.M.; Torre, J. De la; Garcia C, M.A. [ININ, A.P. 18-1027, 11801 Mexico D.F. (Mexico)

2004-07-01

The Hot Cells Laboratory (LCC) located in the National Institute of Nuclear Research are an installation that was designed for the management at distance of 10,000 Curies of Co-60 or other radioactive materials with different values in activity. The management of such materials in the installation, implies to analyze and to determine the doses that the POE will receive as well as the implementation of protection measures and appropriate radiological safety so that is completed the specified by the ALARA concept. In this work it is carried out an evaluation of the doses to receive for the POE when managing radionuclides with maximum activities that can be allowed in function of the current conditions of the cells and an evaluation of results is made with the program of surveillance and radiological protection implemented for the development of the works that carried out in the installation. (Author)

Los Alamos Hot-Cell-Facility modifications for examining FFTF fuel pins

International Nuclear Information System (INIS)

Campbell, B.M.; Ledbetter, J.M.

1982-01-01

Commissioned in 1960, the Wing 9 Hot Cell Facility at Los Alamos was recently modified to meet the needs of the 1980s. Because fuel pins from the Fast Flux Test Facility (FFTF) at the Hanford Engineering Development Laboratory (HEDL) are too long for examination in the original hot cells, we modified cells to accommodate longer fuel pins and to provide other capabilities as well. For instance, the T-3 shipping cask now can be opened in an inert atmosphere that can be maintained for all nondestructive and destructive examinations of the fuel pins. The full-length pins are visually examined and photographed, the wire wrap is removed, and fission gas is sampled. After the fuel pin is cropped, a cap is seal-welded on the section containing the fuel column. This section is then transferred to other cells for gamma-scanning, radiography, profilometry, sectioning for metallography, and chemical analysis

Decommissioning of the Risoe hot cell facility

International Nuclear Information System (INIS)

Carlsen, H.

1992-02-01

Concise descriptions of actions taken in relation to the decommissioning of the hot cell facility at Risoe National Laboratory are presented. The removal of fissile material, of large contaminated equipment from the concrete cell line and a separate shielded storage facility, and the removal of large contaminated facilities such as out cell parts of a tube transport system between a concrete cell and a lead shielded steel box and a remotely operated Reichert Telatom microscope housed in a lead shielded glove box is described in addition to the initial mapping of radiation levels related to the decontamination of concrete cells. The dose commitment of 17.7 mSv was ascribed to 12 persons in the 2nd half of 1991. The work resulting in these doses was mainly handling of waste together with the frogman entrances in order to repair the in-cell crane and power manipulator. The overall time schedule for the project still appears to be applicable. (AB)

Waste reduction efforts through the evaluation and procurement of a digital camera system for the Alpha-Gamma Hot Cell Facility at Argonne National Laboratory-East

International Nuclear Information System (INIS)

Bray, T. S.; Cohen, A. B.; Tsai, H.; Kettman, W. C.; Trychta, K.

1999-01-01

The Alpha-Gamma Hot Cell Facility (AGHCF) at Argonne National Laboratory-East is a research facility where sample examinations involve traditional photography. The AGHCF documents samples with photographs (both Polaroid self-developing and negative film). Wastes generated include developing chemicals. The AGHCF evaluated, procured, and installed a digital camera system for the Leitz metallograph to significantly reduce labor, supplies, and wastes associated with traditional photography with a return on investment of less than two years

Hot-cell verification facility

International Nuclear Information System (INIS)

Eschenbaum, R.A.

1981-01-01

The Hot Cell Verification Facility (HCVF) was established as the test facility for the Fuels and Materials Examination Facility (FMEF) examination equipment. HCVF provides a prototypic hot cell environment to check the equipment for functional and remote operation. It also provides actual hands-on training for future FMEF Operators. In its two years of operation, HCVF has already provided data to make significant changes in items prior to final fabrication. It will also shorten the startup time in FMEF since the examination equipment will have been debugged and operated in HCVF

Report on operation, utilization and technical development of research reactors and hot laboratory

International Nuclear Information System (INIS)

1980-03-01

Activities of the Division of Research Reactor Operation in fiscal 1978 are described. The division is responsible for operation and maintenance of JRR-2, JRR-3, JRR-4 and Hot Laboratory. In the above connection, various other works are performed, including technical management of fuel and coolant, radiation control, irradiation technique, etc. In Hot Laboratory, postirradiation examinations of fuels and materials are made, and also development of examination methods. (author)

Report on operation utilization and technical development of research reactors and hot laboratory

International Nuclear Information System (INIS)

1982-03-01

Activities of the Division of Research Reactor Operation in fiscal 1980 are described. The division is responsible for operation and maintenance of JRR-2, JRR-3, JRR-4 and Hot Laboratory. In the above connection, various other works are performed, including technical management of fuel and coolant, radiation control, irradiation technique, etc. In Hot Laboratory, postirradiation examinations of fuels and materials are made, and also development of examination methods. (author)

Report on operation, utilization and technical development of Research Reactors and Hot Laboratory

International Nuclear Information System (INIS)

1984-10-01

Activities of the Division of Research Reactor Operation in fiscal 1981 are described. The division is responsible for operation and maintenance of JRR-2, JRR-3, JRR-4 and Hot Laboratory. In the above connection, various other works are performed, including technical management of fuel and coolant, radiation control, irradiation technique, etc. In Hot Laboratory, postirradiation examinations of fuels and materials are made, and also development of examination methods. (author)

LASER ABLATION-INDUCTIVELY COUPLED PLASMA-ATOMIC EMISSION SPECTROSCOPY STUDY AT THE 222-S LABORATORY USING HOT-CELL GLOVE BOX PROTOTYPE SYSTEM

International Nuclear Information System (INIS)

Seidel, C.M.; Jain, J.; Owens, J.W.

2009-01-01

This report describes the installation, testing, and acceptance of the Waste Treatment and Immobilization Plant (WTP) procured laser ablation-inductively coupled plasma-atomic emission spectroscopy (LA-ICP-AES) system for remotely analyzing high-level waste (HLW) samples in a hot cell environment. The work was completed by the Analytical Process Development (APD) group in accordance with Task Order 2005-003; ATS MP 1027, Management Plan for Waste Treatment Plant Project Work Performed by Analytical Technical Services. The APD group at the 222-S Laboratory demonstrated acceptable turnaround time (TAT) and provide sufficient data to assess sensitivity, accuracy, and precision of the LA-ICP-AES method

Characterisation study of radionuclides in Hot Cell Facility

International Nuclear Information System (INIS)

Ghare, P.T.; Rath, D.P.; Govalkar, Atul; Mukherjee, Govinda; AniIKumar, S.; Yadav, R.K.B.; Mallik, G.K.

2016-01-01

Examination of different types of experimental as well as power reactor irradiated fuels and validation of fuel modeling codes is carried out in general Hot cell facility. The Hot cell facility has six concrete shielded hot cells, capable of handling radioactivity varying from 3.7 TBQ to 3700 TBq gamma activity. The facility was augmented with two hot cells having designed capacity to handle radioactivity of 9250 TBQ of equivalent activity of 60 Co. The study of characterization of various radionuclides present inside the hot cell of PIE facility was taken up. This study will help in providing valuable inputs for various radiological safety parameters to keep personnel exposure to ALARA level as per the mandate of radiation safety program

Fire protection at hot laboratories: Prevention, surveillance and fire-fighting

International Nuclear Information System (INIS)

Chappellier, A.M.

1976-01-01

After pointing out that fire in a hot laboratory can be an important factor contributing to a radioactivity accident, the author briefly recalls the items to be taken into account in a fire hazard analysis. He then describes various important aspects of prevention, detection and fire-fighting which - at the French Commissariat a l'Energie Atomique - are governed by already defined rules or by guidelines which are sufficiently advanced to give a clear idea of the final conclusions to be drawn therefrom. From the point of view protection, the concept of fire sector has been evolved, at hot laboratories, becomes the fire and contamination sector, so as to ensure under all circumstances the containment of any radioactive materials dispersed in the premises on fire. Regarding fire detection, a study should be made on the constraints specific to the facility and liable to affect detector operation. These include ventilation, radiations, neutral or corrosive atmosphere, etc. As regards fire-fighting, two particular aspects are dealt with, namely the question of using water in case of fire and action to be taken concerning ventilation. A practical example - the protection of a ventilation system - is described. In conclusion the paper refers to the need for a thorough analysis specific to each hot laboratory, and to the importance of preparing an operational plan so as to avoid any dangerous improvisations in case of an accident. (author)

Cleanout and decontamination of radiochemical hot cells

International Nuclear Information System (INIS)

Surma, J.E.; Holton, L.K. Jr.; Katayama, Y.B.; Gose, J.E.; Haun, F.E.; Dierks, R.D.

1990-01-01

The Pacific Northwest Laboratory is developing and employing advanced remote and contact technologies in cleaning out and decontaminating six radiochemical hot cells at Hanford under the Department of Energy's Surplus Facilities Management Program. The program is using a series of remote and contact decontamination techniques to reduce costs and to significantly lower radiation doses to workers. Refurbishment of the cover blocks above the air lock trench reduced radiation exposure in the air lock and cleanout and decontamination of an analytical cell achieved a reduction in radioactive contamination. Nuclear Regulatory Commission-approved Type B burial boxes are also being used to reduce waste disposal costs and radiation doses. PNL is currently decommissioning its pilot-scale radioactive liquid-fed ceramic melter. Special tools have been developed and are being used to accomplish the world's first such effort. 4 refs., 5 figs

Applying hot-wire anemometry to directly measure the water balance in a proton exchange membrane fuel cell

DEFF Research Database (Denmark)

Al Shakhshir, Saher; Andreasen, Søren Juhl; Berning, Torsten

2016-01-01

In order to better understand and more accurately measure the water balance in a proton exchange membrane fuel cell, our group has recently proposed to apply hot wire anemometry in the fuel cell's anode outlet. It was theoretically shown that the electrical signal obtained from the hot wire sensor...... can be directly converted into the fuel cell water balance. In this work an ex-situ experimental investigation is performed to examine the effect of the wire diameter and the outlet pipe diameter on the voltage signal. For a laboratory fuel cell where the mass flow rate the anode outlet is small...... number Nu range between m = 0.137 and m = 0.246. In general, it is shown that applying hot wire anemometry yields in fact very clear voltage readings with high frequency, and it can be used as a diagnosis tool in various fuel cell applications....

Design and management of hot-laboratories. [Manual]. Hottorabo no sekkei to kanri

Energy Technology Data Exchange (ETDEWEB)

1976-09-01

This document is a manual for the design and management of hot-laboratories. It is composed of three parts. The first part is devoted to the design of hot-laboratories. Items included here are; conceptual design; many regulations which must be considered at design stage; design of cave and its shielding; and the design of building, ventilation, and draining. Many examples of specific designs are presented by figures and photographs. The second part is concerned with the methods of operation management. Organizational structure, scheduling of operation, process management, and regulatory problems are discussed with some examples. Technological problems associated with the operation of a hot laboratory (e.g., manipulator, transfer machine, maintenance, and decontamination) are also discussed based on the authors' experiences. An example of the operation manual is presented for reference. The third part is devoted to the safety management and the training of personnel. The regulations by law are briefly explained. Most of this part is devoted to the problem of monitoring radio-activity. Monitoring of control areas, radio-active wastes, and personal dosage is discussed together with many other specific monitoring problems. As for training, the purpose and the present status are explained.

Rockwell International Hot Laboratory decontamination and dismantlement interim progress report 1987-1996

International Nuclear Information System (INIS)

None

1997-01-01

OAK A271 Rockwell International Hot Laboratory decontamination and dismantlement interim progress report 1987-1996. The Rockwell International Hot Laboratory (RIHL) is one of a number of former nuclear facilities undergoing decontamination and decommissioning (D and D) at the Santa Susana Field Laboratory (SSFL). The RIHL facility is in the later stages of dismantlement, with the final objective of returning the site location to its original natural state. This report documents the decontamination and dismantlement activities performed at the facility over the time period 1988 through 1996. At this time, the support buildings, all equipment associated with the facility, and the entire above-ground structure of the primary facility building (Building 020) have been removed. The basement portion of this building and the outside yard areas (primarily asphalt and soil) are scheduled for D and D activities beginning in 1997

Current status and future prospects of JMTR Hot Laboratory

International Nuclear Information System (INIS)

Baba, Osamu; Ooka, Norikazu; Hoshiya, Taiji

1999-01-01

A wide variety of post-irradiation examinations (PIEs) for research and development of nuclear fuels and materials to be utilized in nuclear field is available in three kinds of β - γ hot cells; concrete, lead and steel cells in the JMTR Hot Laboratory (JMTR HL) associated with the Japan Materials Testing Reactor (JMTR). In addition to PIEs, re-capsuling including re-instrumentation on the irradiated specimen is currently conducted for the power ramping tests of the LWR fuels using the Boiling Water Capsule (BOCA) or for the re-irradiation tests in the different neutron fields (coupling irradiation test). The newly developed techniques by the JMTR HL have provided us with the key information about the irradiation effects on mechanical and physical properties of the specimen in various environments as fission and fusion reactors. These techniques are focused on several topics as follows; (1) miniaturized specimen test as an advanced mechanical test, (2) slow strain rate tensile test (SSRT) and crack propagation measurement in high temperature and pressure water for the study of Irradiation Assisted Stress Corrosion Cracking (IASCC) of LWR core internals, (3) handling technique on materials containing tritium for the research and development of tritium breeders and neutron multiplier for fusion reactors, (4) jointing method using the conventional Tungsten Inert Gas (TIG) welding for re-assembling of irradiation capsules and/or re-fabrication of specimen, and (5) Nondestructive examination using ultrasonic wave and infrared thermography for the quantitative evaluation of irradiation embrittlement of structural materials in fission and fusion reactors. As there are various PIE facilities around Oarai site, mutual exchange of PIE information, interchange of researchers and mutual utilization on PIE facilities are desired to raise the scientific and technical potential on PIE and to get the break-through of the study in the field of nuclear applications. (author)

Dismantling of a hot cell of high level activity. Method and tools used

International Nuclear Information System (INIS)

Jeantet, E.; Miquel, P.; Baudoin, J.C.; Moutonnet, A.

1981-05-01

The aim of this operation is the removal of all the equipment and the material introduced and used in the hot cell 'Attila' and its decontamination to obtain an irradiation level as low as possible to allow direct intervention. The Attila facilitie was build in 1964-1966 to study dry processing of irradiated fuels by halogenide volatility process. Dismantling of the out-cell and of the laboratory associated to the shielded cell, dismantling inside the shielded cell with the remote handling equipment of the cell and tools used for these operations are described in this article [fr

Construction of concrete hot cells

International Nuclear Information System (INIS)

1981-12-01

The standard is to be applied to rooms (hot cells) which are enclosed by a concrete shield and in which radioactive material is handled by remote control. The rooms may be in facilities for experimental purposes (e.g. development of fuel elements and materials or of chemical processes) or in facilities for production purposes (e.g. reprocessing of nuclear fuel or treatment of radioactive wastes). The standard is to give a design hasis for concrete hot cells and their installations which is to be applied by designers, constructors, future users and competent authorities as well as independent experts. (orig.) [de

Construction of concrete hot cells

International Nuclear Information System (INIS)

1980-09-01

The standard is to be applied to rooms (hot cells) which are enclosed by a concrete shield and in which radioactive material is handled by remote control. The rooms may be in facilities for experimental purposes (e.g. development of fuel elements and materials or of chemical processes) or in facilities for production purposes (e.g. reprocessing of nuclear fuel or treatment of radioactive wastes). The standard is to give a design basis for concrete hot cells and their installations which is to be applied by designers, constructors, future users and competent authorities as well as independent experts. (orig.) [de

Hot cell design in the vitrification plant China

International Nuclear Information System (INIS)

Jiang Yubo; Wang Guangkai; Zhang Wei; Liang Runan; Dou Yuan

2015-01-01

In the area of reprocessing and radioactive waste management, gloveboxes and cells are a kind of non-standard equipments providing an isolated room to operate radioactive material inside, while the operator outside with essential biological shield and protection. The hot cell is a typical one, which could handle high radioactive material with various operating means and tight enclosure. The dissertation is based on Vitrification Plant China, a cooperation project between China and Germany. For the sino-western difference in design philosophy, it was presented how to draft an acceptable design proposal of applicable huge hot cells by analysing the design requirements, such as radioprotection, observation, illumination, remote handling, transportation, maintenance and decontamination. The construction feasibility of hot cells was also approved. Thanks to 3D software Autodesk Inventor, digital hot cell was built to integrate all the interfaces inside, which validated the design by checking the mechanical interference. (author)

Hot Cell Installation and Demonstration of the Severe Accident Test Station

Energy Technology Data Exchange (ETDEWEB)

Linton, Kory D. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Burns, Zachary M. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Terrani, Kurt A. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Yan, Yong [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

2017-08-01

A Severe Accident Test Station (SATS) capable of examining the oxidation kinetics and accident response of irradiated fuel and cladding materials for design basis accident (DBA) and beyond design basis accident (BDBA) scenarios has been successfully installed and demonstrated in the Irradiated Fuels Examination Laboratory (IFEL), a hot cell facility at Oak Ridge National Laboratory. The two test station modules provide various temperature profiles, steam, and the thermal shock conditions necessary for integral loss of coolant accident (LOCA) testing, defueled oxidation quench testing and high temperature BDBA testing. The installation of the SATS system restores the domestic capability to examine postulated and extended LOCA conditions on spent fuel and cladding and provides a platform for evaluation of advanced fuel and accident tolerant fuel (ATF) cladding concepts. This document reports on the successful in-cell demonstration testing of unirradiated Zircaloy-4. It also contains descriptions of the integral test facility capabilities, installation activities, and out-of-cell benchmark testing to calibrate and optimize the system.

Hot Corrosion Test Facility at the NASA Lewis Special Projects Laboratory

Science.gov (United States)

Robinson, Raymond C.; Cuy, Michael D.

1994-01-01

The Hot Corrosion Test Facility (HCTF) at the NASA Lewis Special Projects Laboratory (SPL) is a high-velocity, pressurized burner rig currently used to evaluate the environmental durability of advanced ceramic materials such as SiC and Si3N4. The HCTF uses laboratory service air which is preheated, mixed with jet fuel, and ignited to simulate the conditions of a gas turbine engine. Air, fuel, and water systems are computer-controlled to maintain test conditions which include maximum air flows of 250 kg/hr (550 lbm/hr), pressures of 100-600 kPa (1-6 atm), and gas temperatures exceeding 1500 C (2732 F). The HCTF provides a relatively inexpensive, yet sophisticated means for researchers to study the high-temperature oxidation of advanced materials, and the injection of a salt solution provides the added capability of conducting hot corrosion studies.

The development of synthetic test procedure for hot cell equipment systems in IMEF

International Nuclear Information System (INIS)

Ahn, Sang Bok; Lee, Key Soon; Park, Dae Kyu; Hong, Kwon Pyo; Choo, Yong Sun

1998-04-01

Hot cell facility should be confirmed to operation safety through pre-commissioning test after construction. In this report, the detailed procedure of hot cell equipment are described. The contents are as follows: 1. Entrance equipment of hot cell 2. Specimen transportation equipment between hot cells 3. Waste discharge equipment in hot cell 4. Specimen loading equipment to hot cell 5. Interlinking equipment in hot cell. (author). 4 tabs

Reversible electron–hole separation in a hot carrier solar cell

International Nuclear Information System (INIS)

Limpert, S; Bremner, S; Linke, H

2015-01-01

Hot-carrier solar cells are envisioned to utilize energy filtering to extract power from photogenerated electron–hole pairs before they thermalize with the lattice, and thus potentially offer higher power conversion efficiency compared to conventional, single absorber solar cells. The efficiency of hot-carrier solar cells can be expected to strongly depend on the details of the energy filtering process, a relationship which to date has not been satisfactorily explored. Here, we establish the conditions under which electron–hole separation in hot-carrier solar cells can occur reversibly, that is, at maximum energy conversion efficiency. We thus focus our analysis on the internal operation of the hot-carrier solar cell itself, and in this work do not consider the photon-mediated coupling to the Sun. After deriving an expression for the voltage of a hot-carrier solar cell valid under conditions of both reversible and irreversible electrical operation, we identify separate contributions to the voltage from the thermoelectric effect and the photovoltaic effect. We find that, under specific conditions, the energy conversion efficiency of a hot-carrier solar cell can exceed the Carnot limit set by the intra-device temperature gradient alone, due to the additional contribution of the quasi-Fermi level splitting in the absorber. We also establish that the open-circuit voltage of a hot-carrier solar cell is not limited by the band gap of the absorber, due to the additional thermoelectric contribution to the voltage. Additionally, we find that a hot-carrier solar cell can be operated in reverse as a thermally driven solid-state light emitter. Our results help explore the fundamental limitations of hot-carrier solar cells, and provide a first step towards providing experimentalists with a guide to the optimal configuration of devices. (paper)

Conceptual layout design of CFETR Hot Cell Facility

Energy Technology Data Exchange (ETDEWEB)

Gong, Zheng, E-mail: gongz@mail.ustc.edu.cn [University of Science and Technology of China, Hefei 230026 (China); Institute of Plasma Physics, Chinese Academy of Sciences, Hefei (China); Qi, Minzhong, E-mail: qiminzhong@ipp.ac.cn [Institute of Plasma Physics, Chinese Academy of Sciences, Hefei (China); Cheng, Yong, E-mail: chengyong@ipp.ac.cn [Institute of Plasma Physics, Chinese Academy of Sciences, Hefei (China); Song, Yuntao, E-mail: songyt@ipp.ac.cn [University of Science and Technology of China, Hefei 230026 (China); Institute of Plasma Physics, Chinese Academy of Sciences, Hefei (China)

2015-11-15

Highlights: • This article proposed a conceptual layout design for CFETR. • The design principles are to support efficient maintenance to ensure the realization of high duty time. • The preliminary maintenance process and logistics are described in detail. • Life cycle management, maneuverability, risk and safety are in the consideration of design. - Abstract: CFETR (China Fusion Engineering Test Reactor) is new generation of Tokomak device beyond EAST in China. An overview of hot cell layout design for CFETR has been proposed by ASIPP&USTC. Hot Cell, as major auxiliary facility, not only plays a pivotal role in supporting maintenance to meet the requirements of high duty time 0.3–0.5 but also supports installation and decommissioning. Almost all of the Tokomak devices are lateral handling internal components like ITER and JET, but CFETR maintain the blanket module from 4 vertical ports, which is quite a big challenge for the hot cell layout design. The activated in-vessel components and several diagnosis instruments will be repaired and refurbished in the Hot Cell Facility, so the appropriate layout is very important to the Hot Cell Facility to ensure the high duty time, it is divided into different parts equipped with a variety of RH equipment and diagnosis devices based on the functional requirements. The layout of the Hot Cell Facility should make maintenance process more efficient and reliable, and easy to service and rescue when a sudden events taking place, that is the capital importance issue considered in design.

Hot Cell Window Shielding Analysis Using MCNP

International Nuclear Information System (INIS)

Pope, Chad L.; Scates, Wade W.; Taylor, J. Todd

2009-01-01

The Idaho National Laboratory Materials and Fuels Complex nuclear facilities are undergoing a documented safety analysis upgrade. In conjunction with the upgrade effort, shielding analysis of the Fuel Conditioning Facility (FCF) hot cell windows has been conducted. This paper describes the shielding analysis methodology. Each 4-ft thick window uses nine glass slabs, an oil film between the slabs, numerous steel plates, and packed lead wool. Operations in the hot cell center on used nuclear fuel (UNF) processing. Prior to the shielding analysis, shield testing with a gamma ray source was conducted, and the windows were found to be very effective gamma shields. Despite these results, because the glass contained significant amounts of lead and little neutron absorbing material, some doubt lingered regarding the effectiveness of the windows in neutron shielding situations, such as during an accidental criticality. MCNP was selected as an analysis tool because it could model complicated geometry, and it could track gamma and neutron radiation. A bounding criticality source was developed based on the composition of the UNF. Additionally, a bounding gamma source was developed based on the fission product content of the UNF. Modeling the windows required field inspections and detailed examination of drawings and material specifications. Consistent with the shield testing results, MCNP results demonstrated that the shielding was very effective with respect to gamma radiation, and in addition, the analysis demonstrated that the shielding was also very effective during an accidental criticality.

Hot cells of the Osiris reactor

International Nuclear Information System (INIS)

Jourdain, Jean

1969-10-01

Hot cells of the Osiris reactor are β and γ type cells. Their main functions are: the extraction of irradiated samples from experimental assemblies (irradiation loops, experimental devices) used to irradiate them, the reinstallation of experimental setups with irradiated samples, the fractioning of unrecoverable experimental devices, and the removal of irradiated samples and active wastes. Each cell is therefore equipped with means for remote handling, for observation and for removal, and a venting. Each cell may also receive additional equipment, notably for the dismantling of experimental setups. This report presents the cell implantation in the reactor, elements to be handled in cells, the path followed by elements to be handled (arrival, departure, conveyors). It describes the cells (capacity and protection, design and construction, external and internal arrangements) and the cell equipment (remote handling devices, windows, lighting, lifting unit, sound system), and the installed electric power. A realisation planning is provided. An appendix indicates the cost of these hot cells

Design Report for ACP Hot Cell Rear Door

Energy Technology Data Exchange (ETDEWEB)

Ku, J. H.; Kwon, K. C.; Choung, W. M.; Cho, I. J.; Kook, D. H.; Lee, W. K.; You, G. S.; Lee, E. P.; Park, S. W

2005-12-15

A hot-cell facility was constructed at the IMEF building for the demonstrate ACP process. ACP hot-cell consists of process cell and maintenance cell, and each cell has rear door. Since this facility was constructed at basement floor, all process materials, equipment and radioactive materials are take in and out through the rear door. Also, this door can be an access route of workers for the maintenance works. Therefore ACP hot-cell rear doors must maintain the radiation shielding, sealing, mechanical and structural safety. This report presents design criteria, design contents of each part and driving part. It was confirmed that the rear doors sufficiently maintain the safety through the structural analysis and shielding analysis. Also, it was confirmed that the rear doors were constructed as designed by the gamma scanning test after the installation.

Design Report for ACP Hot Cell Rear Door

International Nuclear Information System (INIS)

Ku, J. H.; Kwon, K. C.; Choung, W. M.; Cho, I. J.; Kook, D. H.; Lee, W. K.; You, G. S.; Lee, E. P.; Park, S. W.

2005-12-01

A hot-cell facility was constructed at the IMEF building for the demonstrate ACP process. ACP hot-cell consists of process cell and maintenance cell, and each cell has rear door. Since this facility was constructed at basement floor, all process materials, equipment and radioactive materials are take in and out through the rear door. Also, this door can be an access route of workers for the maintenance works. Therefore ACP hot-cell rear doors must maintain the radiation shielding, sealing, mechanical and structural safety. This report presents design criteria, design contents of each part and driving part. It was confirmed that the rear doors sufficiently maintain the safety through the structural analysis and shielding analysis. Also, it was confirmed that the rear doors were constructed as designed by the gamma scanning test after the installation

Development of a new bench for puncturing of irradiated fuel rods in STAR hot laboratory

Science.gov (United States)

Petitprez, B.; Silvestre, P.; Valenza, P.; Boulore, A.; David, T.

2018-01-01

A new device for puncturing of irradiated fuel rods in commercial power plants has been designed by Fuel Research Department of CEA Cadarache in order to provide experimental data of high precision on fuel pins with various designs. It will replace the current set-up that has been used since 1998 in hot cell 2 of STAR facility with more than 200 rod puncturing experiments. Based on this consistent experimental feedback, the heavy-duty technique of rod perforation by clad punching has been preserved for the new bench. The method of double expansion of rod gases is also retained since it allows upgrading the confidence interval of volumetric results obtained from rod puncturing. Furthermore, many evolutions have been introduced in the new design in order to improve its reliability, to make the maintenance easier by remote handling and to reduce experimental uncertainties. Tightness components have been studied with Sealing Laboratory Maestral at Pierrelatte so as to make them able to work under mixed pressure conditions (from vacuum at 10-5 mbar up to pressure at 50 bars) and to lengthen their lifetime under permanent gamma irradiation in hot cell. Bench ergonomics has been optimized to make its operating by remote handling easier and to secure the critical phases of a puncturing experiment. A high pressure gas line equipped with high precision pressure sensors out of cell can be connected to the bench in cell for calibration purposes. Uncertainty analyses using Monte Carlo calculations have been performed in order to optimize capacity of the different volumes of the apparatus according to volumetric characteristics of the rod to be punctured. At last this device is composed of independent modules which allow puncturing fuel pins out of different geometries (PWR, BWR, VVER). After leak tests of the device and remote handling simulation in a mock-up cell, several punctures of calibrated specimens have been performed in 2016. The bench will be implemented soon in hot

Seismic evaluation of a hot cell structure

International Nuclear Information System (INIS)

Srinivasan, M.G.; Kot, C.A.

1995-01-01

The evaluation of the structural capacity of and the seismic demand on an existing hot cell structure in a nuclear facility is described. An ANSYS finite-element model of the cell was constructed, treating the walls as plates and the floor and ceiling as a system of discrete beams. A modal analysis showed that the fundamental frequencies of the cell walls lie far above the earthquake frequency range. An equivalent static analysis of the structure was performed. Based on the analysis it was demonstrated that the hot cell structure, would readily withstand the evaluation basis earthquake

Decommissioning of the Risoe Hot Cell facility

International Nuclear Information System (INIS)

Carlsen, H.

1993-02-01

A concise description of the current status (December 31st, 1992) regarding the decommissioning of the hot cell facility at Risoe National Laboratory is given in this periodic report. During the second half of the year 1992, all remaining fissile material and a large amount of contaminated material were removed, major repair work was carried out on the in-cell crane, the shielded storage facility was decontaminated and sealed, iodine filters in the cell ventilation system were removed, remote cleaning was carried out on three concrete cells to radiation levels acceptable for final cleaning by frogmen, and the remaining work schedule was planned. These processes are briefly described. Some breakdowns of older, but vital equipment (i.e. the in-cell crane and the power manipulator) that was taken into extensive use led to a certain amount of delay. The collective radiation doses during this half-year were no higher than under normal operation of the facility, and amounted to 12 man-mSv ascribed to 14 persons. It was concluded that, when removing old epoxy paint in the cells using paint strippers applied by hand, personnel can wear polythene oversuits, although a technique for remote handling has been developed. Tables illustrate measured radiation levels in cells number 1,4,5 and 6, and a diagram describes the shielded storage facility. (AB)

New electron beam facility for irradiated plasma facing materials testing in hot cell

International Nuclear Information System (INIS)

Sakamoto, N.; Kawamura, H.; Akiba, M.

1995-01-01

Since plasma facing components such as the first wall and the divertor for the next step fusion reactors are exposed to high heat loads and high energy neutron flux generated by the plasma, it is urgent to develop of plasma facing components which can resist these. Then, we have established electron beam heat facility (open-quotes OHBISclose quotes, Oarai Hot-cell electron Beam Irradiating System) at a hot cell in JMTR (Japan Materials Testing Reactor) hot laboratory in order to estimate thermal shock resistivity of plasma facing materials and heat removal capabilities of divertor elements under steady state heating. In this facility, irradiated plasma facing materials (beryllium, carbon based materials and so on) and divertor elements can be treated. This facility consists of an electron beam unit with the maximum beam power of 50kW and the vacuum vessel. The acceleration voltage and the maximum beam current are 30kV (constant) and 1.7A, respectively. The loading time of electron beam is more than 0.1ms. The shape of vacuum vessel is cylindrical, and the mainly dimensions are 500mm in inner diameter, 1000mm in height. The ultimate vacuum of this vessel is 1 x 10 -4 Pa. At present, the facility for thermal shock test has been established in a hot cell. And performance estimation on the electron beam is being conducted. Presently, the devices for heat loading tests under steady state will be added to this facility

New electron beam facility for irradiated plasma facing materials testing in hot cell

International Nuclear Information System (INIS)

Shimakawa, S.; Akiba, M.; Kawamura, H.

1996-01-01

Since plasma facing components such as the first wall and the divertor for the next step fusion reactors are exposed to high heat loads and high energy neutron flux generated by the plasma, it is urgent to develop plasma facing components which can resist these. We have established electron beam heat facility ('OHBIS', Oarai hot-cell electron beam irradiating system) at a hot cell in JMTR (Japan materials testing reactor) hot laboratory in order to estimate thermal shock resistivity of plasma facing materials and heat removal capabilities of divertor elements under steady state heating. In this facility, irradiated plasma facing materials (beryllium, carbon based materials and so on) and divertor elements can be treated. This facility consists of an electron beam unit with the maximum beam power of 50 kW and the vacuum vessel. The acceleration voltage and the maximum beam current are 30 kV (constant) and 1.7 A, respectively. The loading time of the electron beam is more than 0.1 ms. The shape of vacuum vessel is cylindrical, and the main dimensions are 500 mm in inside diameter, 1000 mm in height. The ultimate vacuum of this vessel is 1 x 10 -4 Pa. At present, the facility for the thermal shock test has been established in a hot cell. The performance of the electron beam is being evaluated at this time. In the future, the equipment for conducting static heat loadings will be incorporated into the facility. (orig.)

Linear thermal expansion coefficient measurement technology in hot cell

International Nuclear Information System (INIS)

Park, Dae Gyu; Choo, Yong Sun; Ahn, Sang Bok; Hong, Kwon Pyo; Lee, K. S.

1998-06-01

To establish linear thermal expansion coefficient measurement technology in hot cell, we reviewed and evaluated various measuring technology by paper and these were compared with the data produced with pre-installed dilatometer in hot cell. Detailed contents are as follows; - The theory of test. - Review of characteristics for various measurement technology and compatibility with hot cell. - Review of standard testing regulations(ASTM). - System calibration of pre-installed dilatometer. - Performance test of pre-installed dilatometer. (author). 12 refs., 15 tabs., 8 figs

25th-year jubilee edition of the Hot Laboratory's annual report

International Nuclear Information System (INIS)

Bart, G.

1989-07-01

The topics discussed in this report concern the history of PSI's Hot Laboratory, nuclear fuel development performed there during the last twenty years, post irradiation examination work, basic research for a final repository of radioactive wastes, and neutron embrittlement experiments. 44 figs., 1 tab., 82 refs

Remote Robotic Cleaning System for Contaminated Hot-Cell Floor

International Nuclear Information System (INIS)

Kim, Ki Ho; Park, Jang Jin; Yang, Myung S.; Kwon, Hyo Kjo

2005-01-01

The M6 hot-cell of the Irradiated Material Examination Facility at the Korea Atomic Energy Research Institute (KAERI) has been contaminated with spent fuel debris and other radioactive waste due to the DUPIC nuclear fuel development processes. As the hot-cell is active, direct human workers' access, even with protection, to the in-cell is not possible because of the nature of the high radiation level of the spent PWR fuel. A remote robotic cleaning system has been developed for use in a highly radioactive environment of the M6 hot-cell. The remote robotic cleaning system was designed to completely eliminate human interaction with hazardous radioactive contaminants. This robotic cleaning system was also designed to remove contaminants or contaminated smears placed or fixed on the floor of the M6 hot-cell by mopping it in a remote manner. The environmental, functional and mechanical design considerations, control system and capabilities of the developed remote robotic cleaning system are presented

Hot-cell shielding system for high power transmission in DUPIC fuel fabrication

International Nuclear Information System (INIS)

Kim, K.; Lee, J.; Park, J.; Yang, M.; Park, H.

2000-01-01

This paper presents a newly designed hot-cell shielding system for use in the development of DUPIC (Direct Use of spent PWR fuel In CANDU reactors) fuel at KAERI (Korea Atomic Energy Research Institute). This hot-cell shielding system that was designed to transmit high power to sintering furnace in-cell from the out-of-cell through a thick cell wall has three subsystems - a steel shield plug with embedded spiral cooling line, stepped copper bus bars, and a shielding lead block. The dose-equivalent rates of the hot-cell shielding system and of the apertures between this system and the hot-cell wall were calculated. Calculated results were compared with the allowable dose limit of the existing hot-cell. Experiments for examining the temperature changes of the shielding system developed during normal furnace operation were also carried out. Finally, gamma-ray radiation survey experiments were conducted by Co-60 source. It is demonstrated that, from both calculated and experimental results, the newly designed hot-cell shielding system meets all the shielding requirements of the existing hot-cell facility, enabling high power transmission to the in-cell sintering furnace. (author)

Decontamination of hot cells K-1, K-3, M-1, M-3, and A-1, M-Wing, Building 200: Project final report Argonne National Laboratory-East

International Nuclear Information System (INIS)

Cheever, C.L.; Rose, R.W.

1996-09-01

The purpose of this project was to remove radioactively contaminated materials and equipment from the hot cells, to decontaminate the hot cells, and to dispose of the radioactive waste. The goal was to reduce stack releases of Rn-220 and to place the hot cells in an emptied, decontaminated condition with less than 10 microSv/h (1 mrem/h) general radiation background. The following actions were needed: organize and mobilize a decontamination team; prepare decontamination plans and procedures; perform safety analyses to ensure protection of the workers, public, and environment; remotely size-reduce, package, and remove radioactive materials and equipment for waste disposal; remotely decontaminate surfaces to reduce hot cell radiation background levels to allow personnel entries using supplied air and full protective suits; disassemble and package the remaining radioactive materials and equipment using hands-on techniques; decontaminate hot cell surfaces to remove loose radioactive contaminants and to attain a less than 10 microSv/h (1 mrem/h) general background level; document and dispose of the radioactive and mixed waste; and conduct a final radiological survey

Decommissioning of the Risoe Hot Cell facility

International Nuclear Information System (INIS)

Carlsen, H.

1994-06-01

Nuclear fuels have been handled and examined after irradiation by physical and chemical techniques, and radiotherapy sources, mainly 60 Co, have been produced at Risoe National Laboratory since 1964. The aims of decommissioning (during 1990-94, at IAEA Stage 2 level for reactors) were to obtain safe conditions for the remaining parts of the facility and to produce clean space areas for new projects. The facility comprises 6 concrete cells, several lead-shielded steel cells, glove boxes, shielded storage for waste, a remotely operated optical microscope, a frogman area for personnel access to the concrete cells, a decontamination facility, workshops and safety installations. All steel cells, glove boxes and the microscope were emptied and removed. The concrete cells were emptied of fissile material, scientific equipment, general tools and scrap. Decontamination should facilitate waste packing and reduce amount of waste to be stored temporarily at the Risoe waste treatment facility together with highly active waste. The concrete cells were cleaned remotely by wiping, hot spot removal, by mechanical means and vacuum cleaning. The interiors of 2 cells were decontaminated by high pressure water jetting. All master-slave manipulators and part of the contaminated ventilation system at the cells were removed. The cells are left in a non-ventilated state, connected to the atmosphere by an absolute filter. The main contaminants measured before cell closure were 60 Co, 137 Cs and alpha-emitters. Dismantling, decontamination waste disposal and received doses are described. Simple techniques involving low doses were found to be very effective. (AB)

Application of Cyclone to Removal of Hot Particulate in Hot Cell

International Nuclear Information System (INIS)

Kim, Gye Nam; Lee, Sung Yeol; Won, Hui Jun; Jung, Chong Hun; Oh, Won Zin

2005-01-01

The size and main ingredient of hot particulate generated during the nuclide experiment in hot cells of nuclear facilities were 0.5300 μm and UO 2 . A cyclone filter equipment which consists of a cyclone and Bag/HEPA filter was devised to remove hot particulate generated during the nuclide experiment in hot cells of nuclear facilities. The experimental conditions to maximize the collection efficiency of hot particulate were suggested through experiments done with the cyclone filter equipment. With the large size of simulated particulate, the collection efficiency of the particulate was high. When the size of simulated particulate was more than 5 μm, the collection efficiency of the particulate was more than 80% and when the size of simulated particulate was less than 1.0 μm, the collection efficiency decreased by less than. If the inflow velocity of simulated particulate was increased, the collection efficiency of the particulate was also increased. When the inflow velocity of simulated particulate was more than 12 m/sec, the collection efficiency was higher than , but after 17 m/sec inflow velocity, no change observed. The collection efficiency of the simulated particulate can be enhanced with the length of vortex finder inside the chamber. With the length of vortex finder, 7.2 cm, the observed collection efficiency of the particulate was the maximum. Moreover, when the sub-cone was attached under the cyclone, the collection efficiency of cyclone increased 2%. It was found that effect by attachment of sub-cone was not serious.

Validation of a Hot Water Distribution Model Using Laboratory and Field Data

Energy Technology Data Exchange (ETDEWEB)

Backman, C.; Hoeschele, M.

2013-07-01

Characterizing the performance of hot water distribution systems is a critical step in developing best practice guidelines for the design and installation of high performance hot water systems. Developing and validating simulation models is critical to this effort, as well as collecting accurate input data to drive the models. In this project, the ARBI team validated the newly developed TRNSYS Type 604 pipe model against both detailed laboratory and field distribution system performance data. Validation efforts indicate that the model performs very well in handling different pipe materials, insulation cases, and varying hot water load conditions. Limitations of the model include the complexity of setting up the input file and long simulation run times. In addition to completing validation activities, this project looked at recent field hot water studies to better understand use patterns and potential behavioral changes as homeowners convert from conventional storage water heaters to gas tankless units. Based on these datasets, we conclude that the current Energy Factor test procedure overestimates typical use and underestimates the number of hot water draws. This has implications for both equipment and distribution system performance. Gas tankless water heaters were found to impact how people use hot water, but the data does not necessarily suggest an increase in usage. Further study in hot water usage and patterns is needed to better define these characteristics in different climates and home vintages.

Validation of a Hot Water Distribution Model Using Laboratory and Field Data

Energy Technology Data Exchange (ETDEWEB)

Backman, C. [Alliance for Residential Building Innovation (ARBI), Davis, CA (United States); Hoeschele, M. [Alliance for Residential Building Innovation (ARBI), Davis, CA (United States)

2013-07-01

Characterizing the performance of hot water distribution systems is a critical step in developing best practice guidelines for the design and installation of high performance hot water systems. Developing and validating simulation models is critical to this effort, as well as collecting accurate input data to drive the models. In this project, the Building America research team ARBI validated the newly developed TRNSYS Type 604 pipe model against both detailed laboratory and field distribution system performance data. Validation efforts indicate that the model performs very well in handling different pipe materials, insulation cases, and varying hot water load conditions. Limitations of the model include the complexity of setting up the input file and long simulation run times. This project also looked at recent field hot water studies to better understand use patterns and potential behavioral changes as homeowners convert from conventional storage water heaters to gas tankless units. The team concluded that the current Energy Factor test procedure overestimates typical use and underestimates the number of hot water draws, which has implications for both equipment and distribution system performance. Gas tankless water heaters were found to impact how people use hot water, but the data does not necessarily suggest an increase in usage. Further study in hot water usage and patterns is needed to better define these characteristics in different climates and home vintages.

Decommissioning of the Risoe Hot Cell facility

International Nuclear Information System (INIS)

Carlsen, H.

1991-02-01

The Hot Cell facility at Risoe has been in active use since 1964. During the years several types of nuclear fuels have been handled and examined: test reactor fuel pins from the Danish reactor DR3, the Norwegian Halden reactor, etc; power reactor fuel pins from several foreign reactors, including plutonium enriched pins; HTGR fuel from the Dragon reactor. All kinds of physical and chemical non-destructive and destructive post irradiation examinations have been performed. Besides, different radiotherapy sources have been produced, mainly cobalt sources. The general object of the decommissioning programme for the Hot Cell facility was to obtain a safe condition for the total building that does not require the special safety provisions. The hot cell building will be usable for other purposes after decommissioning. The facilicy comprised six concrete cells, lead cells, glove boxes, a shielded unit for temporary storage of waste, frogman area, decontamination areas, workshops, various installations of importance for safe operation of the plant, offices, etc. The tasks comprised e.g. removal of all irradiated fuel items, removal of other radioactive items, removal of contaminated equipment, and decontamination of all the cells and rooms. The goal was to decontaminate all the concrete cells to a degree where no loose contamination exists in the cells, and where the radiation level is so low, that total removal of the cell structures can be done at any time in the future without significant dose commitments. (AB)

Shield wall evaluation of hot cell facility for advanced spent fuel conditioning process

International Nuclear Information System (INIS)

Cho, I. J.; Kuk, D. H.; Ko, J. H.; Jung, W. M.; Yoo, G. S.; Lee, E. P.; Park, S. W.

2002-01-01

The future hot cell is located in the Irradiated Material Experiment Facility (IMEF) at the Korea Atomic Energy Research Institute (KAERI). It is β-γ type hot cell that was constructed on the base floor in IMEF building for irradiated material testing. And this hot cell will be used for carrying out the Advanced spent fuel Conditioning Process (ACP). The radiation shielding capability of hot cell should be sufficient to meet the radiation dose requirements in the related regulations. Because the radioactive sources of ACP are expected to be higher than radioactive sources of IMEF design criteria, the future hot cell in current status is unsatisfactory to hot test of ACP. So the shielding analysis of the future hot cell is performed to evaluate shielding ability of concrete shield wall. The shielding analysis included (a) identification of ACP source term; (b) photon source spectrum; (c) shielding analysis by QADS and MCNP-4C; and (d) enhancement of concrete shield wall. In this research, dose rates are obtained according to ACP source, geometry and hot cell shield wall thickness. And the evaluation and reinforcement thickness of the shield wall about future hot cell are concluded

Development of a hot cell for post-irradiation analysis of nuclear fuels

Energy Technology Data Exchange (ETDEWEB)

Silva, Selma S.C.; Silva Junior, Silverio Ferreira da; Loureiro, Joao Roberto M. [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)], e-mail: selmasallam@yahoo.com.br, e-mail: silvasf@cdtn.br, e-mail: jrmattos@cdtn.br

2009-07-01

Post irradiation examinations of nuclear fuels are performed in order to verify their in-service behavior. Examinations are conducted in compact structures called hot cells, designed to attend the different types of tests and analysis for fuel's characterization. The characterization of fuel microstructure is an activity performed in hot cells. Usually, hot cells for microstructural fuel analysis are designed to allow the metallographic and ceramographic samples preparation and after that, microscopical analysis of the fuel's microstructure. Due to the complexity of the foreseen operations, the severe limitations imposed by the available space into the hot cells, the capabilities of the remote manipulation devices, the procedures of radiological protection and the needs to obtain samples with an adequate surface quality for microscopic analysis, the design of a hot cell for fuel samples preparation presents a high level of complexity. In this paper, the methodology used to develop a hot cell facility for nuclear fuel's metallographic and ceramographic samples preparation is presented. Equipment, devices and systems used in conventional sample preparation processes were evaluated during bench tests. After the necessary adjustments and processes adaptations, they were assembled in a mock-up of the respective hot cell, where they were tested in conditions as realistic as possible, in order to improve the operations and processes to be performed at the real hot cells. (author)

Development of a hot cell for post-irradiation analysis of nuclear fuels

International Nuclear Information System (INIS)

Silva, Selma S.C.; Silva Junior, Silverio Ferreira da; Loureiro, Joao Roberto M.

2009-01-01

Post irradiation examinations of nuclear fuels are performed in order to verify their in-service behavior. Examinations are conducted in compact structures called hot cells, designed to attend the different types of tests and analysis for fuel's characterization. The characterization of fuel microstructure is an activity performed in hot cells. Usually, hot cells for microstructural fuel analysis are designed to allow the metallographic and ceramographic samples preparation and after that, microscopical analysis of the fuel's microstructure. Due to the complexity of the foreseen operations, the severe limitations imposed by the available space into the hot cells, the capabilities of the remote manipulation devices, the procedures of radiological protection and the needs to obtain samples with an adequate surface quality for microscopic analysis, the design of a hot cell for fuel samples preparation presents a high level of complexity. In this paper, the methodology used to develop a hot cell facility for nuclear fuel's metallographic and ceramographic samples preparation is presented. Equipment, devices and systems used in conventional sample preparation processes were evaluated during bench tests. After the necessary adjustments and processes adaptations, they were assembled in a mock-up of the respective hot cell, where they were tested in conditions as realistic as possible, in order to improve the operations and processes to be performed at the real hot cells. (author)

Multipurpose reprocessing hot cell

International Nuclear Information System (INIS)

Fletcher, R.D.

1975-01-01

A multipurpose hot cell is being designed for use at the Idaho Chemical Processing Plant for handling future scheduled fuels that cannot be adequately handled by the existing facilities and equipment. In addition to providing considerable flexibility to handle a wide variety of fuel sizes up to 2,500 lb in weight the design will provide for remote maintenance or replacement of the in-cell equipment with a minimum of exposure to personnel and also provide process piping connections for custom processing of small quantities of fuel. (auth)

Development of Radioactive Substance Contamination Diffusion Preventive Equipment for a Hot cell

International Nuclear Information System (INIS)

Choo, Yong Sun; Kim, Do Sik; Baik, Seung Je; Yoo, Byung Ok; Kim, Ki Ha; Lee, Eun Pyo; Ahn, Sang Bok; Ryu, Woo Seok

2009-01-01

The hot cell of irradiated materials examination facility (IMEF), which has been operating since 1996, is generally contaminated by the radioactive nuclides of irradiated nuclear fuels and structural steels like Cs-137, Co-60, Co-134 and Ru-106. Especially Cs-137 is a main contaminated radioactive isotope which is easily moved here and there due to air flow in the hot cell, water-soluble, extremely toxic, and has a half-life of 30.23 years. To repair or fix the abnormal function of test apparatus installed in the hot cell, the maintenance door, so called a rear door and located at an intervention area, is opened to enter the hot cell inside. In a moment of opening the maintenance door, dirty air diffusion from the hot cell to an intervention area could be occurred in spite of increasing the rpm of exhaust fan to maintain much low under pressure, but an adjacent area to a maintenance door, i.e. intervention area, is very severely contaminated due to the unpredictable air flow. In this paper, the development of the radioactive substance contamination diffusion preventive equipment for a hot cell is studied to prevent dirty and toxic gaseous radioactive nuclides diffusion from a hot cell and installed at an intervention area of IMEF

Dose levels in the hot cells area ININ

International Nuclear Information System (INIS)

Torre, J. De la; Ramirez, J.M.; Solis, M.L.

2004-01-01

The Laboratory of Hot Cells (LCC) located in the National Institute of Nuclear Research (ININ) is an institution, it is an area where radioactive material is managed with different activity values, in function of its original design for 10,000 curies of Co-60. Managing this materials in the installation, it implies to measure and to analyze the dose levels that the POE will receive as well as the implementation of appropriate measures of radiological protection and radiological safety, so that that is completed settled down by the concept ALARA. In this work they are carried out mensurations of the levels of the dose to receive for the POE when managing radionuclides with maximum activities that can be allowed in function of the current conditions of the cells and an evaluation of the obtained results is made comparing them with the effective international norms as well as the application of the program of surveillance and radiological protection implemented for the development of the works that are carry out in the installation. (Author)

Annual report on operation, utilization and technical development of research reactors and hot laboratory

International Nuclear Information System (INIS)

1990-09-01

This report describes the activities of the Department of Research Reactor Operation in fiscal year of 1989. It also presents some technical topics on the reactor operation and utilization in details. The Department is responsible for operation of the research reactors, JRR-2 and JRR-4, and the Hot Laboratory. The research reactor JRR-3 was reconstructed to enhance the performance for utilization. The first criticality was achieved on March 22, 1989, and it subsequently went into operation. In connection with the reactor operation, the various research and development activities in the area of fuel management, water chemistry, radiation monitoring and material irradiation have been made. In the Hot Laboratory, post-irradiation examinations of fuels and materials have been carried out along with the development of related techniques. (author)

Hot Cell Facility modifications at Sandia National Laboratories to support 99Mo production

International Nuclear Information System (INIS)

Vernon, M.; Philbin, J.; Berry, D.

1997-01-01

In September, 1996, following the completion of an extensive Environmental Impact Statement (EIS), a record of decision (ROD) was issued by DOE selecting Sandia as the facility to take on the 99 Mo production mission. 99 Mo is the precursor to 99m Tc which is used in 36,000 medical procedures per day in the US. to meet US 99 Mo medical demands, 20 kCi of 99 Mo must be delivered to the pharmaceutical companies each week. This could be accomplished by the processing of twenty-five targets (total fission product of 15 kCi/target) each week within the SNL Hot Cell Facility (HCF). To accomplish this new mission, significant modifications to the HCF will have to be undertaken. This paper presents a brief history of the HCF, and describes modifications necessary to achieve DOE directives

Experience of Integrated Safeguards Approach for Large-scale Hot Cell Laboratory

International Nuclear Information System (INIS)

Miyaji, N.; Kawakami, Y.; Koizumi, A.; Otsuji, A.; Sasaki, K.

2010-01-01

The Japan Atomic Energy Agency (JAEA) has been operating a large-scale hot cell laboratory, the Fuels Monitoring Facility (FMF), located near the experimental fast reactor Joyo at the Oarai Research and Development Center (JNC-2 site). The FMF conducts post irradiation examinations (PIE) of fuel assemblies irradiated in Joyo. The assemblies are disassembled and non-destructive examinations, such as X-ray computed tomography tests, are carried out. Some of the fuel pins are cut into specimens and destructive examinations, such as ceramography and X-ray micro analyses, are performed. Following PIE, the tested material, in the form of a pin or segments, is shipped back to a Joyo spent fuel pond. In some cases, after reassembly of the examined irradiated fuel pins is completed, the fuel assemblies are shipped back to Joyo for further irradiation. For the IAEA to apply the integrated safeguards approach (ISA) to the FMF, a new verification system on material shipping and receiving process between Joyo and the FMF has been established by the IAEA under technical collaboration among the Japan Safeguard Office (JSGO) of MEXT, the Nuclear Material Control Center (NMCC) and the JAEA. The main concept of receipt/shipment verification under the ISA for JNC-2 site is as follows: under the IS, the FMF is treated as a Joyo-associated facility in terms of its safeguards system because it deals with the same spent fuels. Verification of the material shipping and receiving process between Joyo and the FMF can only be applied to the declared transport routes and transport casks. The verification of the nuclear material contained in the cask is performed with the method of gross defect at the time of short notice random interim inspections (RIIs) by measuring the surface neutron dose rate of the cask, filled with water to reduce radiation. The JAEA performed a series of preliminary tests with the IAEA, the JSGO and the NMCC, and confirmed from the standpoint of the operator that this

Hot Cell Facility (HCF) Safety Analysis Report

Energy Technology Data Exchange (ETDEWEB)

MITCHELL,GERRY W.; LONGLEY,SUSAN W.; PHILBIN,JEFFREY S.; MAHN,JEFFREY A.; BERRY,DONALD T.; SCHWERS,NORMAN F.; VANDERBEEK,THOMAS E.; NAEGELI,ROBERT E.

2000-11-01

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 management programs at SNL are described in ancillary chapters of the SAR.

Hot Cell Facility (HCF) Safety Analysis Report

International Nuclear Information System (INIS)

MITCHELL, GERRY W.; LONGLEY, SUSAN W.; PHILBIN, JEFFREY S.; MAHN, JEFFREY A.; BERRY, DONALD T.; SCHWERS, NORMAN F.; VANDERBEEK, THOMAS E.; NAEGELI, ROBERT E.

2000-01-01

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 management programs at SNL are described in ancillary chapters of the SAR

Air system in the hot cell for injectable radiopharmaceutical production: requirements for personnel and environment safety and protection of the product

Energy Technology Data Exchange (ETDEWEB)

Campos, Fabio E.; Araujo, Elaine B., E-mail: fecampos@ipen.b, E-mail: ebaraujo@ipen.b [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

2009-07-01

. Nevertheless, the application of clean room requirements in radioisotope laboratories in general and hot cells is technically not an easy task. The required negative pressure inside the hot cell depends on the operations to be performed inside the cell, on the type of radionuclide and their total activity. Hot cells works in negative pressure that ranges typically from 200 Pa to 500 Pa below room pressure. The new rules for radiopharmaceutical production will be soon published by ANVISA in order to regulate the GMP in this area. This make urgent the development of national models for hot cells that combines GMP and radioprotection concepts and attempt for the radiopharmaceutical process lines as in development at IPEN. (author)

Air system in the hot cell for injectable radiopharmaceutical production: requirements for personnel and environment safety and protection of the product

International Nuclear Information System (INIS)

Campos, Fabio E.; Araujo, Elaine B.

2009-01-01

. Nevertheless, the application of clean room requirements in radioisotope laboratories in general and hot cells is technically not an easy task. The required negative pressure inside the hot cell depends on the operations to be performed inside the cell, on the type of radionuclide and their total activity. Hot cells works in negative pressure that ranges typically from 200 Pa to 500 Pa below room pressure. The new rules for radiopharmaceutical production will be soon published by ANVISA in order to regulate the GMP in this area. This make urgent the development of national models for hot cells that combines GMP and radioprotection concepts and attempt for the radiopharmaceutical process lines as in development at IPEN. (author)

Waste Handling in SVAFO's Hot Cell

International Nuclear Information System (INIS)

Moeller, Jennifer; Ekenborg, Fredrik; Hellsten, Erik

2016-01-01

The decommissioning and dismantling of nuclear installations entails the generation of significant quantities of radioactive waste that must be accepted for disposal. In order to optimise the use of the final repositories for radioactive waste it is important that the waste be sent to the correct repository; that is, that waste containing short-lived radionuclides not be designated as long-lived due to conservative characterisation procedures. The disposal of short-lived waste in a future Swedish repository for long-lived waste will result in increased costs, due to the higher volumetric cost of the disposal as well as costs associated with decades of interim storage before disposal can occur. SVAFO is a non-profit entity that is responsible for the decommissioning of nuclear facilities from historical research and development projects in Sweden. They provide interim storage for radioactive waste arising from research activities until the final repository for long-lived waste is available. SVAFO's offices and facilities are located on the Studsvik site on the east coast of Sweden near the town of Nykoeping. Some of the retired facilities that SVAFO is in the process of decommissioning are located elsewhere in Sweden. The HM facility is a small waste treatment plant owned and operated by SVAFO. The plant processes both liquid and solid radioactive wastes. The facility includes a hot cell equipped with a compactor, a saw and other tools as well as manipulators for the handling and packaging of waste with high dose rates. The cell is fitted with special systems for transporting waste in and passing it out in drums. As with most hot cells there has been an accumulation of surface contamination on the walls, floor and other surfaces during decades of operation. Until recently there has been no attempt to quantify or characterize this contamination. Current practices dictate that after waste is handled in the hot cell it is conservatively designated as long

Certification of the PSI request for the renewal of the operation license for the Hot Laboratory

International Nuclear Information System (INIS)

2014-03-01

At the Paul Scherrer Institute (PSI), the Hot Laboratory was built in the years 1961 to 1963 in the former EIR in order to make scientific material analyses on highly radioactive material samples and to prepare diagnostic and therapeutically useful radioisotopes. The 1964 safety report with the request for the granting of the operational warrant was revised for the first time in 2004. Further safety reports and radiation protection plans were produced and accepted by the surveying authorities. The operational regulations were revised and approved on a yearly basis by the PSI direction. The regulations reflect the experience gained in 40 years of safe operation and take new regulations in nuclear energy legislation into account. In the years 2000-2002 the Hot Lab was refitted especially with respect to the fields of radiation and fire protection. Presently, the Hot Lab is used for applied material research on highly radioactive samples which mainly come from nuclear power plants, research reactors and the target stations of the PSI accelerator facilities. The investigations on highly radioactive samples and the handling of large quantities of radioisotopes include the possibility of incidents. The analysis of such incidents shows that the legal safety requirements are satisfied. The Swiss Federal Nuclear Safety Inspectorate (ENSI) requirements concerning the protection of personnel, population and environment, as well as the protection against fire, are fulfilled. In the Hot Lab the principle of barriers for the containment of radioactive materials is applied. Open radioactive sources are manipulated in depressurized cells. The air extracted from the cells is filtered before being released to the environment. In the building, the total amount of radioactive materials is limited in order to reduce the exposition of the population in normal operation as well as in case of incidents, and to avoid criticality accidents. Possible weaknesses in this concept can be shown

General reformulation of hot cell complex

International Nuclear Information System (INIS)

Almeida, G.L. de; Souza, A.S.F. de; Souza, M.L.M. de; Rautenberg, F.A.

1986-01-01

The implantation of an operation philosophy without direct intervention of operator during isotope production process in hot cells of the CV-28 cyclotron is presented. The modifications carried out in equipments, systems and installations are described. (M.C.K.)

Activity of safety review for the facilities using nuclear material (2). Safety review results and maintenance experiences for hot laboratories

International Nuclear Information System (INIS)

Amagai, Tomio; Fujishima, Tadatsune; Mizukoshi, Yasutaka; Sakamoto, Naoki; Ohmori, Tsuyoshi

2009-01-01

In the site of O-arai Research and Development Center of Japan Atomic Energy Agency (JAEA), five hot laboratories for post-irradiation examination and development of plutonium fuels are operated more than 30 years. A safety review method for preventive maintenance on these hot laboratories includes test facilities and devices are established in 2003. After that, the safety review of these facilities and devices are done and taken the necessary maintenance based on the results in each year. In 2008, 372 test facilities and devices in these hot laboratories were checked and reviewed by this method. As a results of the safety review, repair issues of 38 facilities of above 372 facilities were resolved. This report shows the review results and maintenance experiences based on the results. (author)

Introduction of radiation protection and dosimetry in new hot cell facility in research center Rez

International Nuclear Information System (INIS)

Svrcula, P.; Petrickova, A.; Srba, O.; Miklos, M.; Svoboda, P.

2015-01-01

The purpose of the poster is to present radiation protection and dosimetry in the new hot cell facility being constructed as part of the SUSEN project. The hot cell facility is composed of 10 hot cells and 1 semi-hot cell. All shielding is made from steel, the outer wall shielding has thickness of 500 mm, internal wall between hot cells 300 mm with the possibility to extension to 500 mm. The ceiling shielding has a thickness of 400 mm and the floor shielding is 300 mm wide. Shielded windows allow direct view into the hot cells. Their shielding effect is equivalent to 500 mm of steel. The dimension of the window in the control room is 800 mm x 600 mm with a thickness of 900 mm. All important operating data are collected in the central system of hot cells. The system monitors under-pressure level and temperature in each chamber. If necessary it can directly control the ventilation system. Each hot cell is equipped with dose rate probes. The system also measures and evaluates airborne radioactivity in the building

Decommissioning of hot cells using a hydraulically powered servo manipulator

International Nuclear Information System (INIS)

Asquith, J.D.; Loughborough, D.

1993-01-01

This paper describes the preparations and initial trials involved in remotely dismantling the containment boxes within two concrete shielded hot cells at Harwell Laboratory using a hydraulically powered servo manipulator, ARTISAN. The manipulator deploys a variety of tools for cutting operations. The modular design has enabled it to be specifically configured for this application by adjusting the link lengths using spacers between the joints. In addition to the remote handling requirements, a new posting and ventilation system for the facility is outlined. Trials with ARTISAN in an in-active mock-up have now been successfully completed, and the manipulator is installed in the active facility. The considerations and approach adopted in this project are typical of many situations where remote techniques are required for decommissioning activities. (author)

Engineering hot-cell windows for radiation protection

International Nuclear Information System (INIS)

Ferguson, K.R.; Courtney, J.C.

1983-01-01

Radiation protection considerations in the design and construction of hot-cell windows are discussed. The importance of evaluating the potential gamma spectra and neutron source terms is stressed. 11 references

Hot spots and heavily dislocated regions in multicrystalling silicon cells

International Nuclear Information System (INIS)

Simo, A.; Martinuzzi, S.

1990-01-01

The formation mechanism and the electrical consequences of hot spots have been investigated in multicrystalline solar cells. The hot spots were revealed by means of an infrared camera when the cells are reverse biassed in the dark. The minority carrier diffusion length (L n ), the photovoltage (V oc ) and the photocurrent (J sc ) were measured in the hot spot area and far from this zone thanks to mesa diodes. Dark forward I-V curves lead to values of ideality factor (M) and reverse saturation current (J o ). It is found that J o and M are higher in the hot spot area, while J sc , V oc and at a less extent L n are smaller. Large densities of dislocations and lineages structures are revealed in the abnormally heated regions

Laboratory procedures used in the hot corrosion project

International Nuclear Information System (INIS)

Jeys, T.R.

1980-01-01

The objective of the Hot Corrosion Project in the LLNL Metals and Ceramics Division is to study the physical and chemical mechanisms of corrosion of nickel, iron, and some of their alloys when these metals are subjected to oxidizing or sulfidizing environments at temperatures between 850 and 950 0 C. To obtain meaningful data in this study, we must rigidly control many parameters. Parameters are discussed and the methods chosen to control them in this laboratory. Some of the mechanics and manipulative procedures that are specifically related to data access and repeatability are covered. The method of recording and processing the data from each experiment using an LS-11 minicomputer are described. The analytical procedures used to evaluate the specimens after the corrosion tests are enumerated and discussed

Technical specifications of variable speed motors for negative pressure control in hot cell area

Energy Technology Data Exchange (ETDEWEB)

Kim, Seon Duk; Bang, H. S.; Cho, W. K

2002-01-01

Hot cells are the facilities for handling the high radioactive materials and various R and D activities are performed using hot cells. Therefore the control of air flow in hot cell area is very important technology and it is started with the variable speed motor(VSM) controlling the air handling system in that area. This report describes various technical aspects of VS motors and will be useful for understanding the practical technologies of VS motors and also for optimization of the negative pressure controls in hot cell area.

A Shielding Analysis of Hot Cell for a 10 MW Research Reactor

International Nuclear Information System (INIS)

Alnajjar, Alaaddin; Park, Chang Je; Roh, Gyuhong; Lee, Byunchul

2013-01-01

In this paper, a shielding analysis has been performed for the hot cell in a 10 MW research reactor. Two kinds of shielding analysis code systems are used such as MCNPX2.7 and M-Shield7. The first one is Monte Carlo stochastic code and the second one is a deterministic point kernel code. The results are compared in this study. In order to obtain source term, the ORIGEN-S code is used for different kinds of source. Four kinds of sources are taken into consideration. From the simulation, it is also proposed that the proper thickness of shielding material and the maximum source capacity in the hot cell. This study shows preliminary analysis results of hot cell shielding for 10MW research reactor. Total four different source terms are considered such as spent fuel assembly, Ir-192, Mo-99, and I-131. For shielding material, general concrete, heavy concrete, and lead are used. MCNPX code is mainly used for a simplified hot cell model and the result are nearly consistent when compared with M-Shield code. Required shielding thickness and the hot cell capacity are also obtained for various criterion of surface dose rates

Iodine speciation in the hot cell effluent gases

International Nuclear Information System (INIS)

Lee, B.S.; Jester, W.A.; Olynyk, J.M.

1990-01-01

The various species of airborne radioiodine can affect the iodine source term of a severe core damage accident because of the different transport and deposition properties. also, the radiobiological hazardness may vary according to their chemical form. The purpose of the work reported in this paper was to characterize the various chemical forms of airborne radioiodine in hot cell effluent gases of a radiopharmaceutical production facility that produces medical radioisotopes from separated fission products of irradiated uranium targets. It is concluded that the methyl iodide is the youngest chemical species in terms of effective decay time age, and the hot cell filter bank is least efficient in removing the methyl iodide

Single-nanowire, low-bandgap hot carrier solar cells with tunable open-circuit voltage

Science.gov (United States)

Limpert, Steven; Burke, Adam; Chen, I.-Ju; Anttu, Nicklas; Lehmann, Sebastian; Fahlvik, Sofia; Bremner, Stephen; Conibeer, Gavin; Thelander, Claes; Pistol, Mats-Erik; Linke, Heiner

2017-10-01

Compared to traditional pn-junction photovoltaics, hot carrier solar cells offer potentially higher efficiency by extracting work from the kinetic energy of photogenerated ‘hot carriers’ before they cool to the lattice temperature. Hot carrier solar cells have been demonstrated in high-bandgap ferroelectric insulators and GaAs/AlGaAs heterostructures, but so far not in low-bandgap materials, where the potential efficiency gain is highest. Recently, a high open-circuit voltage was demonstrated in an illuminated wurtzite InAs nanowire with a low bandgap of 0.39 eV, and was interpreted in terms of a photothermoelectric effect. Here, we point out that this device is a hot carrier solar cell and discuss its performance in those terms. In the demonstrated devices, InP heterostructures are used as energy filters in order to thermoelectrically harvest the energy of hot electrons photogenerated in InAs absorber segments. The obtained photovoltage depends on the heterostructure design of the energy filter and is therefore tunable. By using a high-resistance, thermionic barrier, an open-circuit voltage is obtained that is in excess of the Shockley-Queisser limit. These results provide generalizable insight into how to realize high voltage hot carrier solar cells in low-bandgap materials, and therefore are a step towards the demonstration of higher efficiency hot carrier solar cells.

Estimation of radiation exposure for hot cell workers during DUPIC fuel fabrication process in IMEF M6 cell

Energy Technology Data Exchange (ETDEWEB)

Jeon, Yong Bum; Baek, Sang Yeol; Park, Dae Kyu

1997-06-01

DUPIC(Direct Use of spent PWR fuel In CANDU) fuel cycle to utilize the PWR spent fuel in fabricating CANDU fuel, which is expected to reduce not only the total amount of high level radwastes but the energy sources is underway. IMEF M6 cell to be used as DUPIC fuel fabrication facility is refurbished and retrofitted. Radiation exposure for the hot cell worker by dispersion of the radioactive materials during the DUPIC process were estimated on the basis of the hot cell design information. According to the estimation results, DUPIC fuel fabrication process could be run without any severe impacts to the hot cell workers when the ventilation system to maintain the sufficient pressure difference between hotcell and working area and radiation monitoring system is supports the hot cell operation properly. (author). 4 tabs., 6 figs.

The development on electric discharge machine for hot cell usage

International Nuclear Information System (INIS)

Ahn, Sang Bok; Kim, Young Suk; Park, Dae Kyu; Choo, Yong Sun; Oh, Wan Ho

1998-06-01

The electric discharge machine(EDM) was developed for hot cell usages in IMEF. This machine will be used to fabricate specimen directly from irradiated components from NPP's. The detailed contents are as follows; 1. Outline of electric discharge machine 2. Specimen shape to be fabricated by EDM 3. Technical specification to manufacture EDM 4. Installation EDM in hot cell 5. Optimum discharge conditions to fabricate specimens from CANDU tube. (author). 4 tabs., 20 figs

A State of the Art Report on the Case Study of Hot Cell Decontamination and Refurbishment

Energy Technology Data Exchange (ETDEWEB)

Won, H. J.; Jung, C. H.; Moon, J. K.; Park, G. I.; Song, K. C

2008-08-15

As the increase of the operation age of the domestic high radiation facilities such as IMEF, PIEF and DFDF, the necessity of decontamination and refurbishment of hot cells in these facilities is also increased. In the near future, the possibilities of refurbishment of hot cells in compliance with the new regulations, the reuse of hot cells for the other purposes and the decommissioning of the facilities also exist. To prepare against the decontamination and refurbishment of hot cells, the reports on the refurbishment, decommissioning and decontamination experiences of hot cells in USA, Japan, France, Belgium and Great Britain were investigated. ANL of USA performed the project on the decontamination of hot cells. The purpose of the project was to practically eliminate the radioactive emissions of Rn-220 to the environment and to restore the hot cells to an empty restricted use condition. The five hot cells were emptied and decontaminated for restricted use. Chemical processing facility in JAEA of Japan was used for the reprocessing study of spent fuels, hot cells in CPF were refurbished from 1995 for the tests of the newly developed reprocessing process. In a first stage, decommissioning and decontamination were fully performed by the remote operation Then, decommissioning and decontamination were performed manually. By the newly developed process, they reported that the radiation exposure of workers were satisfactorily reduced. In the other countries, they also make an effort for the refurbishment and decontamination of hot cells and it is inferred that they accumulate experiences in these fields.

Use of lasers at the Los Alamos Hot-Cell Facility

International Nuclear Information System (INIS)

Lazarus, M.E.

1983-01-01

An optical profilometer that uses a Techmet LaserMike scanning, focused, laser-beam, optical micrometer is installed in a remote alpha-gamma containment cell at the Los Alamos Hot-Cell Facility. A hot-cell extension chamber provides the nominal 30-cm (12-in.) working distance required by the LaserMike and, at the same time, keeps the LaserMike components outside the high-radiation-containment environment. This system provides measurement accuracy better than +- 5 μm (0.0002 in.) on diameters between 2 and 13 mm (0.88 and 0.5 in.) at a rate of 33 measurements per second. The Hot-Cell Facility also uses a Korad 20-J-output ruby pulsed laser to drill a hole in reactor-fuel-element cladding to sample fission gas. The laser is then used to reweld the hole so that the fuel element will not be contaminated and may be stored without an alpha-containment barrier. The wall thickness of the fuel elements sampled varies from 0.25 to 0.50 mm (0.010 to 0.020 in.)

ITER diagnostics: Maintenance and commissioning in the hot cell test bed

International Nuclear Information System (INIS)

Walker, C.I.; Barnsley, R.; Costley, A.E.; Gottfried, R.; Haist, B.; Itami, K.; Kondoh, T.; Loesser, G.D.; Palmer, J.; Sugie, T.; Tesini, A.; Vayakis, G.

2005-01-01

In-vessel diagnostic equipment in ITER integrated in six equatorial and 12 upper ports, 16 divertor cassettes and five lower ports is designed to be removed in modules and then repaired, tested and commissioned in the same location at the ITER hot cell. The repair requirements and tests on these components are described along with design features that facilitate repair. The testing establishes the repair strategy, qualifies the refurbishment work and finally checks the mechanical and diagnostic function before the return of the modules. At the hot cell, a dummy port is provided for tests of mechanical and vacuum integrity as well as commissioning of the diagnostic equipment. The scope of the hot cell maintenance and commissioning activities is summarised and an overview of the integration of the diagnostic equipment is given

The 'SILOE' reactor at Grenoble, France and associated hot cell facilities. Information sheets

International Nuclear Information System (INIS)

Hardt, P. von der; Roettger, H.

1981-01-01

Technical information is given on the SILOE reactor and associated hot cell facilities, with the main emphasis on experimental irradiation facilities, specialized irradiation devices (loops and capsules) and possibilities for post-irradiation examinations of samples. The information is presented in the form of eight information sheets under the headings: main characteristics of the reactor; utilization and specialization of the reactor; experimental facilities; neutron spectra; main characteristics of specialized irradiation devices; main characteristics of hot cell facilities; equipment and techniques available for post-irradiation examinations; utilization and specialization of the hot cell facilities

The 'OSIRIS' reactor at Saclay, France and available hot cell facilities. Information sheets

International Nuclear Information System (INIS)

Hardt, P. von der; Roettger, H.

1981-01-01

Technical information is given on the OSIRIS reactor and associated hot cell facilities, with the main emphasis on experimental irradiation facilities, specialized irradiation devices (loops and capsules) and possibilities for post-irradiation examinations of samples. The information is presented in the form of eight information sheets under the headings: main characteristics of the reactor; utilization and specialization of the reactor; experimental facilities; neutron spectra; main characteristics of specialized irradiation devices; main characteristics of hot cell facilities; equipment and techniques available for post-irradiation examinations; utilization and specialization of the hot cell facilities

Nonplasmonic Hot-Electron Photocurrents from Mn-Doped Quantum Dots in Photoelectrochemical Cells.

Science.gov (United States)

Dong, Yitong; Rossi, Daniel; Parobek, David; Son, Dong Hee

2016-03-03

We report the measurement of the hot-electron current in a photoelectrochemical cell constructed from a glass/ITO/Al2 O3 (ITO=indium tin oxide) electrode coated with Mn-doped quantum dots, where hot electrons with a large excess kinetic energy were produced through upconversion of the excitons into hot electron hole pairs under photoexcitation at 3 eV. In our recent study (J. Am. Chem. Soc. 2015, 137, 5549), we demonstrated the generation of hot electrons in Mn-doped II-VI semiconductor quantum dots and their usefulness in photocatalytic H2 production reaction, taking advantage of the more efficient charge transfer of hot electrons compared with band-edge electrons. Here, we show that hot electrons produced in Mn-doped CdS/ZnS quantum dots possess sufficient kinetic energy to overcome the energy barrier from a 5.4-7.5 nm thick Al2 O3 layer producing a hot-electron current in photoelectrochemical cell. This work demonstrates the possibility of harvesting hot electrons not only at the interface of the doped quantum dot surface, but also far away from it, thus taking advantage of the capability of hot electrons for long-range electron transfer across a thick energy barrier. © 2016 WILEY-VCH Verlag GmbH & Co. KGaA, Weinheim.

Review of tritium confinement and atmosphere detritiation system in hot cells complex

International Nuclear Information System (INIS)

Rizzello, Claudio; Borgognoni, Fabio; Pinna, Tonio; Tosti, Silvano

2010-01-01

The tritium confinement strategy adopted during the past years in the ITER hot cell building is compared to the safety requirements given by the standard ISO-17873 'Nuclear facilities - criteria for the design and operation of ventilation systems for nuclear installations other than nuclear reactors'. In fact, this is the reference safety guideline recommended by French licensing authorities. Several features of the considered design of the hot cell building are not in agreement with these guidelines. Main discrepancies concern the zoning of the hot cell complex, the flow rates of ventilation, and the possibility to recycle the room atmosphere and to detritiate the effluent air. These aspects are discussed together with some proposed modifications of the design.

Radiation shielding design for a hot repair facility

International Nuclear Information System (INIS)

Courtney, J.C.; Dwight, C.C.

1991-01-01

A new repair and decontamination area is being built to support operations at the demonstration fuel cycle facility for the Integral Fast Reactor program at Argonne National Laboratory's site at the Idaho National Engineering Laboratory. Provisions are made for remote, glove wall, and contact maintenance on equipment removed from hot cells where spent fuel will be electrochemically processed and recycled to the Experimental Breeder Reactor-II. The source for the shielding design is contamination from a mix of fission and activation products present on items removed from the hot cells. The repair facility also serves as a transfer path for radioactive waste produced by processing operations. Radiation shields are designed to limit dose rates to no more than 5 microSv h-1 (0.5 mrem h-1) in normally occupied areas. Point kernel calculations with buildup factors have been used to design the shielding and to position radiation monitors within the area

Annual report on operation, utilization and technical development of Research Reactors and Hot Laboratory, from April 1, 1983 to March 31, 1984

International Nuclear Information System (INIS)

1984-11-01

Activities of the Department of Research Reactor Operation in fiscal year 1983 are described. The department is responsible for operation and maintenance of JRR-2, JRR-3, JRR-4 and Hot Laboratory. In the above connection, various other work has also been performed, such as technical management of fuel and coolant, radiation control, irradiation technique, etc. In Hot Laboratory, we have performed post-irradiation examinations of fuels and materials, and also development of examination procedures, too. (author)

Experience of in-cell visual inspection using CCD camera in hot cell of Reprocessing Plant

International Nuclear Information System (INIS)

Reddy, Padi Srinivas; Amudhu Ramesh Kumar, R.; Geo Mathews, M.; Ravisankar, A.

2013-01-01

This paper describes the selection, customization and operating experience of the visual inspection system for the hot cell of a Reprocessing Plant. For process equipment such as fuel chopping machine, dissolver, centrifuge, centrifugal extractors etc., viewing of operations and maintenance using manipulators is required. For this, the service of in-cell camera is essential. The ambience of the hot cell of Compact facility for Reprocessing of Advanced fuels in Lead cell (CORAL) for the reprocessing of fast reactor spent fuel has high gamma radiation and acidic vapors. Black and white Charge Coupled Device (CCD) camera has been used in CORAL incorporating in-house modifications to suit the operating ambient conditions, thereby extending the operating life of the camera. (author)

Conceptual design report of hot cell modification and process for fission Mo-99 production

International Nuclear Information System (INIS)

Park, Jin Ho; Choung, W. M.; Lee, K. I.; Hwang, D. S.; Kim, Y. K.; Park, K. B.; Jung, Y. J.; Kim, D. S.; Park, Y. C.

2001-05-01

In this conceptual design report, the basic data and design guides for detail design of fission Mo-99 production process and hot cell modification are included.The basic data and design guides for detail design of fission Mo-99 production process contains following contents. -design capacity, the basic process, process flow diagram, process material balance, process data. The basic data and design guides for modification of existing hot cell contains following contents. - plot plan of hot cell facility, the plan for shield reinforcement of hot cell, the plan for management and storage of high level liquid wastes, the plan of ventilation system, the plan for modification of auxiliary facilities. And also, the results of preliminary safety analysis(normal operation and accidents) and criticality analysis are included in this conceptual design report

Conceptual design report of hot cell modification and process for fission Mo-99 production

Energy Technology Data Exchange (ETDEWEB)

Park, Jin Ho; Choung, W. M.; Lee, K. I.; Hwang, D. S.; Kim, Y. K.; Park, K. B.; Jung, Y. J.; Kim, D. S.; Park, Y. C

2001-05-01

In this conceptual design report, the basic data and design guides for detail design of fission Mo-99 production process and hot cell modification are included.The basic data and design guides for detail design of fission Mo-99 production process contains following contents. -design capacity, the basic process, process flow diagram, process material balance, process data. The basic data and design guides for modification of existing hot cell contains following contents. - plot plan of hot cell facility, the plan for shield reinforcement of hot cell, the plan for management and storage of high level liquid wastes, the plan of ventilation system, the plan for modification of auxiliary facilities. And also, the results of preliminary safety analysis(normal operation and accidents) and criticality analysis are included in this conceptual design report.

A new approach for helium backfilling and leak testing seal-welded capsules in a hot cell

International Nuclear Information System (INIS)

Strasslsund, E.K.; Berger, D.N.

1992-05-01

Gamma irradiation sources containing radioactive 137 Cesium Chloride are being produced at the US Department of Energy's Hanford Site as part of a Westinghouse Hanford company/Pacific Northwest Laboratory cooperative program. New equipment was developed to leak test the double-encapsulated sources in a hot cell. The equipment, which includes a helium backfill chamber and end cap press , a vacuum chamber, and a helium mass spectrometer, has provided technicians with the capability to detect leaks in sealed sources as small as 1. 0x10 -7 atm cm 3 /S helium

D and D Toolbox Project - Technology Demonstration of Fixatives Applied to Hot Cell Facilities via Remote Sprayer Platforms

International Nuclear Information System (INIS)

Lagos, L.; Shoffner, P.; Espinosa, E.; Pena, G.; Kirk, P.; Conley, T.

2009-01-01

The objective of the US Department of Energy Office of Environmental Management's (DOE-EM's) D and D Toolbox Project is to use an integrated systems approach to develop a suite of decontamination and decommissioning (D and D) technologies, a D and D toolbox, that can be readily used across the DOE complex to improve safety, reduce technical risks, and limit uncertainty within D and D operations. Florida International University's Applied Research Center (FIU-ARC) is supporting this initiative by identifying technologies suitable to meet specific facility D and D requirements, assessing the readiness of those technologies for field deployment, and conducting technology demonstrations of selected technologies at FIU-ARC facilities in Miami, Florida. To meet the technology gap challenge for a technology to remotely apply strippable/fixative coatings, FIU-ARC identified and demonstrated of a remote fixative sprayer platform. During this process, FIU-ARC worked closely with the Oak Ridge National Laboratory in the selection of typical fixatives and in the design of a hot cell mockup facility for demonstrations at FIUARC. For this demonstration and for future demonstrations, FIU-ARC built a hot cell mockup facility at the FIU-ARC Technology Demonstration/Evaluation site in Miami, Florida. FIU-ARC selected the International Climbing Machines' (ICM's) Robotic Climber to perform this technology demonstration. The selected technology was demonstrated at the hot cell mockup facility at FIU-ARC during the week of November 10, 2008. Fixative products typically used inside hot cells were investigated and selected for this remote application. The fixatives tested included Sherwin Williams' Promar 200 and DTM paints and Bartlett's Polymeric Barrier System (PBS). The technology evaluation documented the ability of the remote system to spray fixative products on horizontal and vertical concrete surfaces. The technology performance, cost, and health and safety issues were evaluated

NDE of PWR fuel: Identifying candidates for hot cell examination

International Nuclear Information System (INIS)

Moon, J.E.; Bury, J.G.; Correal, O.A.; Kunishi, H.; Wilson, H.W.

1992-05-01

On-site examinations were performed at the Indian Point 3 and Callaway reactors to attempt to identify the leakage mechanism of several leaking fuel rods. The exams consisted of removing the leaking fuel rods from the assembly and performing a visual examination. These results, combined with other available on-site data on leaking fuel rods, were used to select fuel rods for shipment to a hot cell for detailed root cause examination. Three fuel rods from the Indian Point 3 reactor were found to be leaking due to debris-induced fretting. The examinations at Callaway were terminated prior to completion due to utility scheduler conflicts. Rods from the Callaway reactor were selected for shipment to the hot cell along with the rods from the Byron 1 and 2 and V.C. Summer reactors. The data presented in the report summarize the coolant activity history, the UT examination results, and a summary of the review of the fabrication records. The basis for the selection of the rods to be sent to the hot cells is also summarized

Integrated safeguards testing laboratories in support of the advanced fuel cycle initiative

International Nuclear Information System (INIS)

Santi, Peter A.; Demuth, Scott F.; Klasky, Kristen L.; Lee, Haeok; Miller, Michael C.; Sprinkle, James K.; Tobin, Stephen J.; Williams, Bradley

2009-01-01

A key enabler for advanced fuel cycle safeguards research and technology development for programs such as the Advanced Fuel Cycle Initiative (AFCI) is access to facilities and nuclear materials. This access is necessary in many cases in order to ensure that advanced safeguards techniques and technologies meet the measurement needs for which they were designed. One such crucial facility is a hot cell based laboratory which would allow developers from universities, national laboratories, and commercial companies to perform iterative research and development of advanced safeguards instrumentation under realistic operating conditions but not be subject to production schedule limitations. The need for such a facility arises from the requirement to accurately measure minor actinide and/or fission product bearing nuclear materials that cannot be adequately shielded in glove boxes. With the contraction of the DOE nuclear complex following the end of the cold war, many suitable facilities at DOE sites are increasingly costly to operate and are being evaluated for closure. A hot cell based laboratory that allowed developers to install and remove instrumentation from the hot cell would allow for both risk mitigation and performance optimization of the instrumentation prior to fielding equipment in facilities where maintenance and repair of the instrumentation is difficult or impossible. These benefits are accomplished by providing developers the opportunity to iterate between testing the performance of the instrumentation by measuring realistic types and amounts of nuclear material, and adjusting and refining the instrumentation based on the results of these measurements. In this paper, we review the requirements for such a facility using the Wing 9 hot cells in the Los Alamos National Laboratory's Chemistry and Metallurgy Research facility as a model for such a facility and describe recent use of these hot cells in support of AFCI.

Integrated safeguards testing laboratories in support of the advanced fuel cycle initiative

Energy Technology Data Exchange (ETDEWEB)

Santi, Peter A [Los Alamos National Laboratory; Demuth, Scott F [Los Alamos National Laboratory; Klasky, Kristen L [Los Alamos National Laboratory; Lee, Haeok [Los Alamos National Laboratory; Miller, Michael C [Los Alamos National Laboratory; Sprinkle, James K [Los Alamos National Laboratory; Tobin, Stephen J [Los Alamos National Laboratory; Williams, Bradley [DOE, NE

2009-01-01

A key enabler for advanced fuel cycle safeguards research and technology development for programs such as the Advanced Fuel Cycle Initiative (AFCI) is access to facilities and nuclear materials. This access is necessary in many cases in order to ensure that advanced safeguards techniques and technologies meet the measurement needs for which they were designed. One such crucial facility is a hot cell based laboratory which would allow developers from universities, national laboratories, and commercial companies to perform iterative research and development of advanced safeguards instrumentation under realistic operating conditions but not be subject to production schedule limitations. The need for such a facility arises from the requirement to accurately measure minor actinide and/or fission product bearing nuclear materials that cannot be adequately shielded in glove boxes. With the contraction of the DOE nuclear complex following the end of the cold war, many suitable facilities at DOE sites are increasingly costly to operate and are being evaluated for closure. A hot cell based laboratory that allowed developers to install and remove instrumentation from the hot cell would allow for both risk mitigation and performance optimization of the instrumentation prior to fielding equipment in facilities where maintenance and repair of the instrumentation is difficult or impossible. These benefits are accomplished by providing developers the opportunity to iterate between testing the performance of the instrumentation by measuring realistic types and amounts of nuclear material, and adjusting and refining the instrumentation based on the results of these measurements. In this paper, we review the requirements for such a facility using the Wing 9 hot cells in the Los Alamos National Laboratory's Chemistry and Metallurgy Research facility as a model for such a facility and describe recent use of these hot cells in support of AFCI.

Hot sample archiving. Revision 3

International Nuclear Information System (INIS)

McVey, C.B.

1995-01-01

This Engineering Study revision evaluated the alternatives to provide tank waste characterization analytical samples for a time period as recommended by the Tank Waste Remediation Systems Program. The recommendation of storing 40 ml segment samples for a period of approximately 18 months (6 months past the approval date of the Tank Characterization Report) and then composite the core segment material in 125 ml containers for a period of five years. The study considers storage at 222-S facility. It was determined that the critical storage problem was in the hot cell area. The 40 ml sample container has enough material for approximately 3 times the required amount for a complete laboratory re-analysis. The final result is that 222-S can meet the sample archive storage requirements. During the 100% capture rate the capacity is exceeded in the hot cell area, but quick, inexpensive options are available to meet the requirements

The DIDO-reactor at Harwell, U.K. and ancillary hot cell facilities. Information sheets

International Nuclear Information System (INIS)

Hardt, P. von der; Roettger, H.

1981-01-01

Technical information is given on the DIDO reactor and associated hot cell facilities, with the main emphasis on experimental irradiation facilities, specialized irradiation devices (loops and capsules) and possibilities for post-irradiation examinations of samples. The information is presented in the form of eight information sheets under the headings: main characteristics of the reactor; utilization and specialization of the reactor; experimental facilities; neutron spectra; main characteristics of specialized irradiation devices; main characteristics of hot cell facilities; equipment and techniques available for post-irradiation examinations; utilization and specialization of the hot cell facilities

Facilities for post-irradiation examination of experimental fuel elements at Chalk River Nuclear Laboratories

International Nuclear Information System (INIS)

Mizzan, E.; Chenier, R.J.

1979-10-01

Expansion of post-irradiation facilities at the Chalk River Nuclear Laboratories and steady improvement in hot-cell techniques and equipment are providing more support to Canada's reactor fuel development program. The hot-cell facility primarily used for examination of experimental fuels averages a quarterly throughput of 40 elements and 110 metallographic specimens. New developments in ultrasonic testing, metallographic sample preparation, active storage, active waste filtration, and fissile accountability are coming into use to increase the efficiency and safety of hot-cell operations. (author)

An improved out-cell to in-cell rapid transfer system at the HFEF-south

International Nuclear Information System (INIS)

Bacca, J.P.; Sherman, E.K.

1990-01-01

The Argonne National Laboratory (ANL) Hot Fuel Examination Facility-South (HFEF-S), located at the ANL-West site of the Idaho National Engineering Laboratory, is currently undergoing extensive refurbishment and modifications in preparation for its use, beginning in 1991, in demonstrating remote recycling of fast reactor, metal-alloy fuel as part of the US Department of Energy liquid-metal reactor, Integral Fast Reactor (IFR) program. Included in these improvements to HFEF-S is a new, small-item, rapid transfer system (RTS). When installed, this system will enable the rapid transfer of small items from the hot-cell exterior into the argon cell (argon-gas atmosphere) of the facility without necessitating the use of time-consuming and laborious procedures. The new RTS will also provide another important function associated with HFEF-S hot-cell operation in the IFR Fuel Recycle Program; namely, the rapid insertion of clean, radioactive contamination-measuring smear paper specimens into the hot cells for area surveys, and the expedited removal of these contaminated (including alpha as well as beta/gamma contamination) smears from the argon cell for transfer to an adjacent health physics field laboratory in the facility for nuclear contamination/radiation counting

Annual report on operation, utilization and technical development of research reactors and hot laboratory, from April 1, 1987 to March 31, 1988

International Nuclear Information System (INIS)

1988-10-01

Activities of the Department of Research Reactor Operation in fiscal year 1987 are described. The department is responsible for operation and maintenance of JRR-2, JRR-4, Research Reactor Development Division which performed upgraded JRR-3 and other R D, and Hot Laboratory. In the above connection various other work has also been performed, such as technical management of fuel and coolant, radiation control, irradiation technique, etc. In Hot Laboratory, we have performed post-irradiation examinations of fuels and materials, and also development of examination procedures, too. (author)

Annual report on operation, utilization and technical development of research reactors and hot laboratory, from April 1, 1985 to March 31, 1986

International Nuclear Information System (INIS)

1986-10-01

Activities of the Department of Research Reactor Operation in fiscal year 1985 are described. The department is responsible for operation and maintenance of JRR-2, JRR-4, Research Reactor Development Division which performed upgraded JRR-3 and other R and D, and Hot Laboratory. In the above connection various other work has also been performed, such as technical management of fuel and coolant, radiation control, irradiation technique, etc. In Hot Laboratory, we have performed post-irradiation examinations of fuels and materials, and also development of examination procedures, too. (author)

Criticality detector exclusion zone in a spent-fuel hot cell

International Nuclear Information System (INIS)

Kim, S.S.; Sterbentz, J.W.

1999-01-01

The main purpose of a criticality alarm system (CAS) is to protect personnel by detecting a criticality event (neutron radiation) and actuating an alarm system to initiate emergency response. Inadvertent criticality alarms from noncritical events, such as spurious voltage spikes or intense gamma radiation fields, can produce work cessation and time-consuming and costly event assessments and may result in harm to personnel during an evacuation. It therefore becomes a major concern to ensure that inadvertent or false criticality alarms do not occur or at least are minimized. Minimization of inadvertent criticality alarms due to intense gamma radiation emitted from spent-nuclear-fuel (SNF) elements as opposed to neutron radiation from an actual criticality event is the primary focus of this calculational and experimental study. The Irradiated Fuel Storage Facility (IFSF) located at the Idaho National Engineering and Environmental Laboratory is a government-owned, contractor-operated facility whose mission is to provide safe handling and dry storage for various types of SNFs. Although other fuel types (lower burnup) are stored in the IFSF, it is the high-burnup elements with the associated intense gamma radiation fields that have the potential to inadvertently set off the criticality alarms in the fuel-handling area adjacent to the storage vault. Typically, in the fuel-handling cave or hot cell of the IFSF, the cask lid is removed, and individual fuel elements are extracted from the cask and placed in special storage canisters. It is during the time period when fuel elements are extracted from their casks or when fully loaded canisters are moved in the hot cell that the CAS detectors are exposed to the intense gamma radiation fields from the spent fuel. The neutron detectors positioned in one of the manipulator ports are designed such that fast neutrons from a criticality event are thermalized by a polyethylene moderator, strike the scintillator detector material, and

PWR fuel monitoring: recent progress with hot cells' examination equipment

International Nuclear Information System (INIS)

Chenebault, P.

1989-01-01

The 'hot' laboratories set up by the French Atomic Energy Authority (CEA) in its nuclear research centers at Saclay and Grenoble, and by the French Electricity Board (EDF) on the Chinon nuclear power station site, are used for dismantling and examining fuel rod assemblies irradiated in PWRs. This article is limited to a description of a number of new or totally updated items of equipment in these laboratories. Nuclear industry companies are also participating in the development of new examination techniques. As an example, the use of wave-guides for remote transmission of signals in a radioactive environment is described. 2 figs

Laboratory of Cell and Molecular Biology

Data.gov (United States)

Federal Laboratory Consortium — The Laboratory of Cell and Molecular Biology investigates the organization, compartmentalization, and biochemistry of eukaryotic cells and the pathology associated...

GSPEL - Fuel Cell Laboratory

Data.gov (United States)

Federal Laboratory Consortium — The Fuel Cell Lab (FCL)Established to investigate, integrate, testand verifyperformance and technology readiness offuel cell systems and fuel reformers for use with...

Hot cell chemistry for isotope production at Los Alamos Meson Physics Facility

International Nuclear Information System (INIS)

Barnes, J.W.; Bentley, G.E.; Ott, M.A.; DeBusk, T.P.

1978-01-01

A family of standardized glass and plastic ware has been developed for the unit processes of dissolution, volume reduction, ion exchange, extraction, gasification, filtration, centrifugation, and liquid transfer in the hot cells. Computerized data handling and gamma pulse analysis have been applied to quality control and process development in hot cell procedures for production of isotopes for research in physics and medicine. The above has greatly reduced the time needed to set up for and produce a new isotope

The DR 3 reactor at Risoe, Denmark and its associated hot cell facilities. Information sheets

International Nuclear Information System (INIS)

Hardt, P. von der; Roettger, H.

1981-01-01

Technical information is given on the DR 2 reactor and associated hot cell facilities, with the main emphasis on experimental irradiation facilities, specialized irradiation devices (loops and capsules) and possibilities for post-irradiation examinations of samples. The information is presented in the form of seven information sheets under the headings: main characteristics of the reactor; utilization and specialization of the reactor; experimental facilities; main characteristics of specialized irradiation devices; main characteristics of hot cell facilities; equipment and techniques available for post-irradiation examinations; utilization and specialization of the hot cell facilities

Evaluation of modular robot system for maintenance tasks in hot cell

Energy Technology Data Exchange (ETDEWEB)

Pagala, Prithvi Sekhar, E-mail: ps.pagala@upm.es [Centre for Automation and Robotics UPM-CSIC (Spain); Ferre, Manuel, E-mail: m.ferre@upm.es [Centre for Automation and Robotics UPM-CSIC (Spain); Orona, Luis, E-mail: l.orona@gsi.de [GSI Helmholtzzentrum für Schwerionenforschung (Germany)

2014-10-15

Highlights: •Modular robot deployment inside hot cell for remote manipulation evaluated. •Flexible and adaptable system for variety of tasks presented. •Uses in large workspaces and evolving requirements shown. -- Abstract: This work assesses the use of a modular robot system to perform maintenance and inspection tasks such as, remote flexible inspection, manipulation and cooperation with deployed systems inside the hot cell. A flexible modular solution for the inclusion in maintenance operations is presented. The proposed heterogeneous modular robotic system is evaluated using simulations of the prototype across selected robot configuration to perform tasks. Results obtained show the advantages and ability of the modular robot to perform the necessary tasks as well as its ability to adapt and evolve depending on the need. The simulation test case inside hot cell shows modular robot configuration, a two modular arm to perform tele-operation tasks in the workspace and a wheeled platform for inspection collaborating to perform tasks. The advantage of using re-configurable modular robot over conventional robot platforms is shown.

Analytical modeling of the temporal evolution of hot spot temperatures in silicon solar cells

Science.gov (United States)

Wasmer, Sven; Rajsrima, Narong; Geisemeyer, Ino; Fertig, Fabian; Greulich, Johannes Michael; Rein, Stefan

2018-03-01

We present an approach to predict the equilibrium temperature of hot spots in crystalline silicon solar cells based on the analysis of their temporal evolution right after turning on a reverse bias. For this end, we derive an analytical expression for the time-dependent heat diffusion of a breakdown channel that is assumed to be cylindrical. We validate this by means of thermography imaging of hot spots right after turning on a reverse bias. The expression allows to be used to extract hot spot powers and radii from short-term measurements, targeting application in inline solar cell characterization. The extracted hot spot powers are validated at the hands of long-term dark lock-in thermography imaging. Using a look-up table of expected equilibrium temperatures determined by numerical and analytical simulations, we utilize the determined hot spot properties to predict the equilibrium temperatures of about 100 industrial aluminum back-surface field solar cells and achieve a high correlation coefficient of 0.86 and a mean absolute error of only 3.3 K.

Solid Oxide Fuel Cell Experimental Laboratory

Data.gov (United States)

Federal Laboratory Consortium — NETL’s Solid Oxide Fuel Cell Experimental Laboratory in Morgantown, WV, gives researchers access to models and simulations that predict how solid oxide fuel cells...

Fastener tightening in a radioactive (hot) cell

International Nuclear Information System (INIS)

Kalk, J.J.

1986-01-01

Accurate remote tightening of fasteners in a radioactive (Hot) cell can be a very exasperating experience. Viewing can be difficult (in many places) and work sometimes must be done using mirrors and/or cameras. If electro mechanical manipulators are used, the operator has no ''feel,'' which often can result in cross threading, or improper torquing of fasteners. At the Interim Examination and Maintenance (IEM) Cell, where reactor components from the Fast Flux Test Facility (FFTF) are disassembled, these problems are prevalent because three of the IEM Cell walls have no windows. Electric impact wrenches were first proposed and tested for the IEM Cell, but the combined effects of radiation, dry argon atmosphere and poor visibility radically altered the cell tool development philosophy. This change in philosophy is reflected in the development of several simple fastener tightening devices

Fastener tightening in a radioactive (hot) cell

International Nuclear Information System (INIS)

Kalk, J.J.

1987-01-01

Accurate remote tightening of fasteners in a radioactive (hot) cell can be a very exasperating experience. Viewing can be difficult (in many places) and work sometimes must be done using mirrors and/or cameras. If electro mechanical manipulators are used, the operator has no feel, which often can result in cross threading, or improper torquing of fasteners. At the Interim Examination and Maintenance (IEM) Cell, where reactor components from the Fast Flux Testing Facility (FFTF) are disassembled, these problems are prevalent because three of the IEM Cell walls have no windows. Electric impact wrenches were first proposed and tested for the IEM Cell, but the combined effects of radiation, dry argon atmosphere and poor visibility radically altered the cell tool development philosophy. This change in philosophy is reflected in the development of several simple fastener tightening devices

Enhancing Students' HOTS in Laboratory Educational Activity by Using Concept Map as an Alternative Assessment Tool

Science.gov (United States)

Ghani, I. B. A.; Ibrahim, N. H.; Yahaya, N. A.; Surif, J.

2017-01-01

Educational transformation in the 21st century demands in-depth knowledge and understanding in order to promote the development of higher-order thinking skills (HOTS). However, the most commonly reported problem with respect to developing a knowledge of chemistry is poor mastery of basic concepts. Chemistry laboratory educational activities are…

Determination of hot-spot susceptibility of multistring photovoltaic modules in a central-station application

Science.gov (United States)

Gonzalez, C. C.; Weaver, R. W.; Ross, R. G., Jr.; Spencer, R.; Arnett, J. C.

1984-01-01

Part of the effort of the Jet Propulsion Laboratory (JPL) Flat-Plate Solar Array Project (FSA) includes a program to improve module and array reliability. A collaborative activity with industry dealing with the problem of hot-spot heating due to the shadowing of photovoltaic cells in modules and arrays containing several paralleled cell strings is described. The use of multiparallel strings in large central-station arrays introduces the likelihood of unequal current sharing and increased heating levels. Test results that relate power dissipated, current imbalance, cross-strapping frequency, and shadow configuration to hot-spot heating levels are presented. Recommendations for circuit design configurations appropriate to central-station applications that reduce the risk of hot-spot problems are offered. Guidelines are provided for developing hot-spot tests for arrays when current imbalance is a threat.

The 'MELUSINE' reactor at Grenoble, France, and associated hot cell facilities. Information sheets

International Nuclear Information System (INIS)

Hardt, P. von der; Roettger, H.

1981-01-01

Technical information is given on the MELUSINE reactor and associated hot cell facilities, with the main emphasis on experimental irradiation facilities and specialized irradiation devices (loops and capsules). The information is presented in the form of six information sheets under the headings: main characteristics of the reactor; utilization and specialization of the reactor; experimental facilities; neutron spectra; main characteristics of specialized irradiation devices; main characteristics of hot cell facilities

Zirconium Recycle Test Equipment for Hot Cell Operations

International Nuclear Information System (INIS)

Collins, Emory D.; DelCul, Guillermo Daniel; Spencer, Barry B.; Bradley, Eric Craig; Brunson, Ronald Ray

2015-01-01

The equipment components and assembly support work were modified for optimized, remote hot cell operations to complete this milestone. The modifications include installation of a charging door, Swagelok connector for the off-gas line between the reactor and condenser, and slide valve installation to permit attachment/replacement of the product salt collector bottle.

The FR 2 reactor at Karlsruhe, F.R. Germany and associated hot cell facilities. Information sheets

International Nuclear Information System (INIS)

Hardt, P. von der; Roettger, H.

1981-01-01

Technical information is given on the FR 2 reactor and associated hot cell facilities, specialized irradiation devices (loops and capsules) and possibilities for post-irradiation examinations of samples. The information is presented in the form of eight information sheets under the headings: main characteristics of the reactor; utilization and specialization of the reactor; experimental facilities; neutron spectra; main characteristics of specialized irradiation devices; main characteristics of hot cell facilities; equipment and techniques available for post-irradiation examinations; utilization and specialization of the hot cell facilities

Experiences from Refurbishment of Metallography Hot Cells and Application of a New Preparation Concept for Materialography Samples

International Nuclear Information System (INIS)

Oberlander, B. C.; Espeland, M.; Solum, N. O.

2001-01-01

After more than 30 years of operation the lead shielded metallography hot cells needed a basic renewal and modernisation not least of the specimen preparation equipment. Preparation in hot cells of radioactive samples for metallography and ceramography is challenging and time consuming. It demands a special design and quality of all in-cell equipment and skill and patience from the operator. Essentials in the preparation process are: simplicity and reliability of the machines, and a good quality, reproducibility and efficiency in performance. Desirable is process automation, flexibility and an alara amounto of radioactive waste produced per sample prepared. State of the art preparation equipment for materialography seems to meet most of the demands, however, it cannot be used in hot cells without modifications. Therefore. IFE and Struers in Copenhagen modified a standard model of a Strues precision cutting machine and a microprocessor controlled grinding and polishing machine for Hot Cell application. Hot cell utilisation of the microcomputer controlled grinding and polishing machine and the existing automatic dosing equipment made the task of preparing radioactive samples more attractive. The new grinding and polishing system for hot cells provides good sample preparation quality and reproductibility at reduced preparation time and reduced amount of contaminated waste produced per sample prepared. the sample materials examined were irradiated cladding materials and fuels

Basic design and construction of a mobile hot cell for the conditioning of spent high activity radioactive sources

International Nuclear Information System (INIS)

An Hongxiang; Fan Zhiwen; Al-Mughrabi, M.

2011-01-01

The conditioning of spent high activity radioactive sources is one important step in sealed radioactive sources management strategies. Based on the practice on the designing of the immobilized hot cell, the handling of the sealed radioactive sources, and the reference of the mobile hot cell constructed in South Africa, SHARS conditioning process and the basic design of a mobile hot cell is developed. The mobile hot cell has been constructed and the tests including the cold test of the SRS conditioning, the hot cell assemble and disassemble and SRS recovery were done. The shielding capacity were tested by 3.8 x 10 13 Bq cobalt-60 sources and the dose rate of the equipment surface, below 2 m, is less than 0.016 mSv/h. It is proved that the designing requirement is meet and the function of the equipment is good. (authors)

Cooling Grapple System for FMEF hot cell

International Nuclear Information System (INIS)

Semmens, L.S.; Frandsen, G.B.; Tome, R.

1983-01-01

A Cooling Grapple System was designed and built to handle fuel assemblies within the FMEF hot cell. The variety of functions for which it is designed makes it unique from grapples presently in use. The Cooling Grapple can positively grip and transport assemblies vertically, retrieve assemblies from molten sodium where six inches of grapple tip is submerged, cool 7 kw assemblies in argon, and service an in-cell area of 372 m 2 (4000 ft 2 ). Novel and improved operating and maintenance features were incorporated in the design including a shear pin and mechanical catcher system to prevent overloading the grapple while allowing additional reaction time for crane shutdown

Enhancing the actinide sciences in Europe through hot laboratories networking and pooling: from ACTINET to TALISMAN

International Nuclear Information System (INIS)

Bourg, S.; Poinssot, C.

2013-01-01

Since 2004, Europe supports the strengthening of the European actinides sciences scientific community through the funding of dedicated networks: (i) from 2004 to 2008, the ACTINET6 network of excellence (6. Framework Programme) gathered major laboratories involved in nuclear research and a wide range of academic research organisations and universities with the specific aims of funding and implementing joint research projects to be performed within the network of pooled facilities; (ii) from 2009 to 2013, the ACTINET-I3 integrated infrastructure initiative (I3) supports the cost of access of any academics in the pooled EU hot laboratories. In this continuation, TALISMAN (Trans-national Access to Large Infrastructures for a Safe Management of Actinides) gathers now the main European hot laboratories in actinides sciences in order to promote their opening to academics and universities and strengthen the EU-skills in actinides sciences. Furthermore, a specific focus is set on the development of advanced cutting-edge experimental and spectroscopic capabilities, the combination of state-of-the art experimental with theoretical first-principle methods on a quantum mechanical level and to benefit from the synergy between the different scientific and technical communities. ACTINET-I3 and TALISMAN attach a great importance and promote the Education and Training of the young generation of actinides scientists in the Trans-national access but also by organizing Schools (general Summer Schools or Theoretical User Lab Schools) or by granting students to attend International Conference on actinide sciences. (authors)

Assembly of laboratory line for nuclear fuel reprocessing

International Nuclear Information System (INIS)

Fidler, J.; Chotivka, V.

1979-01-01

The dismantling of a laboratory line for spent fuel reprocessing after the termination of the research programme and the procedures for hot and semi-hot cell decontamination are described. The equipment was mostly disassembled in smaller parts which were then decontaminated by wiping them with cotton wool soaked in detergent and citric acid, varnished with two-component epoxi varnish, wrapped into multiple polyethylene foils, sealed in PVC bags and thus ready for transport. (B.S.)

Planning, Management and Organizational Aspects of the Decommissioning of a Hot Cell Facility

Energy Technology Data Exchange (ETDEWEB)

Strufe, N. [Danish Decommissioning, Roskilde (Denmark)

2013-08-15

This CRP project document ''Planning, Management and Organizational Aspects in Decommissioning of a Hot Cell Facility'' aims to describe the establishment of a management organization that ensures that the DD Hot Cell Project is properly and safely conducted and that staff members, who are seconded to the project, have a strong feeling of ownership and being an integral part of the project. The objectives of the decommissioning project of the hot cell facility is to decontaminate the facility and to remove items that cannot be decontaminated on site, in order for the entire hot cell building to become useable for other purposes without any radiological restrictions. The project requires proper communication and coordination with all stakeholders on-site, comprehensive work plans and strict control of the individual working areas and operations. A project of this type obviously requires a strong and well managed and coordinated project organization. DD has established a management system - KMS. The purposes of the KMS are twofold. The system aims to secure the fulfilment of the conditions and requirements of quality set by the nuclear authorities. The system also aims to provide the basis for a rational and economically feasible operation with a high level of safety. One of the main lessons learned in this project is clear that is to ensure that the necessary resources are available and the required expertise is allocated timely for the performance of the project(s) a strong coordination and great flexibility within the DD organization is required. This document describes the approach and considerations from the project management point of view. The document initially gives an introduction to the hot cell decommissioning project followed by issues of the general considerations and planning of the project within the DD, including aspects on organisation, quality assurance and coordination. (author)

Radiological design of hot laboratories

International Nuclear Information System (INIS)

Unruh, C.M.

1976-04-01

The fundamental design objectives for a laboratory where work with highly radioactive and highly toxic materials, such as plutonium and transplutonium nuclides, is performed are (1) to accomplish the purpose of the laboratory; (2) to protect the environment, (3) to provide safe working conditions; and (4) to keep radiation exposure to staff as low as practicable. The major planning and design features of a well engineered plutonium or transplutonium laboratory are given

Radiological design of hot laboratories

International Nuclear Information System (INIS)

Unruh, C.M.

1976-01-01

The fundamental design objectives for a laboratory where work with highly radioactive and highly toxic materials, such as plutonium and transplutonium nuclides, is performed, are (1) to accomplish the purpose of the laboratory, (2) to protect the environment, (3) to provide safe working conditions, and (4) to keep radiation exposure to staff as low as practicable. The major planning and design features of well-engineered plutonium or transplutonium laboratory are given. (author)

Hot-compress: A new postdeposition treatment for ZnO-based flexible dye-sensitized solar cells

Energy Technology Data Exchange (ETDEWEB)

Haque Choudhury, Mohammad Shamimul, E-mail: shamimul129@gmail.com [Department of Frontier Material, Nagoya Institute of Technology, Gokiso-cho, Showa-ku, Nagoya, Aichi 466-8555 (Japan); Department of Electrical and Electronic Engineering, International Islamic University Chittagong, b154/a, College Road, Chittagong 4203 (Bangladesh); Kishi, Naoki; Soga, Tetsuo [Department of Frontier Material, Nagoya Institute of Technology, Gokiso-cho, Showa-ku, Nagoya, Aichi 466-8555 (Japan)

2016-08-15

Highlights: • A new postdeposition treatment named hot-compress is introduced. • Hot-compression gives homogeneous compact layer ZnO photoanode. • I-V and EIS analysis data confirms the efficacy of this method. • Charge transport resistance was reduced by the application of hot-compression. - Abstract: This article introduces a new postdeposition treatment named hot-compress for flexible zinc oxide–base dye-sensitized solar cells. This postdeposition treatment includes the application of compression pressure at an elevated temperature. The optimum compression pressure of 130 Ma at an optimum compression temperature of 70 °C heating gives better photovoltaic performance compared to the conventional cells. The aptness of this method was confirmed by investigating scanning electron microscopy image, X-ray diffraction, current-voltage and electrochemical impedance spectroscopy analysis of the prepared cells. Proper heating during compression lowers the charge transport resistance, longer the electron lifetime of the device. As a result, the overall power conversion efficiency of the device was improved about 45% compared to the conventional room temperature compressed cell.

Investigation on field removed pipe sections in the PISC hot laboratories

International Nuclear Information System (INIS)

Cambini, M.; Crutzen, S.; Jehenson, P.; Bergh, R. Van den; Violin, F.

1990-01-01

Action No. 1 of PISC II: Real Contaminated Structures (RCS), seeks to collect results from specific investigations and limited round robin tests on real service induced defects in materials and structures of the primary circuit of Light Water Reactors. The hot cell facilities at JRC-Ispra are fully equipped for non destructive and destructive work on a collaborative basis. Cracked austenitic steel primary circuit pipes coming from the primary circuit of the Muhleberg reactor (Switzerland) have been inspected in order to demonstrate the validity of the facilities to examine these contaminated pieces. (author)

Strategic Planning for Hot Cell Closure

International Nuclear Information System (INIS)

LANGSTAFF, D.C.

2001-01-01

The United States Department of Energy (DOE) and its contractor were remediating a large hot cell complex to mitigate the radiological hazard. A Resource Conservation and Recovery Act (RCRA) closure unit was determined to be located within the complex. The regulator established a challenge to develop an acceptable closure plan on a short schedule (four months). The scope of the plan was to remove all excess equipment and mixed waste from the closure unit, establish the requirements of the legally binding Closure Plan and develop an acceptable schedule. The complex has several highly radioactive tanks, tank vaults, piping, and large hot cells containing complex chemical processing equipment. Driven by a strong need to develop an effective strategy to meet cleanup commitments, three principles were followed to develop an acceptable plan: (1) Use a team approach, (2) Establish a buffer zone to support closure, and (3) Use good practice when planning the work sequence. The team was composed of DOE, contractor, and Washington State Department of Ecology (Regulator) staff. The team approach utilized member expertise and fostered member involvement and communication. The buffer zone established an area between the unregulated parts of the building and the areas that were allegedly not in compliance with environmental standards. Introduction of the buffer zone provided simplicity, clarity, and flexibility into the process. Using good practice means using the DOE Integrated Safety Management Core Functions for planning and implementing work safely. Paying adequate attention to detail when the situation required contributed to the process credibility and a successful plan

Fuel Cell Development and Test Laboratory | Energy Systems Integration

Science.gov (United States)

Facility | NREL Fuel Cell Development and Test Laboratory Fuel Cell Development and Test Laboratory The Energy System Integration Facility's Fuel Cell Development and Test Laboratory supports fuel cell research and development projects through in-situ fuel cell testing. Photo of a researcher running

Testing capabilities of Los Alamos National Laboratory for irradiated materials

International Nuclear Information System (INIS)

Maloy, S.A.; James, M.R.; Sommer, W.F.

1999-01-01

Spallation neutron sources expose materials to high energy (>100 MeV) proton and neutron spectra. Although numerous studies have investigated the effects of radiation damage in a lower energy neutron flux from fission or fusion reactors on the mechanical properties of materials, very little work has been performed on the effects that exposure to a spallation neutron spectrum has on the mechanical properties of materials. These effects can be significantly different than those observed in a fission or fusion reactor spectrum because exposure to high energy protons and neutrons produces more He and H along with the atomic displacement damage. Los Alamos National Laboratory has unique facilities to study the effects of spallation radiation damage on the mechanical properties of materials. The Los Alamos Neutron Science Center (LANSCE) has a pulsed linear accelerator which operates at 800 MeV and 1 mA. The Los Alamos Spallation Radiation Effect Facility (LASREF) located at the end of this accelerator is designed to allow the irradiation of components in a proton beam while water cooling these components and measuring their temperature. After irradiation, specimens can be investigated at hot cells located at the Chemical Metallurgy Research Building. Wing 9 of this facility contains 16 hot cells set up in two groups of eight, each having a corridor in the center to allow easy transfer of radioactive shipments into and out of the hot cells. These corridors have been used to prepare specimens for shipment to collaborating laboratories such as PNNL, ORNL, BNL, and the Paul Scherrer Institute to perform specialized testing at their hot cells. The LANL hot cells contain capabilities for opening radioactive components and testing their mechanical properties as well as preparing specimens from irradiated components

The FRJ 1 reactor (MERLIN) at Juelich, F.R. Germany and associated hot cell facilities. Information sheets

International Nuclear Information System (INIS)

Hardt, P. von der; Roettger, H.

1981-01-01

Technical information is given on the FRJ 1 reactor and associated hot cell facilities, with the main emphasis on experimental irradiation facilities, specialized irradiation devices (loops and capsules) and possibilities for post-irradiation examinations of samples. The information is presented in the form of eight information sheets under the headings: main characteristics of the reactor; utilization and specialization of the reactor; experimental facilities; neutron spectra; main characteristics of specialized irradiation devices; main characteristics of hot cell facilities; equipment and techniques available for post-irradiation examinations; utilization and specialization of the hot cell facilities

Apparatus of hot cell for iodine-123 production

International Nuclear Information System (INIS)

Almeida, G.L. de; Rautenberg, F.A.; Souza, A.S.F. de.

1986-01-01

The hot cell installation at IEN cyclotron (Brazilian-CNEN) for sup(123)I production is presented. Several devices, such as, tube furnace coupling system, tube furnace driving system, sup(123)I target transfer system, product extraction system, furnace control system, and effluent systems, were constructed and modified for implanting process engineering. The requirements of safety engineering for operation process were based on ALARA concept. (M.C.K.)

Quantitative experimental assessment of hot carrier-enhanced solar cells at room temperature

Science.gov (United States)

Nguyen, Dac-Trung; Lombez, Laurent; Gibelli, François; Boyer-Richard, Soline; Le Corre, Alain; Durand, Olivier; Guillemoles, Jean-François

2018-03-01

In common photovoltaic devices, the part of the incident energy above the absorption threshold quickly ends up as heat, which limits their maximum achievable efficiency to far below the thermodynamic limit for solar energy conversion. Conversely, the conversion of the excess kinetic energy of the photogenerated carriers into additional free energy would be sufficient to approach the thermodynamic limit. This is the principle of hot carrier devices. Unfortunately, such device operation in conditions relevant for utilization has never been evidenced. Here, we show that the quantitative thermodynamic study of the hot carrier population, with luminance measurements, allows us to discuss the hot carrier contribution to the solar cell performance. We demonstrate that the voltage and current can be enhanced in a semiconductor heterostructure due to the presence of the hot carrier population in a single InGaAsP quantum well at room temperature. These experimental results substantiate the potential of increasing photovoltaic performances in the hot carrier regime.

Investigation on field removed pipe sections in the PISC hot laboratories

International Nuclear Information System (INIS)

Cambini, M.; Crutzen, S.; Jehenson, P.

1990-01-01

Action no. 1 of PISC III (Programme for the Inspection of Steel Components): Real Contaminated Structures (RCS), seeks to collect results from specific investigations and limited round robin tests on real service induced defects in materials and structures of the primary circuit of Light Water Reactors. The hot cell facilities at JRC-Ispra are fully equipped for non destructive and destructive work on a collaborative basis. Cracked austenitic steel pipes coming from the primary circuit of the Muehleberg reactor (Switzerland) have been inspected in order to demonstrate the validity of the facilities for the examination of these contaminated pieces

Current status and future plan of JMTR Hot Laboratory

International Nuclear Information System (INIS)

Hoshiya, Taiji; Usui, Takashi; Saito, Jun-ichi; Shimizu, Michio; Nakakura, Yuichi; Mimura, Hideaki; Nakagawa, Tetsuya; Ooka, Norikazu

1999-01-01

The newly developed techniques by the Hot Laboratory (JMTR HL) have provided for us the key information on behavior of specimens due to mechanical / physical / chemical / synergistic effects of radiation, stress and water for fission and fusion reactor environment. These techniques are focused on several topics as follows; (1) miniaturized specimen test for the development of fusion reactor materials, (2) slow strain rate tensile testing (SSRT) and crack propagation measuring tests for the study of Irradiation Assisted Stress Corrosion Cracking (IASCC) of core internals of LWR, (3) handling technique on specimens including tritium for the research and development of tritium breeders and neutron multiplier as fusion blanket materials, (4) joining method using the Tungsten Inert Gas (TIG) welding technique for re-assembling of capsule and re-fabrication of specimen and (5) nondestructive evaluation using ultrasonic wave and infrared thermography for the quantitative evaluation of irradiation brittleness of key components of fission and/or fusion reactor. The mutual exchange of PIE information, interchange of researchers and mutual utilization on PIE facilities are indispensable to raise PIE potentials and to get the break-through in the study of nuclear power. (author)

Dose control programme of Hot Cell facility at Isotope Wing

International Nuclear Information System (INIS)

Sapkal, Jyotsna A.; Suresh, Manju; Shreenivas, V.; Amruta, C.T.; Yadav, R.K.B.; Gopalkrishanan, R.K.; Patil, B.N.; Sastry, K.V.S.

2015-01-01

Hot Cell Facility of Board of Radiation Isotope Technology (BRIT) at Radiological Laboratories (RLG) is involved in fabrication of sealed radioisotopes like Cobalt-60, Cesium-137 and Iridium-192 radioisotopes which are widely used for various medical and industrial applications. In the field of Medicine, above radioactive sources are used for treatment procedures such as Teletherapy and Brachytherapy. 192 Ir radioisotope is widely used for industrial radiography particularly for non-destructive testing of welds in steel in the oil and gas industries. In spite of the increased production of these radioisotopes to meet the requirements from medical and industrial sector, the annual Collective Dose for BRIT facility, during 2011-2013 has shown a downward trend. This paper describes in brief the measures adopted by the facility based on the radiological safety inputs provided by Radiation Hazards Control (RHC) Unit of Isotope Wing, RLG for reducing the collective dose during year 2012 and 2013 by nearly 40% of collective dose consumed for year-2011. Strict implementation of the radiological safety measures during handling of radioactive sources, administrative controls and engineered safety measures resulted in lowering of collective dose during year 2011-2013. (author)

Design and rescue scenario of common repair equipment for in-vessel components in ITER hot cell

International Nuclear Information System (INIS)

Kakudate, Satoshi; Takeda, Nobukazu; Nakahira, Masataka; Shibanuma, Kiyoshi

2006-06-01

Transportation of the in-vessel components to be repaired in the ITER hot cell is carried by two kinds of transporters, i.e., overhead cranes and floor vehicles. The access area for repair operations in the hot cell is duplicated by these transporters. Clear sharing of the respective roles of these transporters with the minimum duplication is therefore useful for rationalization. The overhead cranes, which are independently installed in the respective cells in the hot sell, cannot pass through the components to be repaired between cells, i.e., receiving cell and refurbishment cell as an example. If the floor vehicle with simple mechanisms can cover the inaccessible area for the overhead cranes, a global transporter system in the hot cell will be simplified and the reliability will be increased. Based on this strategy, the overhead crane and floor vehicle concepts are newly proposed. The overhead crane has an adapter for change of the end-effectors, which can be easily changed, to grasp many kinds of components to be repaired. The floor vehicle, which is equipped with wheel mechanisms for transportation, is just to pass through the components between cells with only straight (linear) motion on the floor. The simple wheel mechanism can solve the spread of the dust, which is the critical issue of the original air bearing mechanism for traveling in the 2001 FDR design. Rescue scenarios and procedures in the hot cell are also studied in this report. The proposed rescue crane has major two functions for rescue operations of the hot cell facility, i.e., one for the overhead crane and the other for refurbishment equipment such as workstation for divertor repair. The rescue of the faulty overhead crane is carried out using the rescue tool installed on the rescue crane or directly traveled by pushing/pulling by the rescue crane after docking on the faulty overhead crane. For the rescue of the workstation, the rescue crane consists of a telescopic manipulator (maximum length

Hot cell facilities for post irradiation examination

International Nuclear Information System (INIS)

Mishra, Prerna; Bhandekar, Anil; Pandit, K.M.; Dhotre, M.P.; Rath, B.N.; Nagaraju, P.; Dubey, J.S.; Mallik, G.K.; Singh, J.L.

2017-01-01

Reliable performance of nuclear fuels and critical core components has a large bearing on the economics of nuclear power and radiation safety of plant operating personnel. In view of this, Post Irradiation Examination (PIE) is periodically carried out on fuels and components to generate feedback information which is used by the designers, fabricators and the reactor operators to bring about changes for improved performance of the fuel and components. Examination of the fuel bundles has to be carried out inside hot cells due to their high radioactivity

Development of one body α-γ type manipulator for hot cell facility

International Nuclear Information System (INIS)

Jung, S. K.; Lee, S. B.; Lee, E. P.

2004-01-01

To handle the high level radioactive materials in a sealed type hot cell, our company has developed the one body alpha-gamma type manipulator and this is an improved model compared with the previously developed beta-gamma and separated alpha-gamma type manipulators. The successful development of one body alpha-gamma type manipulator means our company has a whole capacity to design and fabricate all kinds of manipulators using in hot cells. Until now most of the manipulators in Korea were imported from other countries. The development of Korean manipulators gives us the easier maintenance and lower price compared to the foreign products. It is also possible to export the Korean manipulators to overseas

Conceptual design of the hot cell facility universal docking station at ITER

International Nuclear Information System (INIS)

Dammann, A.; Benchikhoune, M.; Friconneau, J.P.; Ivanov, V.; Lemee, A.; Martins, J.P.; Tamassy, G.

2011-01-01

Between main shutdowns of the ITER machine, in-vessel components and Iter Remote Maintenance System (IRMS) are transferred between the Tokamak complex and the Hot Cell Facility using different types of sealed casks. Transfer Casks have different physical interfaces with the Vacuum Vessel, which need to be the same at the docking stations of the HCF. It means that in-vessel components and IRMS are cleaned in the same cells, which is in fact not convenient. Furthermore, logistic studies showed that the use rate of the cells is very inhomogeneous. In order to have dedicated cell for decontamination of Remote Handling tools, in order to increase the operability efficiency and to removes the hot cell docking operation from the critical path, the concept of a universal docking station has been investigated. Based on an existing design, the work was focused on a review of requirements, the re-design and the integration within the HCF layout. The universal docking station has been proposed and is now integrated in HCF design.

Conceptual design of the hot cell facility universal docking station at ITER

Energy Technology Data Exchange (ETDEWEB)

Dammann, A., E-mail: alexis.dammann@iter.org [ITER Organization, CS 90 046, 13067 St Paul Lez Durance Cedex (France); Benchikhoune, M.; Friconneau, J.P.; Ivanov, V. [ITER Organization, CS 90 046, 13067 St Paul Lez Durance Cedex (France); Lemee, A. [SOGETI High Tech, 180 Rue Rene Descartes, 13851 Aix en Provence (France); Martins, J.P. [ITER Organization, CS 90 046, 13067 St Paul Lez Durance Cedex (France); Tamassy, G. [SOGETI High Tech, 180 Rue Rene Descartes, 13851 Aix en Provence (France)

2011-10-15

Between main shutdowns of the ITER machine, in-vessel components and Iter Remote Maintenance System (IRMS) are transferred between the Tokamak complex and the Hot Cell Facility using different types of sealed casks. Transfer Casks have different physical interfaces with the Vacuum Vessel, which need to be the same at the docking stations of the HCF. It means that in-vessel components and IRMS are cleaned in the same cells, which is in fact not convenient. Furthermore, logistic studies showed that the use rate of the cells is very inhomogeneous. In order to have dedicated cell for decontamination of Remote Handling tools, in order to increase the operability efficiency and to removes the hot cell docking operation from the critical path, the concept of a universal docking station has been investigated. Based on an existing design, the work was focused on a review of requirements, the re-design and the integration within the HCF layout. The universal docking station has been proposed and is now integrated in HCF design.

Hot cell renovation in the spent fuel conditioning process facility at the Korea Atomic Energy Research Institute

Directory of Open Access Journals (Sweden)

Seung Nam Yu

2015-10-01

Results and conclusion: Based on the considered refurbishment workflow, previous equipment in the M8 cell, including vessels and pipes, were removed and disposed of successfully after a zoning smear survey and decontamination, and new equipment with advanced functions and specifications were installed in the hot cell. Finally, the operating area and isolation room were also refurbished to meet the requirements of the improved hot cell facility.

Standard guide for hot cell specialized support equipment and tools

CERN Document Server

American Society for Testing and Materials. Philadelphia

2010-01-01

1.1 Intent: 1.1.1 This guide presents practices and guidelines for the design and implementation of equipment and tools to assist assembly, disassembly, alignment, fastening, maintenance, or general handling of equipment in a hot cell. Operating in a remote hot cell environment significantly increases the difficulty and time required to perform a task compared to completing a similar task directly by hand. Successful specialized support equipment and tools minimize the required effort, reduce risks, and increase operating efficiencies. 1.2 Applicability: 1.2.1 This guide may apply to the design of specialized support equipment and tools anywhere it is remotely operated, maintained, and viewed through shielding windows or by other remote viewing systems. 1.2.2 Consideration should be given to the need for specialized support equipment and tools early in the design process. 1.2.3 The values stated in inch-pound units are to be regarded as standard. The values given in parentheses are mathematical conv...

Particle-in-cell studies of laser-driven hot spots and a statistical model for mesoscopic properties of Raman backscatter

International Nuclear Information System (INIS)

Albright, B.J.; Yin, L.; Bowers, K.J.; Kline, J.L.; Montgomery, D.S.; Fernandez, J.C.; Daughton, W.

2006-01-01

The authors use explicit particle-in-cell simulations to model stimulated scattering processes in media with both solitary and multiple laser hot spots. These simulations indicate coupling among hot spots, whereby scattered light, plasma waves, and hot electrons generated in one laser hot spot may propagate to neighboring hot spots, which can be destabilized to enhanced backscatter. A nonlinear statistical model of a stochastic beam exhibiting this coupled behavior is described here. Calibration of the model using particle-in-cell simulations is performed, and a threshold is derived for 'detonation' of the beam to high reflectivity. (authors)

Hot cell renovation in the spent fuel conditioning process facility at the Korea Atomic Energy Research Institute

Energy Technology Data Exchange (ETDEWEB)

Yu, Seung Nam; Lee, Jong Kwang; Park, Byung Suk; Cho, Il Je; Kim, Ki Ho [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2015-10-15

The advanced spent fuel conditioning process facility (ACPF) of the irradiated materials examination facility (IMEF) at the Korea Atomic Energy Research Institute (KAERI) has been renovated to implement a lab scale electrolytic reduction process for pyroprocessing. The interior and exterior structures of the ACPF hot cell have been modified under the current renovation project for the experimentation of the electrolytic reduction process using spent nuclear fuel. The most important aspect of this renovation was the installation of the argon compartment within the hot cell. For the design and system implementation of the argon compartment system, a full-scale mock-up test and a three-dimensional (3D) simulation test were conducted in advance. The remodeling and repairing of the process cell (M8a), the maintenance cell (M8b), the isolation room, and their utilities were also planned through this simulation to accommodate the designed argon compartment system. Based on the considered refurbishment workflow, previous equipment in the M8 cell, including vessels and pipes, were removed and disposed of successfully after a zoning smear survey and decontamination, and new equipment with advanced functions and specifications were installed in the hot cell. Finally, the operating area and isolation room were also refurbished to meet the requirements of the improved hot cell facility.

Nuclear Materials Characterization in the Materials and Fuels Complex Analytical Hot Cells

International Nuclear Information System (INIS)

Rodriquez, Michael

2009-01-01

As energy prices skyrocket and interest in alternative, clean energy sources builds, interest in nuclear energy has increased. This increased interest in nuclear energy has been termed the 'Nuclear Renaissance'. The performance of nuclear fuels, fuels and reactor materials and waste products are becoming a more important issue as the potential for designing new nuclear reactors is more immediate. The Idaho National Laboratory (INL) Materials and Fuels Complex (MFC) Analytical Laboratory Hot Cells (ALHC) are rising to the challenge of characterizing new reactor materials, byproducts and performance. The ALHC is a facility located near Idaho Falls, Idaho at the INL Site. It was built in 1958 as part of the former Argonne National Laboratory West Complex to support the operation of the second Experimental Breeder Reactor (EBR-II). It is part of a larger analytical laboratory structure that includes wet chemistry, instrumentation and radiochemistry laboratories. The purpose of the ALHC is to perform analytical chemistry work on highly radioactive materials. The primary work in the ALHC has traditionally been dissolution of nuclear materials so that less radioactive subsamples (aliquots) could be transferred to other sections of the laboratory for analysis. Over the last 50 years though, the capabilities within the ALHC have also become independent of other laboratory sections in a number of ways. While dissolution, digestion and subdividing samples are still a vitally important role, the ALHC has stand alone capabilities in the area of immersion density, gamma scanning and combustion gas analysis. Recent use of the ALHC for immersion density shows that extremely fine and delicate operations can be performed with the master-slave manipulators by qualified operators. Twenty milligram samples were tested for immersion density to determine the expansion of uranium dioxide after irradiation in a nuclear reactor. The data collected confirmed modeling analysis with very tight

Some steps of the dismantling of the hot cell ATTILA

International Nuclear Information System (INIS)

Terrasson, L.

1989-01-01

This paper describes the dismantling, during 2 years and just finished now, of a large hot cell (11.6 m x 5.90 m x 5.80 m) at Fontenay-aux-Roses (France) characterised by an importand irradiation and contamination mean dose rate 7 rads/hr, in some places 20 rads/hr, coming at 98 % from Cesium 137 (beta decay radioisotope). Put into operation in March 1967, the Attila cell was used for spent fuel processing using halogenides [fr

The development of a mobile hot cell facility for the conditioning of spent high activity radioactive sources (SHARS)

International Nuclear Information System (INIS)

Liebenberg, G.R.; Al-Mughrabi, M.

2008-01-01

The International Atomic Energy Agency (IAEA) Waste Technology Section with additional support from the U.S. National Nuclear Security Agency (NNSA) through the IAEA Nuclear Security Fund has funded the design, fabrication, evaluation, and testing of a portable hot cell intended to address the problem of disused SHARS in obsolete irradiation devices such as teletherapy heads and dry irradiators. The project is initially targeting the African continent but expected soon to expand to Latin America and Asia. This hot cell would allow source removal, characterization, consolidation, repackaging in modern storage shields, and secure storage of high risk SHARS at single sites in each IAEA Member State. The mobile hot cell and related equipment is transported in two shipping containers to a specific country where the following process takes place: 1-) Assembly of hot cell; 2-) Removal of SHARS from working shields, encapsulation into a stainless steel capsule and placement into a long term storage shield; 3-) Conditioning of any other spent sources the country may require; 4-) Dismantling of the hot cell; 5-) Shipping equipment out of country. The operation in a specific country is planned to be executed over a three week period. This presentation will discuss the development of the mobile hot cell facility as well as the demonstration of the state of readiness of the system for manipulation of SHARS and the planned execution of the conditioning operations. As a result of this project, excess SHARS could be managed safely and securely and possibly be more easily repatriated to their country of origin for appropriate final disposition. (author)

Hot demonstration of proposed commercial nuclide removal technology

International Nuclear Information System (INIS)

Lee, D.

1996-01-01

This task covers the development and operation of an experimental test unit located in a Building 4501 hot cell within Building 4501 at Oak Ridge National Laboratory (ORNL). This equipment is designed to test radionuclides removal technologies under continuous operatoin on actual ORNL Melton Valley Storage Tank (MVST) supernatant, Savannah River high-level waste supernatant, and Hanford supernatant. The latter two may be simulated by adding the appropriate chemicals and/or nuclides to the MVST supernatant

Device for inserting and removing electric plug in socket- using remote handling apparatus inside radioactive hot cell

International Nuclear Information System (INIS)

Chevallereau, R.; Galmard, Y.

1994-01-01

A device for pushing an electric plug into a supply socket inside a radioactive hot cell and for withdrawing the plug after use of the appliance attached to it, comprises a pair of pivotally mounted arms. It can be used inside radioactive hot cells, to insert and put in and put off electric plugs

Ballooning test equipment for use in hot cells

International Nuclear Information System (INIS)

Broendsted, P.; Adrian, F.

1979-12-01

An equipment for testing the LOCA behaviour of irradiated cladding materials is described. The details of the construction and of the installation in the Hot Cells are reported. Pilot tests carried out showed that the performance of the system fulfills the basic experimental prerequisites, which were: heating rate of 2-3degC/s, final temperature 1150degC/s, internal pressure max. 30 atm, external pressure max. 1 atm, test atmosphere either air or steam. (author)

324 and 325 Building Hot Cell Cleanout Program: Air lock cover block refurbishment

International Nuclear Information System (INIS)

Katayama, Y.B.; Holton, L.K. Jr.; Gale, R.M.

1989-05-01

The high-density concrete cover blocks shielding the pipe trench in the hot-cell air lock of the 324 Building Radiochemical Engineering Cells had accumulated fixed radioactivity ranging from 1100 to 22, 000 mrad/hr. A corresponding increase in the radiation exposure to personnel entering the air lock, together with ALARA concerns, led to the removal of the contaminated concrete surface with a hydraulic spaller and the emplacement of a stainless steel covering over a layer of grout. The resultant saving in radiation exposure is estimated to be 7200 mrad for personnel completing burial box runs for the 324 and 325 Building Hot Cell Cleanout Program. Radiation exposure to all staff members entering the air lock is now at least 50% lower. 3 refs., 22 figs., 1 tab

Exposure management in a hot-cell decontamination and refurbishment campaign

International Nuclear Information System (INIS)

Courtney, J.C.; Ferguson, K.R.; Chesnovar, D.L.; Huebner, M.F.

1984-01-01

We developed a minicomputer-based system to provide rapid access to personnel dosimetry data during a campaign to decontaminate and refurbish a hot-cell at the Hot Fuel Examination Facility (HFEF) Complex. This system allows project management to estimate doses for future tasks, assess the effectiveness of decontamination and personnel protection techniques, and balance exposures among members of various skill groups. As the campaign progresses, projected total exposures can be minimized by tradeoffs between estimated doses during decontamination and estimated dose savings during the refurbishment phase. The effectiveness of various dose-reduction procedures can be compared on the basis of data from a few cell entries before more extensive routine operations are scheduled. Because the radiation fields vary significantly with location in the cell, we find that measurements of whole-body, skin, and extremity doses are more valuable than dose-rate information. Penetrating and skin radiation doses to personnel can be compared to administrative guidelines. This helps us to select the most effective combination of protective clothing. For example, leaded gauntlets reduce the dose rate to the workers' hands, but their use can increase the time required for some in-cell tasks. Hence, use of gauntlets can lead to higher whole-body and skin doses. The program is written for the HFEF Complex Harris/6 minimainframe computer with a disk-monitor operating system

324 and 325 Building hot cell cleanout program: Decontamination of C-Cell

International Nuclear Information System (INIS)

Katayama, Y.B.; Holton, L.K. Jr.

1989-10-01

During FY 1989 the decontamination of C-Cell of Hanford's 324 Building was completed as part of the 324 and 325 Building Hot Cell Cleanout Program sponsored by the DOE Nuclear Energy's Surplus Facilities Management Program. The decontamination effort was completed using a series of remote and contact decontamination techniques. Initial radiation readings in C-Cell averaged 50 rad/hr and were reduced remotely to less than 200 mrad/hr using an alkaline foam cleaner followed by a 5000-psi water flush. Contact decontamination was then permissible using ultra high-pressure water, at 36,000 psi, further reducing the average radiation level in the cell to less than 86 mrem/hr. The approach used in decontaminating C-Cell resulted in a savings in radiation exposure of 87% and a cost savings of 39% compared to a hands-on procedure used in A-Cell, 324 Building in 1987. The radiation dose and the costs to achieve a 244-fold reduction in radiation contamination were 1.65 mrem per ft 2 and $96 per ft 2 of cell surface area. 14 figs., 4 tabs

Evaluation of Tritium Behavior in the Epoxy Painted Concrete Wall of ITER Hot Cell

International Nuclear Information System (INIS)

Nakamura, Hirofumi; Hayashi, Takumi; Kobayashi, Kazuhiro; Nishi, Masataka

2005-01-01

Tritium behavior released in the ITER hot cell has been investigated numerically using a combined analytical methods of a tritium transport analysis in the multi-layer wall (concrete and epoxy paint) with the one dimensional diffusion model and a tritium concentration analysis in the hot cell with the complete mixing model by the ventilation. As the results, it is revealed that tritium concentration decay and permeation issues are not serious problem in a viewpoint of safety, since it is expected that tritium concentration in the hot cell decrease rapidly within several days just after removing the tritium release source, and tritium permeation through the epoxy painted concrete wall will be negligible as long as the averaged realistic diffusion coefficient is ensured in the concrete wall. It is also revealed that the epoxy paint on the concrete wall prevents the tritium inventory increase in the concrete wall greatly (two orders of magnitudes), but still, the inventory in the wall is estimated to reach about 0.1 PBq for 20 years operation

Ionospheric hot spot at high latitudes

International Nuclear Information System (INIS)

Schunk, R.W.; Sojka, J.J.

1982-01-01

A hot spot (or spots) can occur in the high-latitude ionosphere depending on the plasma convection pattern. The hot spot corresponds to a small magnetic local time-magnetic latitude region of elevated ion temperatures located near the dusk and/or dawn meridians. For asymmetric convection electric field patterns, with enhanced flow in either the dusk or dawn sector of the polar cap, a single hot spot should occur in association with the strong convection cell. However, on geomagnetically disturbed days, two strong convection cells can occur, and hence, two hot spots should exist. The hot spot should be detectable when the electric field in the strong convection cell exceeds about 40 mV m -1 . For electric fields of the order of 100 mV m -1 in the convection cell, the ion temperature in the hot spot is greatest at low altitudes, reaching 4000 0 K at 160 km, and decreases with altitude in the F-region. An ionospheric hot spot (or spots) can be expected at all seasons and for a wide range of solar cycle conditions

DQO Summary Report for 324 and 327 Building Hot Cells D4 Project Waste Characterization

Energy Technology Data Exchange (ETDEWEB)

T.A. Lee

2006-02-06

This data quality objective (DQO) summary report provides the results of the DQO process conducted for waste characterization activities for the 324 and 327 Building hot cells decommission, deactivate, decontaminate, and demolish activities. This DQO summary report addresses the systems and processes related to the hot cells, air locks, vaults, tanks, piping, basins, air plenums, air ducts, filters, an adjacent elements that have high dose rates, high contamination levels, and/or suspect transuranic waste, which will require nonstandard D4 techniques.

Transformation of a beta gamma hot-cell under air in a tight hot-cell under inert gas

International Nuclear Information System (INIS)

Lambert, G.

1981-05-01

For several years now, fuel elements from graphite gas reactors have been stored in pools at the Cadarache Center after having been subjected (in general) to laboratory examinations. The CEA has adopted the following re-transfer procedure for these fuel elements while awaiting reprocessing: the fuel elements are extracted from their existing cartridges and transferred into new welded stainless steel containers capable of assuring long term storage. The storage, however, envisaged is temporary and is realized in the Pegase pool, specially adapted for this purpose. This re-transfer operation is envisaged for some 2.300 containers. All the appropriate safety measures will be taken. The various different fuel materials handled are often highly irradiated. The presence of water in certain containers due to loss of leaktightness has led to a series of chemical reactions (corrosion of uranium by water, reactions with magnesium, formation of hydrides). As a result, existing envelopes can contain UO 2 , UH 3 and hydrogen; operations must therefore being carried out in an inert atmosphere (preferably argon). The re-transfer process can not therefore be carried out in a conventional cell. It is therefore envisaged to carry out this work in a leaktight cell in an inert atmosphere. A laboratory cell could be modified to perform these functions. This cell would be reconverted to its original state when operations terminate (in about 3 years time) [fr

Handbook of materials testing reactors and ancillary hot laboratories in the European Community

International Nuclear Information System (INIS)

1977-01-01

The purpose of this Handbook is to make available to those interested in 'in-pile' irradiation experiments important data on Materials Testing Reactors in operation in the European Community. Only thermal reactors having a power output of more than 5 MW(th) are taken into consideration. In particular, detailed technical information is given on the experimental irradiation facilities of the reactors, their specialized irradiation devices (loops and instrumented capsules), and the associated hot cell facilities for post-irradiation examination of samples

Analysis of the hot cell lay-out for the advanced spent fuel conditioning process

Energy Technology Data Exchange (ETDEWEB)

Lee, J. Y.; Kim, S. H.; Song, T. G.; Hong, D. H.; Kim, Y. H.; Yoon, J. S

2003-04-01

Equipment used for ACP must operate in intense radiation fields enclosed in a hot cell and be remotely maintained. For the reliable remote maintenance operation, several design aspects should be considered. Even though the design results seem to be satisfactory, all the remote operation should be checked prior to the hot demonstration. The best way to check the remote operability is a real mock-up test, but the mock-up test is too expensive and time consuming, and need refabrication of the design to deal with the problem found in the test operation. The 3D graphic simulator gives an alternate solution for this. It can check the remote operability of the process without fabrication of the process equipment. In other words, using a graphic simulator, remote operation task can be simulated in a computer(virtual environment), not the real environment. In this report, for the analysis on the hat cell layout for the ACP process, the verification from the concept of the process to the detailed motion of the equipment and the remote operation devices using virtual prototyping is described. Also, the requirement of the process equipment in the sense of size and remote maintenance, and that of the transportation and handling for the process material are described. Finally, from these results, the hot cell layout alternatives and the bases for the selection of the optimum layout are implemented. The graphical simulator and the results from this analysis can be effectively used not only for optimizing the hot cell layout but also designing the ACP equipment and maintenance process.

Introducing Mammalian Cell Culture and Cell Viability Techniques in the Undergraduate Biology Laboratory.

Science.gov (United States)

Bowey-Dellinger, Kristen; Dixon, Luke; Ackerman, Kristin; Vigueira, Cynthia; Suh, Yewseok K; Lyda, Todd; Sapp, Kelli; Grider, Michael; Crater, Dinene; Russell, Travis; Elias, Michael; Coffield, V McNeil; Segarra, Verónica A

2017-01-01

Undergraduate students learn about mammalian cell culture applications in introductory biology courses. However, laboratory modules are rarely designed to provide hands-on experience with mammalian cells or teach cell culture techniques, such as trypsinization and cell counting. Students are more likely to learn about cell culture using bacteria or yeast, as they are typically easier to grow, culture, and manipulate given the equipment, tools, and environment of most undergraduate biology laboratories. In contrast, the utilization of mammalian cells requires a dedicated biological safety cabinet and rigorous antiseptic techniques. For this reason, we have devised a laboratory module and method herein that familiarizes students with common cell culture procedures, without the use of a sterile hood or large cell culture facility. Students design and perform a time-efficient inquiry-based cell viability experiment using HeLa cells and tools that are readily available in an undergraduate biology laboratory. Students will become familiar with common techniques such as trypsinizing cells, cell counting with a hemocytometer, performing serial dilutions, and determining cell viability using trypan blue dye. Additionally, students will work with graphing software to analyze their data and think critically about the mechanism of death on a cellular level. Two different adaptations of this inquiry-based lab are presented-one for non-biology majors and one for biology majors. Overall, these laboratories aim to expose students to mammalian cell culture and basic techniques and help them to conceptualize their application in scientific research.

Operating experience and radiation protection problems in the working of the radio-metallurgy hot cell facilities at BARC

International Nuclear Information System (INIS)

Janardhanan, S.; Watamwar, S.B.; Mehta, S.K.; Pillai, P.M.B.; John, Jacob; Kutty, K.N.

1977-01-01

The Bhabha Atomic Research Centre at Bombay has six hot cell facilities for radiometallurgical investigations of irradiated/failed fuel elements. The hot cell facilities have been provided with certain built-in safety features, a ventilation system, radiation monitoring instruments for various purposes, a centralised air monitoring system and a central panel for display of various alarms. Procedures adopted for radiation protection and contamination control include : (1) radiation leak test for cells and filter efficiency evaluation before cell activation, (2) practices to be followed by frog suit personnel while working in hot cell areas, (3) receipt and handling of irradiated fuel elements, (4) cell filter change operation, (5) checks on high level drains and (6) effluent discharge and waste shipments. Operating experience in the working of these facilities along with radiation accident incidents is described. Data regarding release of activity during normal cell operations, dose rates during various metallurgical operations and personnel exposures are presented. (M.G.B.)

Space Solar Cell Characterization Laboratory

Data.gov (United States)

Federal Laboratory Consortium — FUNCTION: Measures, characterizes, and analyzes photovoltaic materials and devices. The primary focus is the measurement and characterization of solar cell response...

The impact of silicon solar cell architecture and cell interconnection on energy yield in hot & sunny climates

KAUST Repository

Haschke, Jan

2017-03-23

Extensive knowledge of the dependence of solar cell and module performance on temperature and irradiance is essential for their optimal application in the field. Here we study such dependencies in the most common high-efficiency silicon solar cell architectures, including so-called Aluminum back-surface-field (BSF), passivated emitter and rear cell (PERC), passivated emitter rear totally diffused (PERT), and silicon heterojunction (SHJ) solar cells. We compare measured temperature coefficients (TC) of the different electrical parameters with values collected from commercial module data sheets. While similar TC values of the open-circuit voltage and the short circuit current density are obtained for cells and modules of a given technology, we systematically find that the TC under maximum power-point (MPP) conditions is lower in the modules. We attribute this discrepancy to additional series resistance in the modules from solar cell interconnections. This detrimental effect can be reduced by using a cell design that exhibits a high characteristic load resistance (defined by its voltage-over-current ratio at MPP), such as the SHJ architecture. We calculate the energy yield for moderate and hot climate conditions for each cell architecture, taking into account ohmic cell-to-module losses caused by cell interconnections. Our calculations allow us to conclude that maximizing energy production in hot and sunny environments requires not only a high open-circuit voltage, but also a minimal series-to-load-resistance ratio.

Haptic shared control improves hot cell remote handling despite controller inaccuracies

NARCIS (Netherlands)

van Oosterhout, J.; Abbink, D. A.; Koning, J. F.; Boessenkool, H.; Wildenbeest, J. G. W.; Heemskerk, C. J. M.

2013-01-01

A promising solution to improve task performance in ITER hot cell remote handling is the use of haptic shared control. Haptic shared control can assist the human operator along a safe and optimal path with continuous guiding forces from an intelligent autonomous controller. Previous research tested

Computer control of ET-RR-1 hot cell manipulators

International Nuclear Information System (INIS)

Effat, A.M.; Rahman, F.A.

1990-01-01

The hot cell designed for remote handling of radioactive materials are, in effect, integral systems of safety devices for attaining adequate radiological protection for the operating personnel. Their operation involve potential hazards that are sometimes of great magnitude. The effect of an incident or accident could thus be fatal. some of these incident are due to the collision of the manipulator slave side with the radioactive objectives. Therefore in order to minimize the probability of such type of incidents, the movement of the manipulators is suggested (in the present investigation) to be kept under computer control. A model have been developed to control the movement of the hot cell manipulators in the slave side for Egypt first research reactor ET-RR-1, specially in the hidden sectors. The model is based on the use of a microprocessor and some accessories fixed to the manipulators slave side in a special manner such that it prevents the manipulator from colliding with radioactive objects. This is achieved by a signal transmitted to a specially designed brake which controls the movement of the upper arm of the manipulator master side. The hardware design of the model as well as the software are presented in details

DISMANTLING OF THE FUEL CELL LABORATORY AT RESEARCH CENTRE JUELICH

International Nuclear Information System (INIS)

Stahn, B.; Matela, K.; Bensch, D.; Ambos, Frank

2003-01-01

The fuel cell laboratory was constructed in three phases and taken into operation in the years 1962 to 1966. The last experimental work was carried out in 1996. After all cell internals had been disassembled, the fuel cell laboratory was transferred to shutdown operation in 1997. Three cell complexes, which differed, in particular, by the type of shielding (lead, cast steel, concrete), were available until then for activities at nuclear components. After approval by the regulatory authority, the actual dismantling of the fuel cell laboratory started in March 2000. The BZ I laboratory area consisted of 7 cells with lead shieldings of 100 to 250 mm thickness. This area was dismantled from April to September 2000. Among other things, approx. 30,000 lead bricks with a total weight of approx. 300 Mg were dismantled and disposed of. The BZ III laboratory area essentially consisted of cells with concrete shieldings of 1200 to 1400 mm thickness. The dismantling of this area started in the fir st half of 2001 and was completed in November 2002. Among other things, approx. 900 Mg of concrete was dismantled and disposed of. Since more than 90 % of the dismantled materials was measurable for clearance, various clearance measurement devices were used during dismantling. The BZ II laboratory area essentially consists of cells with cast steel shieldings of 400 to 460 mm thickness. In September 2002 it was decided to continue using this laboratory area for future tasks. The dismantling of the fuel cell laboratory was thus completed. After appropriate refurbishment, the fuel cell laboratory will probably take up operation again in late 2003

Closure of the concrete supercontainer in hot cell under thermal load

Energy Technology Data Exchange (ETDEWEB)

Craeye, Bart, E-mail: bart.craeye@artesis.b [Artesis Univerity College of Antwerp, Applied Engineering and Technology, Antwerp (Belgium); De Schutter, Geert [Magnel Laboratory for Concrete Research, Ghent University, Technologiepark-Zwijnaarde 904, 9052 Ghent (Belgium); Wacquier, William; Van Humbeeck, Hughes [ONDRAF/NIRAS, Belgian Agency for Radioactive Waste and Enriched Fissile Materials (Belgium); Van Cotthem, Alain [Tractebel Development Engineering, Consulting Company (Belgium); Areias, Lou [SCK.CEN, Belgian Nuclear Research Center (Belgium)

2011-05-15

Research highlights: We model the behaviour of the supercontainer for the disposal of high-level waste and spent fuel assemblies during fabrication at ground surface. We study the early-age cracking behaviour of the buffer and evaluate the crack creating mechanisms. In case accurate measures are taken, cracking of the buffer can be avoided. - Abstract: For the final disposal of long-lived, heat-emitting vitrified high-level waste (HLW) in a clayey host rock, an intensive study is conducted to investigate the early-age behaviour of concrete supercontainers. Self-compacting concrete (SCC) is taken as the reference concrete type as it facilitates the casting process in combination with an improved homogeneity compared to the traditional concrete compositions. A laboratory characterization program is conducted to obtain the relevant thermal, mechanical and maturity-related properties of the SCC. These obtained data are implemented into the material database of the finite element tool HEAT to study the behaviour of the concrete layers during the different construction stages of the supercontainer: (i) Stage 1: Fabrication of the concrete buffer inside a stainless steel envelope. No early-age cracking is expected in case accurate measures are taken to reduce the thermal gradient between the outer surface and the middle of the buffer, e.g. by providing insulation and excluding wind. (ii) Stages 2-4: Emplacement of the carbon steel overpack containing the HLW canisters, filling the remaining annular gap with cementitious filler and closure by fitting the lid under thermal load. The construction stages (2-4) for the closure of the supercontainer are executed in hot cell. In this study, the crack creating mechanism and the behaviour of the concrete supercontainer during these construction stages in hot cell are investigated. In case precautionary measures are taken, such as reducing the coefficient of thermal expansion (CTE) of the overpack, prolonging the preceding cooling

Closure of the concrete supercontainer in hot cell under thermal load

International Nuclear Information System (INIS)

Craeye, Bart; De Schutter, Geert; Wacquier, William; Van Humbeeck, Hughes; Van Cotthem, Alain; Areias, Lou

2011-01-01

Research highlights: → We model the behaviour of the supercontainer for the disposal of high-level waste and spent fuel assemblies during fabrication at ground surface. → We study the early-age cracking behaviour of the buffer and evaluate the crack creating mechanisms. → In case accurate measures are taken, cracking of the buffer can be avoided. - Abstract: For the final disposal of long-lived, heat-emitting vitrified high-level waste (HLW) in a clayey host rock, an intensive study is conducted to investigate the early-age behaviour of concrete supercontainers. Self-compacting concrete (SCC) is taken as the reference concrete type as it facilitates the casting process in combination with an improved homogeneity compared to the traditional concrete compositions. A laboratory characterization program is conducted to obtain the relevant thermal, mechanical and maturity-related properties of the SCC. These obtained data are implemented into the material database of the finite element tool HEAT to study the behaviour of the concrete layers during the different construction stages of the supercontainer: (i) Stage 1: Fabrication of the concrete buffer inside a stainless steel envelope. No early-age cracking is expected in case accurate measures are taken to reduce the thermal gradient between the outer surface and the middle of the buffer, e.g. by providing insulation and excluding wind. (ii) Stages 2-4: Emplacement of the carbon steel overpack containing the HLW canisters, filling the remaining annular gap with cementitious filler and closure by fitting the lid under thermal load. The construction stages (2-4) for the closure of the supercontainer are executed in hot cell. In this study, the crack creating mechanism and the behaviour of the concrete supercontainer during these construction stages in hot cell are investigated. In case precautionary measures are taken, such as reducing the coefficient of thermal expansion (CTE) of the overpack, prolonging the

Distinct Rayleigh scattering from hot spot mutant p53 proteins reveals cancer cells.

Science.gov (United States)

Jun, Ho Joon; Nguyen, Anh H; Kim, Yeul Hong; Park, Kyong Hwa; Kim, Doyoun; Kim, Kyeong Kyu; Sim, Sang Jun

2014-07-23

The scattering of light redirects and resonances when an electromagnetic wave interacts with electrons orbits in the hot spot core protein and oscillated electron of the gold nanoparticles (AuNP). This report demonstrates convincingly that resonant Rayleigh scattering generated from hot spot mutant p53 proteins is correspondence to cancer cells. Hot spot mutants have unique local electron density changes that affect specificity of DNA binding affinity compared with wild types. Rayleigh scattering changes introduced by hot-spot mutations were monitored by localized surface plasmon resonance (LSPR) shift changes. The LSPR λmax shift for hot-spot mutants ranged from 1.7 to 4.2 nm for mouse samples and from 0.64 nm to 2.66 nm for human samples, compared to 9.6 nm and 15 nm for wild type and mouse and human proteins, respectively with a detection sensitivity of p53 concentration at 17.9 nM. It is interesting that hot-spot mutants, which affect only interaction with DNA, launches affinitive changes as considerable as wild types. These changes propose that hot-spot mutants p53 proteins can be easily detected by local electron density alterations that disturbs the specificity of DNA binding of p53 core domain on the surface of the DNA probed-nanoplasmonic sensor. © 2014 WILEY-VCH Verlag GmbH & Co. KGaA, Weinheim.

Fuel cells for transportation program: FY1997 national laboratory annual report

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-12-31

The Department of Energy (DOE) Fuel Cells for Transportation Program is structured to effectively implement the research and development (R and D) required for highly efficient, low or zero emission fuel cell power systems to be a viable replacement for the internal combustion engine in automobiles. The Program is part of the Partnership for a New Generation of Vehicles (PNGV), a government-industry initiative aimed at development of an 80 mile-per-gallon vehicle. This Annual Report summarizes the technical accomplishments of the laboratories during 1997. Participants include: Argonne National Laboratory (ANL), Brookhaven National Laboratory (BNL), Lawrence Berkeley National Laboratory (LBNL), Los Alamos National Laboratory (LANL), Oak Ridge National Laboratory (ORNL), Pacific Northwest National Laboratory (PNNL), and the National Renewable Energy Laboratory (NREL). During 1997, the laboratory R and D included one project on solid oxide fuel cells; this project has since been terminated to focus Department resources on PEM fuel cells. The technical component of this report is divided into five key areas: fuel cell stack research and development; fuel processing; fuel cell modeling, testing, and evaluation; direct methanol PEM fuel cells; and solid oxide fuel cells.

A Preliminary Shielding Study on the Integrated Operation Verification System in the Head-End Hot-Cell of the Pyro-processing

Energy Technology Data Exchange (ETDEWEB)

Kim, Jinhwam; Kim, Yewon; Park, Se-Hwan; Ahn, Seong-Kyu; Cho, Gyuseong [KAIST, Daejeon (Korea, Republic of)

2016-10-15

Nuclear power accounts for more than 30 percent of power production in Korea. Its significance has annually been increased. Disposal spent fuel containing uranium, transuranic elements, and fission products is unavoidable byproduct of nuclear power production. it is recognized that finding appropriate sites for interim storage of disposal spent fuel is not easy because isolated sites should be required. Pyro-processing technology, Pyro-processing should be operated under high radiation environment in hot-cell structures. Because of this reason, all workers should be unauthorized to access inside the hot-cell areas under any circumstances except for acceptable dose verification and a normal operation should be remotely manipulated. For the reliable normal operation of pyroprocessing, it is noted that an evaluation of the space dose distribution in the hot-cell environments is necessary in advance in order to determine which technologies or instruments can be utilized on or near the process as the Integrated Operation Verification System (IOVS) is measured. Not like the electroreduction and electro-refining hot-cells, the head-end hot-cell equips Camera Radiation Detector (CRD) in which plutonium is securely measured and monitored for the safeguard of the pyro-processing. Results have been obtained using F2 surface tally in order to observe the magnitude of the gamma-ray and neutron flux which pass through the surface of the process cell. Furthermore, T-mesh tally has also been used to obtain the space dose distribution in the headend hot-cell. The hot-cell was divided into 7,668 cells in which each dimension was 1 x 1 x 1m for the T-mesh tally. To determine the position of the CRD and the surveillance camera, divergent approaches were required. Because the purpose of the CRD which contains a gamma-ray detector and a neutron detector is to identify the material composition as the process proceeds, the position in which detectable flux is exposed is required, whereas

Saturation spectroscopy of calcium atomic vapor in hot quartz cells with cold windows

Science.gov (United States)

Vilshanskaya, E. V.; Saakyan, S. A.; Sautenkov, V. A.; Murashkin, D. A.; Zelener, B. B.; Zelener, B. V.

2018-01-01

Saturation spectroscopy of calcium atomic vapor was performed in hot quartz cells with cold windows. The Doppler-free absorption resonances with spectral width near 50 MHz were observed. For these experiments and future applications long-lived quartz cells with buffer gas were designed and made. A cooling laser for calcium magneto-optical trap will be frequency locked to the saturation resonances in the long-lived cells.

Qualification of a production and packaging hot cell for sodium pertechnetate Tc 99m

International Nuclear Information System (INIS)

Cavero, Luis; Robles, Anita; Miranda, Jesus; Martinez, Ramos; Paragulla, Wilson; Moore, Mariel; Herrera, Jorge; Ocana, Elias; Portilla, Arturo; Otero, Manuel; Novoa, Carlos; Koga, Roberto

2014-01-01

It was designed and implemented a protocol for a hot cell of production and packaging of sodium pertechnetate Tc 99m, in a two-step process: installation qualification (IQ) and operation qualification (OQ). In the IQ design specifications and user requirements and associated equipment and materials by traceable documentation was verified. In the OQ scheduled for operation and control sequences it was verified plus operational tests recommended by the World Health Organization (WHO) and ISO 14644-1 and 3 were performed to clean areas. The results showed that the hot cell complies with the classification for Grades C and A for the preparation and packaging of Tc 99m. (authors).

Shielding calculation of a hot cell for the processing of fission products

International Nuclear Information System (INIS)

Rocha, A.C.S. da; Pina, J.L.S. de; Silva, J.J.G. da.

1986-12-01

A dose rate estimation is made for an operator of a lead wall, fission products processing hot cell, in a distance of 50 cm from the emission source, at Brazilian Institute of Nuclear Engineering (IEN). (L.C.J.A.)

Laboratory observation of hot bands of H+3

International Nuclear Information System (INIS)

Bawendi, M.G.; Rehfuss, B.D.; Oka, T.

1990-01-01

The (2ν 2 ,l=2 left-arrow ν 2 ), (2ν 2 ,l=0 left-arrow ν 2 ), and (ν 1 +ν 2 left-arrow ν 1 ) hot bands of H + 3 were observed. The vibrationally hot ions were produced in a liquid nitrogen cooled 6 kHz ac discharge using gas mixtures of H 2 and He. The spectra were detected in direct absorption using a newly extended tunable difference frequency spectrometer using both LiNbO 3 and LiIO 3 crystals as nonlinear optical elements. The range of this spectrometer is now ∼5300--∼1900 cm -1 . The positions of the rovibrational transitions compare extremely well with the theoretical predictions of Miller and Tennyson. A vibrational temperature study of the discharge indicates a significant population inversion between the ν 1 and ν 2 levels

Present status of mechanical testing technology at the Research Hot Laboratory

International Nuclear Information System (INIS)

Kizaki, M.; Tobita, T.; Koya, T.; Kikuchi, T.

1993-01-01

Mechanical tests of irradiated metallic materials at the Research Hot Laboratory(RHL) have been carried out for 30 years to support material research in JAERI and to evaluate the irradiation integrity of pressure vessel steel in commercial power plant. Two tensile testing machines and one Charpy impact testing machine are available for the examinations. One of the tensile testing machines has 1000 kgf load capacity under the vacuum of ∼ 10 -7 torr at the temperature of 1300degC max.. The other one has 10 tonf load capacity, and is utilized for the multi-purpose tests such as tensile and compressive tests in air atmosphere at the temperature between -160 and 900degC. Examinations cover tensile test, bending test, J ic fracture toughness test, low cycle fatigue test and so on. Charpy impact testing machine with notched-bar specimen is instrumented with 30 kgf-m capacity in the temperature range of -140 - 240 degC. To support these mechanical tests in RHL, special jigs, devices and instruments have been developed. (author)

Hot cells for testing the UO{sub 2} fuel elements after irradiation. Radiation protection conditions for hot cells design; Vruce celije za ispitivanje gorivnih elemenata UO{sub 2} posle ozracivanja, Uslovi zastite pri projektovanju vrucih celija

Energy Technology Data Exchange (ETDEWEB)

Pavlovic, A; Devic, J; Mihailovic, K [Institut za nuklearne nauke Vinca, Belgrade (Yugoslavia)

1969-07-01

This paper includes protection conditions which hot cells should satisfy for the investigation of fuel elements after reactor irradiation. The basic elements of hot cells are given, and the conditions for a special ventilation, dosimetric control and a special treatment of contaminated water are established (author) U radu su obuhvaceni uslovi zastite koje treba da zadovolje vruce celije za ispitivanje gorivnih elemenata posle ozracivanja u reaktoru, dati su osnovni elementi vrucih celija i postavljeni su uslovi za specijalnu ventilaciju, dozimentrijsku kontrolu i specijalni tretman otpadnih voda (author)

Dismantling of an alpha contaminated hot cell at the Marcoule Pilot Plant

International Nuclear Information System (INIS)

Tachon, M.

1988-01-01

For the remodeling of Marcoule Pilot Plant, the cell 82: old unit for plutonium solution purification by extraction, was dismantled. About 42 tons of wastes were evacuated. Some wastes wen decontaminated by mechanical means other wastes with higher residual activity were stored for subsequent processing. The operation shows that dismantling of a hot cell is possible even if incorporated in an operating plant [fr

Radiation protection measures for hot cell sanitation

International Nuclear Information System (INIS)

Berger, H.U.; Burck, W.; Dilger, H.

1983-01-01

The cell 5 of the Hot Cell Facility of the Kernforschungszentrum Karlsruhe GmbH (KfK) was to be restored and reequipped after 12 years of operation. The decontamination work was first done remotely controlled and afterwards by 38 persons entering the cell, which took about 2 months. The radiation protection methods and personal dosimetry systems are described. At the beginning of the work the γ-dose rate amounted up to 900 mSv/h. After completion of the remotely controlled decontamination work the γ-dose rate decreased to 1.5 mSv/h. At that time the (α+β-contamination was 10 5 Bq/cm 2 . Till the end of the work the removable activity dropped to 10 2 - 10 3 Bq/cm 2 for β-radiation, to 0.3 - 30 Bq/cm 2 for α-radiation and the local dose rate to about 0.03 mSv/h. During the work the accumulated collective doses were listed for breast, hand, head, gonads and foot. In the figure the development with the time of the doses for breast and hand is shown. During restoration work of the cell the accumulated collective whole-body dose amounted to 30 mSv. (orig.) [de

Hot wire deposited hydrogenated amorphous silicon solar cells

Energy Technology Data Exchange (ETDEWEB)

Mahan, A.H.; Iwaniczko, E.; Nelson, B.P.; Reedy, R.C. Jr.; Crandall, R.S. [National Renewable Energy Lab., Golden, CO (United States)

1996-05-01

This paper details the results of a study in which low H content, high deposition rate hot wire (HW) deposited amorphous silicon (a-Si:H) has been incorporated into a substrate solar cell. The authors find that the treatment of the top surface of the HW i layer while it is being cooled from its high deposition temperature is crucial to device performance. They present data concerning these surface treatments, and correlate these treatments with Schottky device performance. The authors also present first generation HW n-i-p solar cell efficiency data, where a glow discharge (GD) {mu}c-Si(p) layer was added to complete the partial devices. No light trapping layer was used to increase the device Jsc. Their preliminary investigations have yielded efficiencies of up to 6.8% for a cell with a 4000 {Angstrom} thick HW i-layer, which degrade less than 10% after a 900 hour light soak. The authors suggest avenues for further improvement of their devices.

Antinociceptive effects of voluntarily ingested buprenorphine in the hot-plate test in laboratory rats

DEFF Research Database (Denmark)

Kristensen, Sara Hestehave; Munro, Gordon; Brønnum Pedersen, Tina

2017-01-01

the animal to a thermal stimulus using a hot plate, significant antinociceptive effects of voluntarily ingested buprenorphine administered in Nutella® were demonstrated. This was evident at doses of 1.0 mg/kg 60 and 120 min post administration (Peffects were not as marked......Researchers performing experiments on animals should always strive towards the refinement of experiments, minimization of stress and provision of better animal welfare. An adequate analgesic strategy is important to improve post-operative recovery and welfare in laboratory rats and mice....... In addition, it is desirable to provide post-operative analgesia using methods that are minimally invasive and stressful. This study investigated the antinociceptive effects of orally administered buprenorphine ingested in Nutella® in comparison with subcutaneous buprenorphine administration. By exposing...

Thermal Shielding of the Shock Absorber to a Seal of a Hot-cell Cask

Energy Technology Data Exchange (ETDEWEB)

Bang, K. S.; Lee, J. C.; Kim, K. Y.; Seo, C. S.; Seo, K. S. [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2010-05-15

In order to safely transport the radioactive waste arising from the hot test of ACP(Advanced Spent Fuel Conditioning Process) a shipping package is required. Therefore KAERI is developing a shipping package to transport the radioactive waste arising in the ACPF during a hot test. Regulatory requirements for a Type B package are specified in the Korea MOST Act 2008-69, IAEA Safety Standard Series No. TS-R-1, and US 10 CFR Part. These regulatory guidelines classify the hot cell cask as a Type B package, and state that the Type B package for transporting radioactive materials should be able to withstand a test sequence consisting of a 9 m drop onto an unyielding surface, a 1 m drop onto a puncture bar, and a 30 minute fully engulfing fire. Greiner et al. performed a research on the thermal protection provided by shock absorbers by using CAFE computer code. This paper discusses the experimental approach used to simulate the response of the hot cell cask to fire in a furnace with chamber dimensions of 300 cm(W) x 400 cm(L) x 200 cm(H) by using a 1/2 scale model which was damaged by both a 9 m drop test and a 1 m puncture test

Report of the Committee of inquiry into a fire which occurred on 18 March 1987 in a radioisotope processing cell, Building 54 at the Lucas Heights Research Laboratories

International Nuclear Information System (INIS)

1987-01-01

At about 1745 hours on Wednesday, 18 March 1987 a fire occurred in a small charcoal filter inside a processing cell (hot cell) in Building 54 at the Lucas Heights Research Laboratories (LHRL). This cell was being used to process irradiated uranium to separate the radioactive isotope molybdenum-99. Some radioactive contamination escaped from the hot cell into the operating area and three AAEC officers were found to have minor radioactive contamination on their skin/hair. The majority of the radioactive material released from the fire was trapped by the main filters outside the cell. The total amounts of radioactive noble gas and of radioiodine released to the environment during the week in which the fire occurred were within the normal range of discharge and were 53% and 2.1%, respectively, of the weekly limit authorised by the NSW Department of Health. On the evidence available to it, the Committee concludes that the fire was caused by spontaneous combustion in the charcoal filter used to trap radioactive gases released by the operations in the hot cell; the mechanism causing the fire cannot be clearly established at this stage; no member of AAEC staff, NSW emergency services personnel or the general public suffered, or will suffer, any adverse health effects from radioactivity as a result of the accident

An improved out-cell to in-cell rapid transfer system at the HFEF/South

International Nuclear Information System (INIS)

Bacca, J.P.; Sherman, E.K.

1991-01-01

This paper reports on Argonne National Laboratory's Fuel Cycle Facility (FCF) (formerly named Hot Fuel Examination Facility-South) (HFEF/South) which is currently being refurbished and upgraded in preparation for demonstrating remote, fast reactor metal-fuel reprocessing and refabrication, as part of the Integral Fast Reactor (IFR) Program. Among the FCF hot-cell system upgrades being provided is a newly fabricated, direct, out-of-cell to in-cell, small-item transfer system for the FCF argon cell. This system will enable the rapid transfer of selected small items from the hot cell exterior into the argon cell (argon-gas atmosphere) of the facility, without necessitating the use of formerly employed, very time-consuming, and quite laborious procedures. The new system will be especially valuable for the rapid insertion of IFR fuel processing makeup materials and small tools into the argon cell, and for use in argon cell and overall FCF radioactive contamination-control activities

Remote maintenance for a new generation of hot cells

International Nuclear Information System (INIS)

Feldman, M.J.; Grant, N.R.

1987-01-01

For several years the Consolidated Fuel Reprocessing Program (CFRP) at Oak Ridge National Laboratory (ORNL) has been developing facility concepts, designing specialized equipment, and testing prototypical hardware for reprocessing spent fuel from fast breeder reactors. The major facility conceptual design, the Hot Experimental Facility, was based on total remote maintenance to increase plant availability and to reduce radiation exposure. This thrust included designing modular equipment to facilitate maintenance and the manipulation necessary to accomplish maintenance. Included in the design repetoire was the development effort in advanced servomanipulator systems, a remote sampling system, television viewing, and a transporter for manipulator positioning. Demonstration of these developed items is currently ongoing, and the technology is available for applications where production operations in highly radioactive environments are required

Stress Analysis for Mobile Hot Cell Design

International Nuclear Information System (INIS)

Muhammad Hannan Bahrin; Anwar Abdul Rahman; Mohd Arif Hamzah

2015-01-01

Prototype and Plant Development Centre (PDC) is developing a Mobile Hot Cell (MHC) to handle and manage Spent High Activity Radioactive Sources (SHARS), such as teletherapy heads and dry irradiators. At present, there are two units of MHC in the world, one in South Africa and the other one in China. Malaysian Mobile MHC is developed by Malaysian Nuclear Agency with the assistance of IAEA expert, based on the design of South Africa and China, but with improved features. Stress analysis has been performed on the design to fulfill the safety requirement in MHC operation. This paper discusses the loading effect analysis from the radiation shielding materials to the MHC wall structure, roof supporting column and window structure. (author)

Preliminary evaluation of rotational Vol-oxidizer for hot cell operation - 5320

International Nuclear Information System (INIS)

Kim, Y.H.; Lee, J.W.; Cho, Y.Z.; Ahn, D.H.; Song, K.C.

2015-01-01

KAERI is developing a mechanical head-end process for pyro-processing. As a piece of the processing equipment, a vol-oxidizer that can handle several tens of kg of HM/batch is under development to supply U 3 O 8 powders to an electrolytic reduction (ER) reactor. To operate a vol-oxidizer in a hot cell, the reactor should be optimized by the mechanical design, and the vol-oxidizer should have a high hull recovery rate. In addition, a vol-oxidizer for hot cell demonstrations that handles the spent fuel of high radiation virulence in a limited space should have a small size and not scatter in its outlet. In this paper, we aim at a preliminary evaluation of a rotational vol-oxidizer for hot cell operation. To evaluate the preliminary situation, we produced a theoretical equation of an optimum reactor size, and verification tests were conducted using an acryl vessel and zircaloy-4 tube according to various weights and lengths. In addition, we predicted the terminal velocity of U 3 O 8 using the terminal velocity of SiO 2 , which will determine the optimum air flux, and through an oxidation experiment, we verified the theory form to detect the existence of U 3 O 8 powder in a discharge filter. In addition, hull separation tests were conducted using a reactor and hulls with a 50 kg HM/batch for the recovery rate of the hulls. The results indicate that we obtained an appropriate air flux so as to not cause U 3 O 8 powder dispersion from using a Stokes equation and density ratio equation prior to the demonstration. The optimum flow and experimental results of the hull separation test have been applied for the design of the demonstration oxidizer, and the operation conditions of the oxidizer were produced. (authors)

Decommissioning of a hot cell with high levels of contamination. Experience during the Undressed of Workers

International Nuclear Information System (INIS)

Martinez, A.; Sancho, C.

1998-01-01

The object of this work is to show the radiological controls in decommissioning of the inner of the Base Cell of the Nuclear Facility of CIEMAT, IN-04 (Metallurgy Hot Cells) and the experience during the undressed of workers in decommissioning of this cell. The workers were equipped with one cotton overalls and one or two paper overalls of one-use. Also, when the radiation levels are high, the workers were equipped with leaded glasses and aprons. The protection equipment for internal contamination were autonomous and semi-autonomous respiratory equipment. Due to a high superficial contamination levels, two areas were established in order to proceed to the undressed of the workers when these concluded their work. The first area was a confined enclosure by joined to the hot cell, where an expert of the Radiation Protection Service (RPS), trained for it, take off the first paper overall and the first pair of gloves to the worker that come out the hot cells. The second area was at the exist of the Load Zone, where another expert of PRS, take off the second paper overall, the second pair of gloves and dislocated the pipe of air of the semi-autonomous respiratory equipment, to the worker that come out this zone. (Author)

Development of the maintenance process by the servo manipulator for the parts of the equipment outside the MSM's workspace in a hot cell

International Nuclear Information System (INIS)

Lee, J. Y.; Kim, S. H.; Song, D. K.; Park, B. S.; Yun, G. S.

2003-01-01

In this study, the maintenance process by the servo manipulator for the parts of the equipment that cannot be reached by MSM in the hot cell was developed. To do this, the virtual mock up is implemented using virtual prototyping technology. And, Using this mock-up, the workspace of the manipulators in the hot cell and the operator's view through the wall-mounted lead glass are analyzed. And the path planning of the servo manipulator using the collision detection of the virtual mockup is established. Also, the maintenance process for the parts of the equipment that are located out area of the MSM's workspace by the servo manipulator is proposed and verified through the graphic simulation. The proposed remote maintenance process of the equipment can be effectively used in the real hot cell operation. Also, the implemented virtual mock-up of the hot cell can be effecively used in analyzing the various hot cell operation and in enhancing the reliability and safety of the spent fuel manaement

Development of maintenance equipment for nuclear material fabrication equipment in a highly active hot cell

International Nuclear Information System (INIS)

Park, J. J.; Yang, M. S.; Kim, K. H. and others

2000-09-01

This report presents the development of a maintenance system for a highly contaminated nuclear material handling equipment at a hot-cell. This maintenance system has mainly three subsystems - a gamma-radiation measurement module for detecting a gamma-radiation level and identifying its distribution in-situ, a dry-type decontamination device for cleaning up contaminated particles, and a maintenance chamber for isolating contaminated equipment. The mechanical design considerations, controller, capabilities and remote operation and manipulation of the maintenance system are described. Such subsystems developed were installed and tested in the IMEF (Irradiated Material Examination Facility) M6 hot-cell after mock-up tests and performed their specific tasks successfully

Development of maintenance equipment for nuclear material fabrication equipment in a highly active hot cell

Energy Technology Data Exchange (ETDEWEB)

Park, J. J.; Yang, M. S.; Kim, K. H. and others

2000-09-01

This report presents the development of a maintenance system for a highly contaminated nuclear material handling equipment at a hot-cell. This maintenance system has mainly three subsystems - a gamma-radiation measurement module for detecting a gamma-radiation level and identifying its distribution in-situ, a dry-type decontamination device for cleaning up contaminated particles, and a maintenance chamber for isolating contaminated equipment. The mechanical design considerations, controller, capabilities and remote operation and manipulation of the maintenance system are described. Such subsystems developed were installed and tested in the IMEF (Irradiated Material Examination Facility) M6 hot-cell after mock-up tests and performed their specific tasks successfully.

Laboratory-scale shielded cell for 252Cf

International Nuclear Information System (INIS)

Anderl, R.A.; Cargo, C.H.

1979-01-01

A shielded-cell facility for storing and handling remotely up to 2 milligram quantities of unencapsulated 252 Cf has been built in a radiochemistry laboratory at the Test Reactor Area of the Idaho National Engineering Laboratory. Unique features of this facility are its compact bulk radiation shield of borated gypsum and transfer lines which permit the transport of fission product activity from 252 Cf fission sources within the cell to a mass separator and to a fast radiochemistry system in nearby rooms

A Wet Chemistry Laboratory Cell

Science.gov (United States)

2008-01-01

This picture of NASA's Phoenix Mars Lander's Wet Chemistry Laboratory (WCL) cell is labeled with components responsible for mixing Martian soil with water from Earth, adding chemicals and measuring the solution chemistry. WCL is part of the Microscopy, Electrochemistry, and Conductivity Analyzer (MECA) instrument suite on board the Phoenix lander. The Phoenix Mission is led by the University of Arizona, Tucson, on behalf of NASA. Project management of the mission is by NASA's Jet Propulsion Laboratory, Pasadena, Calif. Spacecraft development is by Lockheed Martin Space Systems, Denver.

Quality Assurance in Nuclear Fuel Research at the Laboratory of High- and Medium-level Activity at SCK-CEN

Energy Technology Data Exchange (ETDEWEB)

Sannen, L.; Gys, A.; Verwerft, M

1999-10-01

Quality assurance in nuclear fuel research demands specific calibration and validation methodologies. Indeed the analytical experiments in hot-cells on highly radioactive objects are non-standard and many times unique. The standards and validation methods developed for and applied to the main nuclear fuel research experiments in the hot laboratories of the Belgian Nuclear Research Centre SCK-CEN are outlined.

Quality Assurance in Nuclear Fuel Research at the Laboratory of High- and Medium-level Activity at SCK-CEN

International Nuclear Information System (INIS)

Sannen, L.; Gys, A.; Verwerft, M.

1999-10-01

Quality assurance in nuclear fuel research demands specific calibration and validation methodologies. Indeed the analytical experiments in hot-cells on highly radioactive objects are non-standard and many times unique. The standards and validation methods developed for and applied to the main nuclear fuel research experiments in the hot laboratories of the Belgian Nuclear Research Centre SCK-CEN are outlined

Remote maintenance for a new generation of hot cells

International Nuclear Information System (INIS)

Feldman, M.J.; Grant, N.R.

1987-01-01

For several years the Consolidated Fuel Reprocessing Program at the Oak Ridge National Laboratory has been developing facility concepts, designing specialized equipment, and testing prototypical hardware for reprocessing spent fuel from fast breeder reactors. The major facility conceptual design, the Hot Experimental Facility, was based on total remote maintenance to increase plant availability and to reduce radiation exposure. This thrust included designing modular equipment to facilitate maintenance and the manipulation necessary to accomplish maintenance. Included in the design repetoire was the development effort in advanced servomanipulator systems, a remote sampling system, television viewing, and a transporter system, television viewing, and a transporter for manipulator positioning. Demonstration of these developed items is currently ongoing, and the technology is available for applications where production operations in highly radioactive environments are required

Automation in nuclear hot cells (Paper No. 020)

International Nuclear Information System (INIS)

Pal, B.C.; Chougule, A.S.; Radke, M.G.; Ramaswamy, N.V.; Ramkumar, M.S.

1987-02-01

Bhabha Atomic Research Centre (BARC) in Trombay produces radioactive sources for a wide variety of uses in industry, agriculture and medicine, both within the country and abroad. The production and delivery of the radioactive sources in a form, ready for the end use, entails a number of operations, most of which are to be done with remote handling facilities, to maintain the prescribed biological shield to protect the operators. One of the repetitive operation among these which has to be done inside a concrete shielded hot-cell is the picking up of tiny radioactive wafers of iridium as small as 2.5mm dia., 0.3mm thick placing them in the required numbers to make up the total activity inside a capsule, closing the capsule with a top lid and finally welding the capsule. For doing this job remotely, recourse had to be taken to the use of master-slave manipulators (MSM), needing highly skilled operators to handle it for such delicate jobs repetitively. The operations for this repetitive job unlike most of other hot-cell operations, can be structured for machine operation and also fully automated. An automated system synthesising electromechanical, pneumatic and welding operations developed by the Division of Remote Handling and Robotics, BARC is described here. This relieves the operator of a number of jobs, to be repetitively done by MSM which would be strenous and taxing on account of the extremely small sizes of the pellets and wafers when they are to be handled, by remote indirect means with reliance on the master slave manipulators. A description of the automated system is given. (author). 3 figs

Annual report on operation, utilization and technical development of hot laboratories. From April 1, 1996 to March 31, 1997

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-02-01

This report describes activities, in fiscal year 1996, of the Reactor Fuel Examination Facility (RFEF), the Research Hot Laboratory (RHL) and the Waste Safety Testing Facility (WASTEF) which belong to the Department of Hot laboratories. In the RFEF, Post-Irradiation Examinations (PIEs) of PWR fuel assemblies irradiated in the Takahama Unit 3, a BWR fuel assembly irradiated in the Fukusima Daini Unit have been performed. Also, PIEs of assembly materials irradiated in the Fugen Reactor have been carried out. To support R and D works in JAERI, refabrication of segmented fuel rods have been done using irradiated LWR fuel rods for pulse irradiation in the NSRR and re-irradiation tests in the JMTR. PIEs have been performed on high burnup fuel rods and ROX fuel rods. For the RHL, PIEs have been performed on segment fuels irradiated in the NSRR, fuels and materials for HTTR, standard fuels for JRR-3M and materials for nuclear fusion reactor. In addition, a monitoring test of fuel elements in accordance with the surveillance program of the Magnox reactor of the Japan Atomic Power Corporation has been continued. In the WASTEF, leaching tests on TRU in simulated glass forms and a low flow rate tests on glass waste forms have been carried out. The examinations of alpha damage acceleration for the Synroc waste forms have also been performed. (author)

High Density Radiation Shielding Concretes for Hot Cells of 99mTc Project

International Nuclear Information System (INIS)

Sakr, K.

2006-01-01

High density concrete [more than 3.6 ton/m 3 (3.6x10 3 kg/m 3 )] was prepared to be used as a radiation shielding concrete (RSC) for hot-cells in gel technetium project at inshas to attenuate gamma radiation emitted from radioactive sources. different types of concrete were prepared by mixing local mineral aggregates mainly gravel and ilmenite . iron shots were added to the concrete mixture proportion as partial replacement of heavy aggregates to increase its density. the physical properties of prepared concrete in both plastic and hardened phases were investigated. compressive strength and radiation attenuation of gamma rays were determined. Results showed that ilmenite concrete mixed with iron shots had the highest density suitable to be use as RSC according to the chinese hot cell design requirements. Recommendations to avoid some technical problems of manufacturing radiation shielding concrete were maintained

Development of a pattern hot cell for production of injectable radiopharmaceuticals

International Nuclear Information System (INIS)

Campos, Fabio Eduardo de

2010-01-01

A controlled ambient should be established to the production/processing of materials susceptible to contamination, like injectable pharmaceuticals, in order to agree with normative and regulatory requirements. Considering medical but also toxic, radioactive and dangerous products, the ambient should work in special conditions to assure that the materials, which in same cases can be also volatile, do not escape to the external ambient, working in a selective, secure and controlled way. The conditions recommended by local and international rules in use, report an negative pressured ambient in relation to the adjacent areas. The technology related with the sizing of project to this kind of system is fully described in the literature, taking in account the rules that clearly describe the essential requirements. However, it is necessary to develop a controlled ambient for radiopharmaceutical production, in a way compatible with the concept of clean rooms and with the safety related to the manipulation of open radioactive wastes. In this work, some devices were created, methods and procedures were established making possible the classification of the ambient inside the hot cell, without physical barriers in the area, using ergonomic, flexible and practical conditions of work, that can results in the improvement of the productivity. The project resulted in the creation of a controlled ambient, in agreement with the normative requirements, using a pass through for entrance and exit of the materials, without compromise the internal air condition. The tight of the hot cell was obtained using doors with efficient sealing system and active joints. Tong manipulators were used to produce ergonomic and secure conditions, without compromise the internal conditions related to tight and classification in A and B grade, according to local and international rules. An efficient ventilation/exhaustion system was adopted to produce these results, composed by filters and special devices

Line Heat-Source Guarded Hot Plate

Data.gov (United States)

Federal Laboratory Consortium — Description:The 1-meter guarded hot-plate apparatus measures thermal conductivity of building insulation. This facility provides for absolute measurement of thermal...

Dose levels in the hot cells area ININ; Niveles de dosis en el area de celdas calientes-ININ

Energy Technology Data Exchange (ETDEWEB)

Torre, J. De la; Ramirez, J.M. [ININ, A.P. 18-1027, 11801 Mexico D.F. (Mexico); Solis, M.L. [UAEM, Toluca, Estado de Mexico (Mexico)]. E-mail: jto@nuclear.inin.mx

2004-07-01

The Laboratory of Hot Cells (LCC) located in the National Institute of Nuclear Research (ININ) is an institution, it is an area where radioactive material is managed with different activity values, in function of its original design for 10,000 curies of Co-60. Managing this materials in the installation, it implies to measure and to analyze the dose levels that the POE will receive as well as the implementation of appropriate measures of radiological protection and radiological safety, so that that is completed settled down by the concept ALARA. In this work they are carried out mensurations of the levels of the dose to receive for the POE when managing radionuclides with maximum activities that can be allowed in function of the current conditions of the cells and an evaluation of the obtained results is made comparing them with the effective international norms as well as the application of the program of surveillance and radiological protection implemented for the development of the works that are carry out in the installation. (Author)

Radiation monitoring programme in a university hot laboratory

International Nuclear Information System (INIS)

Tillander, M.; Heinonen, O.J.

1979-01-01

The Department of Radiochemistry in the University of Helsinki is the only institute teaching radiochemistry at the university level in Finland. The research programme of the Deparment must therefore include the uses of radiation and radionuclides in many branches of science. The students must receive adequate instruction in radiation protection for safe work in laboratories. This also has the educational benefit that the radiochemists will subsequently be able to observe the necessary safety precautions when employing ionizing radiation professionally. The Department of Radiochemistry consists of the following laboratories: a radiotracer laboratory, a neutron/electron and a gamma irradiation laboratory, an environmental low activity level laboratory, a whole-body counting laboratory, a reactor chemistry laboratory and a waste-treatment facility. The radiation protection organization of the Department is presented. Various methods of monitoring, including advantages and disadvantages are discussed. Emphasis is placed on the reactor chemistry laboratory where transuranic elements are utilized. These elements are highly radiotoxic and their monitoring in most cases requires destructive analysis. Different methods of determining external and internal doses are evaluated with regard to sensitivity and accuracy. Detection limits for radionuclides utilized in the laboratory are presented for different measurement systems, including non-destructive monitoring, spectrometry after chemical analysis, liquid scintillation counting and low-energy gamma spectrometry using a CsI-NaI scintillation detector. The guidelines laid down in the IAEA Safety Series Manuals are discussed in the light of practical experience. (author)

Utilizing hot electrons

Energy Technology Data Exchange (ETDEWEB)

Nozik, Arthur J.

2018-03-01

In current solar cells, any photon energy exceeding the semiconductor bandgap is lost before being collected, limiting the cell performance. Hot carrier solar cells could avoid these losses. Now, a detailed experimental study and analysis shows that this strategy could lead to an improvement of the photoconversion efficiency in practice.

Advanced Manufacturing Technologies (AMT): Additive Manufactured Hot Fire Planning and Testing in GRC Cell 32 Project

Science.gov (United States)

Fikes, John C.

2014-01-01

The objective of this project is to hot fire test an additively manufactured thrust chamber assembly TCA (injector and thrust chamber). GRC will install the additively manufactured Inconel 625 injector, two additively manufactured (SLM) water cooled Cu-Cr thrust chamber barrels and one additively manufactured (SLM) water cooled Cu-Cr thrust chamber nozzle on the test stand in Cell 32 and perform hot fire testing of the integrated TCA.

Process and equipment development for hot isostatic pressing treatability study

Energy Technology Data Exchange (ETDEWEB)

Bateman, Ken; Wahlquist, Dennis; Malewitz, Tim

2015-03-01

Battelle Energy Alliance (BEA), LLC, has developed processes and equipment for a pilot-scale hot isostatic pressing (HIP) treatability study to stabilize and volume reduce radioactive calcine stored at Idaho National Laboratory (INL). In 2009, the U. S. Department of Energy signed a Record of Decision with the state of Idaho selecting HIP technology as the method to treat 5,800 yd^3 (4,400 m^3) of granular zirconia and alumina calcine produced between 1953 and 1992 as a waste byproduct of spent nuclear fuel reprocessing. Since the 1990s, a variety of radioactive and hazardous waste forms have been remotely treated using HIP within INL hot cells. To execute the remote process at INL, waste is loaded into a stainless-steel or aluminum can, which is evacuated, sealed, and placed into a HIP furnace. The HIP simultaneously heats and pressurizes the waste, reducing its volume and increasing its durability. Two 1 gal cans of calcine waste currently stored in a shielded cask were identified as candidate materials for a treatability study involving the HIP process. Equipment and materials for cask-handling and calcine transfer into INL hot cells, as well as remotely operated equipment for waste can opening, particle sizing, material blending, and HIP can loading have been designed and successfully tested. These results demonstrate BEA’s readiness for treatment of INL calcine.

Annual report on operation, utilization and technical development of hot laboratories. From April 1, 2001 to March 31, 2002

International Nuclear Information System (INIS)

2003-01-01

This is an annual report in a fiscal year of 2001 that describes activities of the Reactor Fuel Examination Facility (RFEF), the Waste Safety Testing Facility (WASTEF), and the Research Hot Laboratory (RHL) in the Department of Hot laboratories. In RFEF, PIEs including destructive and nondestructive tests were performed on a BWR fuel assembly and/or its fuel rod irradiated in the Fukushima-2 Nuclear Power Station Unit-1 and a fuel assembly with UO 2 -Gd 2 O 3 and mixed oxide (MOX) fuel pellets for Japan Nuclear Cycle Development Institute. In addition, 34 fuel assemblies irradiated in the nuclear ship ''Mutsu'' were conveyed from Mutsu Establishment, and re-assembly and PIEs for the assemblies were carried out. In WASTEF, tests for evaluating barrier performance in terms of disposal of waste, high temperature tests for evaluating stable on TRansUraniums (TRU) nitrides, leaching tests on Rock-like OXide (ROX) fuels were performed. The slow Strain Rate Tests (SSRT) apparatuses were installed for investigation of Irradiation-Assisted Stress Corrosion Cracking (IASCC) on light water structural materials, and characterization tests for the apparatus were performed. In RHL, PIEs for light water reactor materials, fusion materials, and target materials of Proton Accelerator Facilities were carried out for laboratories in Japan Atomic Energy Research Institute. PIEs for zirconium alloys for ultra-high burn-up irradiated in the Kashiwazaki Nuclear Power Station Unit-5 were also performed. In order to investigate roots cause of pipe rupture in Hamaoka Nuclear Power Station Unit-1 of Chubu Electric Power Company, several examinations including SEM observation, EPMA, and Vickers hardness test were performed in those three facilities. The data from the examinations greatly contribute to clarify roots cause of the pipe rupture. (author)

Annual report on operation, utilization and technical development of hot laboratories. From April 1, 2001 to March 31, 2002

Energy Technology Data Exchange (ETDEWEB)

NONE

2003-01-01

This is an annual report in a fiscal year of 2001 that describes activities of the Reactor Fuel Examination Facility (RFEF), the Waste Safety Testing Facility (WASTEF), and the Research Hot Laboratory (RHL) in the Department of Hot laboratories. In RFEF, PIEs including destructive and nondestructive tests were performed on a BWR fuel assembly and/or its fuel rod irradiated in the Fukushima-2 Nuclear Power Station Unit-1 and a fuel assembly with UO{sub 2}-Gd{sub 2}O{sub 3} and mixed oxide (MOX) fuel pellets for Japan Nuclear Cycle Development Institute. In addition, 34 fuel assemblies irradiated in the nuclear ship ''Mutsu'' were conveyed from Mutsu Establishment, and re-assembly and PIEs for the assemblies were carried out. In WASTEF, tests for evaluating barrier performance in terms of disposal of waste, high temperature tests for evaluating stable on TRansUraniums (TRU) nitrides, leaching tests on Rock-like OXide (ROX) fuels were performed. The slow Strain Rate Tests (SSRT) apparatuses were installed for investigation of Irradiation-Assisted Stress Corrosion Cracking (IASCC) on light water structural materials, and characterization tests for the apparatus were performed. In RHL, PIEs for light water reactor materials, fusion materials, and target materials of Proton Accelerator Facilities were carried out for laboratories in Japan Atomic Energy Research Institute. PIEs for zirconium alloys for ultra-high burn-up irradiated in the Kashiwazaki Nuclear Power Station Unit-5 were also performed. In order to investigate roots cause of pipe rupture in Hamaoka Nuclear Power Station Unit-1 of Chubu Electric Power Company, several examinations including SEM observation, EPMA, and Vickers hardness test were performed in those three facilities. The data from the examinations greatly contribute to clarify roots cause of the pipe rupture. (author)

Slow hot carrier cooling in cesium lead iodide perovskites

Science.gov (United States)

Shen, Qing; Ripolles, Teresa S.; Even, Jacky; Ogomi, Yuhei; Nishinaka, Koji; Izuishi, Takuya; Nakazawa, Naoki; Zhang, Yaohong; Ding, Chao; Liu, Feng; Toyoda, Taro; Yoshino, Kenji; Minemoto, Takashi; Katayama, Kenji; Hayase, Shuzi

2017-10-01

Lead halide perovskites are attracting a great deal of interest for optoelectronic applications such as solar cells, LEDs, and lasers because of their unique properties. In solar cells, heat dissipation by hot carriers results in a major energy loss channel responsible for the Shockley-Queisser efficiency limit. Hot carrier solar cells offer the possibility to overcome this limit and achieve energy conversion efficiency as high as 66% by extracting hot carriers. Therefore, fundamental studies on hot carrier relaxation dynamics in lead halide perovskites are important. Here, we elucidated the hot carrier cooling dynamics in all-inorganic cesium lead iodide (CsPbI3) perovskite using transient absorption spectroscopy. We observe that the hot carrier cooling rate in CsPbI3 decreases as the fluence of the pump light increases and the cooling is as slow as a few 10 ps when the photoexcited carrier density is 7 × 1018 cm-3, which is attributed to phonon bottleneck for high photoexcited carrier densities. Our findings suggest that CsPbI3 has a potential for hot carrier solar cell applications.

Employing Hot Wire Anemometry to Directly Measure the Water Balance of a Proton Exchange Membrane Fuel Cell

DEFF Research Database (Denmark)

Shakhshir, Saher Al; Berning, Torsten

Proton exchange membrane fuel cells (PEMFC’s) are currently being commercialized for various applications ranging from automotive to stationary such as powering telecom back-up units. In PEMFC’s, oxygen from air is internally combined with hydrogen to form water and produce electricity and waste......-hoc and real time electrical signal of the fuel cell water balance by employing hot wire anemometry. The hot wire sensor is placed into a binary mixture of hydrogen and water vapour, and the voltage signal received gives valuable insight into heat and mass transfer phenomena in a PEMFC. A central question...

Radiation dose assessment of ACP hot cell in accident

International Nuclear Information System (INIS)

Kook, D. H.; Jeong, W. M.; Koo, J. H.; Jeo, I. J.; Lee, E. P.; Ryu, K. S.

2003-01-01

The Advanced spent fuel Condition in Process(ACP) is under development for the effective management of spent fuel which had been generated in nuclear plants. The ACP needs a hot cell where most operations will be performed. To give priority to the environments safety, radiation doses evaluations for the radioactive nuclides in accident cases were preliminarily performed with the meteorological data around facility site. Fire accident prevails over several accidnets. Internal Dose and External Dose evaluation according to short dispersion data for that case show a safe margin for regulation limits and SAR limit of IMEF where this facility will be constructed

Cause of Damage. Hot cracking; Schadensursache Heissrissigkeit

Energy Technology Data Exchange (ETDEWEB)

Wader, Therese [BENTELER Steel/Tube GmbH, Paderborn (Germany). Vorentwicklung Werkstoffe

2016-10-15

Under certain conditions, Nb-containing stainless steels are susceptible to hot cracking. Such conditions include low melting phases on the grain boundaries, a coarse-grained microstructure such as cast structures, microstructure orientations towards the main tensile direction and high processing temperatures. The case of damage was characterized using metallographic and microanalytical methods. In the laboratory, the critical temperature range for the formation of hot cracks could furthermore specifically be localized under mechanical stresses by means of a dilatometer aiming at clearly verifying the cause of the damage, namely ''hot cracks''.

Transcription-factor occupancy at HOT regions quantitatively predicts RNA polymerase recruitment in five human cell lines.

KAUST Repository

Foley, Joseph W; Sidow, Arend

2013-01-01

BACKGROUND: High-occupancy target (HOT) regions are compact genome loci occupied by many different transcription factors (TFs). HOT regions were initially defined in invertebrate model organisms, and we here show that they are a ubiquitous feature of the human gene-regulation landscape. RESULTS: We identified HOT regions by a comprehensive analysis of ChIP-seq data from 96 DNA-associated proteins in 5 human cell lines. Most HOT regions co-localize with RNA polymerase II binding sites, but many are not near the promoters of annotated genes. At HOT promoters, TF occupancy is strongly predictive of transcription preinitiation complex recruitment and moderately predictive of initiating Pol II recruitment, but only weakly predictive of elongating Pol II and RNA transcript abundance. TF occupancy varies quantitatively within human HOT regions; we used this variation to discover novel associations between TFs. The sequence motif associated with any given TF's direct DNA binding is somewhat predictive of its empirical occupancy, but a great deal of occupancy occurs at sites without the TF's motif, implying indirect recruitment by another TF whose motif is present. CONCLUSIONS: Mammalian HOT regions are regulatory hubs that integrate the signals from diverse regulatory pathways to quantitatively tune the promoter for RNA polymerase II recruitment.

Transcription-factor occupancy at HOT regions quantitatively predicts RNA polymerase recruitment in five human cell lines.

KAUST Repository

Foley, Joseph W

2013-10-20

BACKGROUND: High-occupancy target (HOT) regions are compact genome loci occupied by many different transcription factors (TFs). HOT regions were initially defined in invertebrate model organisms, and we here show that they are a ubiquitous feature of the human gene-regulation landscape. RESULTS: We identified HOT regions by a comprehensive analysis of ChIP-seq data from 96 DNA-associated proteins in 5 human cell lines. Most HOT regions co-localize with RNA polymerase II binding sites, but many are not near the promoters of annotated genes. At HOT promoters, TF occupancy is strongly predictive of transcription preinitiation complex recruitment and moderately predictive of initiating Pol II recruitment, but only weakly predictive of elongating Pol II and RNA transcript abundance. TF occupancy varies quantitatively within human HOT regions; we used this variation to discover novel associations between TFs. The sequence motif associated with any given TF\\'s direct DNA binding is somewhat predictive of its empirical occupancy, but a great deal of occupancy occurs at sites without the TF\\'s motif, implying indirect recruitment by another TF whose motif is present. CONCLUSIONS: Mammalian HOT regions are regulatory hubs that integrate the signals from diverse regulatory pathways to quantitatively tune the promoter for RNA polymerase II recruitment.

Developing the Sandia National Laboratories transportation infrastructure for isotope products and wastes

International Nuclear Information System (INIS)

Trennel, A.J.

1997-11-01

The US Department of Energy (DOE) plans to establish a medical isotope project that would ensure a reliable domestic supply of molybdenum-99 ( 99 Mo) and related medical isotopes (Iodine-125, Iodine-131, and Xenon-133). The Department's plan for production will modify the Annular Core Research Reactor (ACRR) and associated hot cell facility at Sandia National Laboratories (SNL)/New Mexico and the Chemistry and Metallurgy Research facility at Los Alamos National Laboratory (LANL). Transportation activities associated with such production is discussed

Design and installation of a laboratory-scale system for radioactive waste treatment

International Nuclear Information System (INIS)

Berger, D.N.; Knox, C.A.; Siemens, D.H.

1980-05-01

Described are the mechanical design features and remote installation of a laboratory-scale radiochemical immobilization system which is to provide a means at Pacific Northwest Laboratory of studying effluents generated during solidification of high-level liquid radioactive waste. Detailed are the hot cell, instrumentation, two 4-in. and 12-in. service racks, the immobilization system modules - waste feed, spray calciner unit, and effluent - and a gamma emission monitor system for viewing calcine powder buildup in the spray calciner/in-can melter

The results of decontamination and decommissioning of experimental DUPIC equipment at PIEF 9405 hot cell

Energy Technology Data Exchange (ETDEWEB)

Lee, H. H.; Park, J. J.; Shin, J. M.; Cho, K. H.; Yang, M. S.; Lee, E. P. [Korea Atomic Energy Research Institute, Taejeon (Korea)

2002-02-01

The characterization experiment for powder and sintered fuel had been performed using about 1 kg-U spent PWR fuel at No. 9405 hot-cell in PIEF(Post Irradiated Experiment Facility) since early in 1999. Currently, the experiments in PIEF have been completed. Since all DUPIC equipment in hot-cell are contaminated by high radioactive material, the decontamination and dismantlement must be performed remotely by M/S manipulator. During the radioactive waste packing and transportation, the reduction method of radiation exposure has to be considered. This report describes the basic plan for dismantlement/decontamination of the characterization equipment (power and sintered fuel). And methods of measurement/packing/transportation, method of dismantlement/decontamination of the experimental apparatus and the reduction method of radiation dose exposure, etc. are explained in order. 7 refs., 42 figs., 10 tabs. (Author)

Basic actinide chemistry and physics research in close cooperation with hot laboratories: ACTILAB

International Nuclear Information System (INIS)

Minato, K; Konashi, K; Fujii, T; Uehara, A; Nagasaki, S; Ohtori, N; Tokunaga, Y; Kambe, S

2010-01-01

Basic research in actinide chemistry and physics is indispensable to maintain sustainable development of innovative nuclear technology. Actinides, especially minor actinides of americium and curium, need to be handled in special facilities with containment and radiation shields. To promote and facilitate actinide research, close cooperation with the facilities and sharing of technical and scientific information must be very important and effective. A three-year-program B asic actinide chemistry and physics research in close cooperation with hot laboratories , ACTILAB, was started to form the basis of sustainable development of innovative nuclear technology. In this program, research on actinide solid-state physics, solution chemistry and solid-liquid interface chemistry is made using four main facilities in Japan in close cooperation with each other, where basic experiments with transuranium elements can be made. The 17 O-NMR measurements were performed on (Pu 0.91 Am 0.09 )O 2 to study the electronic state and the chemical behaviour of Am and Cm ions in electrolyte solutions was studied by distribution experiments.

The development of a mobile hot cell facility for the conditioning of spent high activity radioactive sources

International Nuclear Information System (INIS)

Liebenberg, G.R.; Al-Mughrabi, M.

2010-01-01

The International Atomic Energy Agency (IAEA) Waste Technology Section with additional support from the U.S. National Nuclear Security Administration (NNSA) through the IAEA Nuclear Security Fund has funded the design, fabrication, evaluation, and testing of a portable hot cell intended to address the problem of disused Spent High Activity Radioactive Sources (SHARS) in obsolete irradiation devices such as teletherapy heads and dry irradiators. The project is initially targeting the African continent but expected soon to expand to Latin America and Asia. This hot cell allows source removal, characterization, consolidation, repackaging in modern storage shields, and secure storage of high risk SHARS at national radioactive waste storage facilities. (authors)

Non-destructive test for irradiated fuels using X-ray CT system in hot-laboratory

International Nuclear Information System (INIS)

Kim, Heemoon; Kim, Gil-Soo; Yoo, Boung-Ok; Tahk, Young-Wook; Cho, Moon-Sung; Ahn, Sang-Bok

2015-01-01

To inspect inside of irradiated fuel rod for PIE in hotcell, neutron beam and X-ray have been used. Many hot laboratories in the world have shown the results for NDT by 2-D film data. Currently, computed image processing technology instead of film has been developed and CT was applied to the X-ray and neutron beam system. In this trend, our facility needed to set up X-ray system for irradiated fuel inspection and installed in hotcell with consideration of radiation damage. In this study, X-ray system was tested to be operated with radioactive samples and was performed to inspect fuel rods and observe internal damage and dimensional change. 450kV X-ray CT system was installed in hotcell with modification and tested to check image resolution and radiation damage. The image data were analyzed by 3-D computer software. 8 fuel plates and VHTR rods were inspected and measured internal shape and dimension

Multiweek cell culture project for use in upper-level biology laboratories.

Science.gov (United States)

Marion, Rebecca E; Gardner, Grant E; Parks, Lisa D

2012-06-01

This article describes a laboratory protocol for a multiweek project piloted in a new upper-level biology laboratory (BIO 426) using cell culture techniques. Human embryonic kidney-293 cells were used, and several culture media and supplements were identified for students to design their own experiments. Treatments included amino acids, EGF, caffeine, epinephrine, heavy metals, and FBS. Students researched primary literature to determine their experimental variables, made their own solutions, and treated their cells over a period of 2 wk. Before this, a sterile technique laboratory was developed to teach students how to work with the cells and minimize contamination. Students designed their experiments, mixed their solutions, seeded their cells, and treated them with their control and experimental media. Students had the choice of manipulating a number of variables, including incubation times, exposure to treatment media, and temperature. At the end of the experiment, students observed the effects of their treatment, harvested and dyed their cells, counted relative cell numbers in control and treatment flasks, and determined the ratio of living to dead cells using a hemocytometer. At the conclusion of the experiment, students presented their findings in a poster presentation. This laboratory can be expanded or adapted to include additional cell lines and treatments. The ability to design and implement their own experiments has been shown to increase student engagement in the biology-related laboratory activities as well as develop the critical thinking skills needed for independent research.

Hot Cell Liners Category of Transuranic Waste Stored Below Ground within Area G

Energy Technology Data Exchange (ETDEWEB)

Jones, Robert Wesley [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Hargis, Kenneth Marshall [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2014-09-01

A large wildfire called the Las Conchas Fire burned large areas near Los Alamos National Laboratory (LANL) in 2011 and heightened public concern and news media attention over transuranic (TRU) waste stored at LANL’s Technical Area 54 (TA-54) Area G waste management facility. The removal of TRU waste from Area G had been placed at a lower priority in budget decisions for environmental cleanup at LANL because TRU waste removal is not included in the March 2005 Compliance Order on Consent (Reference 1) that is the primary regulatory driver for environmental cleanup at LANL. The Consent Order is an agreement between LANL and the New Mexico Environment Department (NMED) that contains specific requirements and schedules for cleaning up historical contamination at the LANL site. After the Las Conchas Fire, discussions were held by the U.S. Department of Energy (DOE) with the NMED on accelerating TRU waste removal from LANL and disposing it at the Waste Isolation Pilot Plant (WIPP). This report summarizes available information on the origin, configuration, and composition of the waste containers within the Hot Cell Liners category; their physical and radiological characteristics; the results of the radioassays; and the justification to reclassify the five containers as LLW rather than TRU waste.

Physical processes in hot cosmic plasmas

International Nuclear Information System (INIS)

Fabian, A.G.; Giovannelli, F.

1990-01-01

The interpretation of many high energy astrophysical phenomena relies on a detailed knowledge of radiation and transport processes in hot plasmas. The understanding of these plasma properties is one of the aims of terrestrial plasma physics. While the microscopic properties of astrophysical plasmas can hardly be determined experimentally, laboratory plasmas are more easily accessible to experimental techniques, but transient phenomena and the interaction of the plasma with boundaries often make the interpretation of measurements cumbersome. This book contains the talks given at the NATO Advanced Research Workshop on astro- and plasma-physics in Vulcano, Sicily, May 29-June 2, 1989. The book focuses on three main areas: radiation transport processes in hot (astrophysical and laboratory) plasmas; magnetic fields; their generation, reconnection and their effects on plasma transport properties; relativistic and ultra-high density plasmas

The improvement of dynamic universal testing machine for hot cell usages

International Nuclear Information System (INIS)

Ahn, Sang Bok; Lee, Key Soon; Park, Dae Kyu; Hong, Kwon Pyo; Choo, Yong Sun

1998-01-01

Dynamic universal testing machine(UTM) were developed for hot cell usages, which can perform tensile, compression, bending, fracture toughness and fatigue crack growth tests. In this report, technical reviews in the course of developing machine were described. Detailed subjects are as follows; 1. Outline of testing method using dynamic UTM 2. Detailed testing system organizations 3. Technical specification to develop machine 4. Setting up load string 5. Inspection and pre-commissioning tests on machine. (author). 14 figs

Maintenance experiences at analytical laboratory at the Tokai reprocessing plant

International Nuclear Information System (INIS)

Suzuki, Hisanori; Nagayama, Tetsuya; Horigome, Kazushi; Ishibashi, Atsushi; Kitao, Takahiko; Surugaya, Naoki

2014-01-01

The Tokai Reprocessing Plant (TRP) is developing the technology to recover uranium and plutonium from spent nuclear fuel. There is an analytical laboratory which was built in 1977, as one of the most important facilities for process and material control analyses at the TRP. Samples taken from each process are analyzed by various analytical methods using hot cells, glove boxes and hume-hoods. A large number of maintenance work have been so far carried out and different types of experience have been accumulated. This paper describes our achievements in the maintenance activities at the analytical laboratory at the TRP. (author)

Advanced manipulator system for large hot cells

International Nuclear Information System (INIS)

Vertut, J.; Moreau, C.; Brossard, J.P.

1981-01-01

Large hot cells can be approached as extrapolated from smaller ones as wide, higher or longer in size with the same concept of using mechanical master slave manipulators and high density windows. This concept leads to a large number of working places and corresponding equipments, with a number of penetrations through the biological protection. When the large cell does not need a permanent operation of number of work places, as in particular to serve PIE machines and maintain the facility, use of servo manipulators with a large supporting unit and extensive use of television appears optimal. The advance on MA 23 and supports will be described including the extra facilities related to manipulators introduction and maintenance. The possibility to combine a powered manipulator and MA 23 (single or pair) on the same boom crane system will be described. An advance control system to bring the minimal dead time to control support movement, associated to the master slave arm operation is under development. The general television system includes over view cameras, associated with the limited number of windows, and manipulators camera. A special new system will be described which brings an automatic control of manipulator cameras and saves operator load and dead time. Full scale tests with MA 23 and support will be discussed. (author)

Certification of the PSI request for the renewal of the operation license for the Hot Laboratory; Gutachten zum Gesuch des Paul Scherrer Instituts um Erneuerung der Betriebsbewilligung für das Hotlabor

Energy Technology Data Exchange (ETDEWEB)

NONE

2014-03-15

At the Paul Scherrer Institute (PSI), the Hot Laboratory was built in the years 1961 to 1963 in the former EIR in order to make scientific material analyses on highly radioactive material samples and to prepare diagnostic and therapeutically useful radioisotopes. The 1964 safety report with the request for the granting of the operational warrant was revised for the first time in 2004. Further safety reports and radiation protection plans were produced and accepted by the surveying authorities. The operational regulations were revised and approved on a yearly basis by the PSI direction. The regulations reflect the experience gained in 40 years of safe operation and take new regulations in nuclear energy legislation into account. In the years 2000-2002 the Hot Lab was refitted especially with respect to the fields of radiation and fire protection. Presently, the Hot Lab is used for applied material research on highly radioactive samples which mainly come from nuclear power plants, research reactors and the target stations of the PSI accelerator facilities. The investigations on highly radioactive samples and the handling of large quantities of radioisotopes include the possibility of incidents. The analysis of such incidents shows that the legal safety requirements are satisfied. The Swiss Federal Nuclear Safety Inspectorate (ENSI) requirements concerning the protection of personnel, population and environment, as well as the protection against fire, are fulfilled. In the Hot Lab the principle of barriers for the containment of radioactive materials is applied. Open radioactive sources are manipulated in depressurized cells. The air extracted from the cells is filtered before being released to the environment. In the building, the total amount of radioactive materials is limited in order to reduce the exposition of the population in normal operation as well as in case of incidents, and to avoid criticality accidents. Possible weaknesses in this concept can be shown

Diurnal rhythm and concordance between objective and subjective hot flashes: the Hilo Women's Health Study.

Science.gov (United States)

Sievert, Lynnette L; Reza, Angela; Mills, Phoebe; Morrison, Lynn; Rahberg, Nichole; Goodloe, Amber; Sutherland, Michael; Brown, Daniel E

2010-01-01

The aims of this study were to test for a diurnal pattern in hot flashes in a multiethnic population living in a hot, humid environment and to examine the rates of concordance between objective and subjective measures of hot flashes using ambulatory and laboratory measures. Study participants aged 45 to 55 years were recruited from the general population of Hilo, HI. Women wore a Biolog hot flash monitor (UFI, Morro Bay, CA), kept a diary for 24 hours, and also participated in 3-hour laboratory measures (n = 199). Diurnal patterns were assessed using polynomial regression. For each woman, objectively recorded hot flashes that matched subjective experience were treated as true-positive readings. Subjective hot flashes were considered the standard for computing false-positive and false-negative readings. True-positive, false-positive, and false-negative readings were compared across ethnic groups by chi analyses. Frequencies of sternal, nuchal, and subjective hot flashes peaked at 1500 +/- 1 hours with no difference by ethnicity. Laboratory results supported the pattern seen in ambulatory monitoring. Sternal and nuchal monitoring showed the same frequency of true-positive measures, but nonsternal electrodes picked up more false-positive readings. Laboratory monitoring showed very low frequencies of false negatives. There were no ethnic differences in the frequency of true-positive or false-positive measures. Women of European descent were more likely to report hot flashes that were not objectively demonstrated (false-negative measures). The diurnal pattern and peak in hot flash occurrence in the hot humid environment of Hilo were similar to results from more temperate environments. Lack of variation in sternal versus nonsternal measures and in true-positive measures across ethnicities suggests no appreciable effect of population variation in sweating patterns.

A study on decontamination and decommissioning of experimental DUPIC equipment at PIEF 9405 hot cell

International Nuclear Information System (INIS)

Lee, H. H.; Park, J. J.; Shin, J. M.; Yang, M. S.; Lee, H. S.; Lee, E. P.

2000-09-01

The characterization experiment for powder and sintered fuel had been performed using about 1 kg-U spent PWR fuel at No. 9405 hot-cell in PIEF(Post Irradiated Experiment Facility) since early in 1999. Currently, The experiments in PIEF have been completed. It is supposed to dismantle and decontaminate the installed equipment by the end of year 2000. Since all of DUPIC equipment in hot-cell are contaminated by high radioactive material, the decontamination and dismantlement must br performed remotely by M/S manipulator. During the radioactive waste packing and transportation, the reduction method of radiation exposure has to be considered. Firstly, This report describes the basic plan for dismantlement/decontamination of the characterization equipment(power and sintered fuel). And methods of measurement/packing/ transportation, method of dismantlement/decontamination of the experimental apparatus and the reduction method of radiation dose exposure, etc. are explained in order

Hot water-extracted Lycium barbarum and Rehmannia glutinosa inhibit proliferation and induce apoptosis of hepatocellular carcinoma cells

Science.gov (United States)

Chao, Jane C-J; Chiang, Shih-Wen; Wang, Ching-Chiung; Tsai, Ya-Hui; Wu, Ming-Shun

2006-01-01

AIM: To investigate the effect of hot water-extracted Lycium barbarum (LBE) and Rehmannia glutinosa (RGE) on cell proliferation and apoptosis in rat and/or human hepatocellular carcinoma (HCC) cells. METHODS: Rat (H-4-II-E) and human HCC (HA22T/VGH) cell lines were incubated with various concentrations (0-10 g/L) of hot water-extracted LBE and RGE. After 6-24 h incubation, cell proliferation (n = 6) was measured by a colorimetric method. The apoptotic cells (n = 6) were detected by flow cytometry. The expression of p53 protein (n = 3) was determined by SDS-PAGE and Western blotting. RESULTS: Crude LBE (2-5 g/L) and RGE (2-10 g/L) dose-dependently inhibited proliferation of H-4-II-E cells by 11% (P < 0.05) to 85% (P < 0.01) after 6-24 h treatment. Crude LBE at a dose of 5 g/L suppressed cell proliferation of H-4-II-E cells more effectively than crude RGE after 6-24 h incubation (P < 0.01). Crude LBE (2-10 g/L) and RGE (2-5 g/L) also dose-dependently inhibited proliferation of HA22T/VGH cells by 14%-43% (P < 0.01) after 24 h. Crude LBE at a dose of 10 g/L inhibited the proliferation of HA22T/VGH cells more effectively than crude RGE (56.8% ± 1.6% vs 70.3% ± 3.1% of control, P = 0.0003 < 0.01). The apoptotic cells significantly increased in H-4-II-E cells after 24 h treatment with higher doses of crude LBE (2-5 g/L) and RGE (5-10 g/L) (P < 0.01). The expression of p53 protein in H-4-II-E cells was 119% and 143% of the control group compared with the LBE-treated (2, 5 g/L) groups, and 110% and 132% of the control group compared with the RGE -treated (5, 10 g/L) groups after 24 h. CONCLUSION: Hot water-extracted crude LBE (2-5 g/L) and RGE (5-10 g/L) inhibit proliferation and stimulate p53-mediated apoptosis in HCC cells. PMID:16874858

Evaluation of the Shielding Performance for the Hot-cell built in 100-MeV Isotope Beam-line of KOMAC

Energy Technology Data Exchange (ETDEWEB)

Park, Jeong Min; Park, Sung Kyun; Min, Yi Sub; Cho, Yong Sub [KAERI, Daejeon (Korea, Republic of)

2016-05-15

This study describes the structure of the hot-cell constructed in KOMAC for radioisotope production and evaluates the shielding performance for the hot-cell via the radiation shielding ability test. Korea multi-purpose accelerator complex (KOMAC) is currently operating 20-MeV and 100-MeV beam-line one by on. Additional 100-MeV beam-line and target room (TR101) are planned for the purpose of the radioisotope production in this year. The initial goal of the radioisotope production is to produce the radioactive isotopes, Sr-82 or Cu-67, used widely for the diagnosis and treatment of the cancer. In order to produce these radioisotopes mentioned, the proton beam with the energy between 70-MeV and 100- MeV at a beam current of 300 μA is irradiated into a solid target made of ZnO or RbCl. After the irradiation of the proton beam during approximately 100 hours, the radioisotope Sr-82 with the radioactivity amount of about 3.8 Ci or the Cu-67 with the amount of about 2.7 Ci will be produced. Radioisotopes produced though this process should be conveyed from the TR101 target room to the PR101 processing room and then in order to be delivered into the place for the next process step, a hot-cell is necessary. Result of the shielding performance evaluation of the hot-cell for producing radioisotopes shows the necessity of the shield reinforcement using lead material at side of the lead glass window.

Modeling deflagration waves out of hot spots

Science.gov (United States)

Partom, Yehuda

2017-01-01

It is widely accepted that shock initiation and detonation of heterogeneous explosives comes about by a two-step process known as ignition and growth. In the first step a shock sweeping through an explosive cell (control volume) creates hot spots that become ignition sites. In the second step, deflagration waves (or burn waves) propagate out of those hot spots and transform the reactant in the cell into reaction products. The macroscopic (or average) reaction rate of the reactant in the cell depends on the speed of those deflagration waves and on the average distance between neighboring hot spots. Here we simulate the propagation of deflagration waves out of hot spots on the mesoscale in axial symmetry using a 2D hydrocode, to which we add heat conduction and bulk reaction. The propagation speed of the deflagration waves may depend on both pressure and temperature. It depends on pressure for quasistatic loading near ambient temperature, and on temperature at high temperatures resulting from shock loading. From the simulation we obtain deflagration fronts emanating out of the hot spots. For 8 to 13 GPa shocks, the emanating fronts propagate as deflagration waves to consume the explosive between hot spots. For higher shock levels deflagration waves may interact with the sweeping shock to become detonation waves on the mesoscale. From the simulation results we extract average deflagration wave speeds.

Lignin monomer composition affects Arabidopsis cell-wall degradability after liquid hot water pretreatment

Directory of Open Access Journals (Sweden)

Ladisch Michael

2010-12-01

Full Text Available Abstract Background Lignin is embedded in the plant cell wall matrix, and impedes the enzymatic saccharification of lignocellulosic feedstocks. To investigate whether enzymatic digestibility of cell wall materials can be improved by altering the relative abundance of the two major lignin monomers, guaiacyl (G and syringyl (S subunits, we compared the degradability of cell wall material from wild-type Arabidopsis thaliana with a mutant line and a genetically modified line, the lignins of which are enriched in G and S subunits, respectively. Results Arabidopsis tissue containing G- and S-rich lignins had the same saccharification performance as the wild type when subjected to enzyme hydrolysis without pretreatment. After a 24-hour incubation period, less than 30% of the total glucan was hydrolyzed. By contrast, when liquid hot water (LHW pretreatment was included before enzyme hydrolysis, the S-lignin-rich tissue gave a much higher glucose yield than either the wild-type or G-lignin-rich tissue. Applying a hot-water washing step after the pretreatment did not lead to a further increase in final glucose yield, but the initial hydrolytic rate was doubled. Conclusions Our analyses using the model plant A. thaliana revealed that lignin composition affects the enzymatic digestibility of LHW pretreated plant material. Pretreatment is more effective in enhancing the saccharification of A. thaliana cell walls that contain S-rich lignin. Increasing lignin S monomer content through genetic engineering may be a promising approach to increase the efficiency and reduce the cost of biomass to biofuel conversion.

Diurnal rhythm and concordance between objective and subjective hot flashes: The Hilo Women’s Health Study

Science.gov (United States)

Sievert, Lynnette L.; Reza, Angela; Mills, Phoebe; Morrison, Lynn; Rahberg, Nichole; Goodloe, Amber; Sutherland, Michael; Brown, Daniel E.

2010-01-01

Objective To test for a diurnal pattern in hot flashes in a multi-ethnic population living in a hot, humid environment. To examine rates of concordance between objective and subjective measures of hot flashes using ambulatory and laboratory measures. Methods Study participants aged 45–55 were recruited from the general population of Hilo, Hawaii. Women wore a Biolog hot flash monitor, kept a diary for 24-hours, and also participated in 3-hour laboratory measures (n=199). Diurnal patterns were assessed using polynomial regression. For each woman, objectively recorded hot flashes that matched subjective experience were treated as true positive readings. Subjective hot flashes were considered the standard for computing false positive and false negative readings. True positive, false positive, and false negative readings were compared across ethnic groups by chi-square analyses. Results Frequencies of sternal, nuchal and subjective hot flashes peaked at 15:00 ± 1 hour with no difference by ethnicity. Laboratory results supported the pattern seen in ambulatory monitoring. Sternal and nuchal monitoring showed the same frequency of true positive measures, but non-sternal electrodes picked up more false positive readings. Laboratory monitoring showed very low frequencies of false negatives. There were no ethnic differences in the frequency of true positive or false positive measures. Women of European descent were more likely to report hot flashes that were not objectively demonstrated (false negative measures). Conclusions The diurnal pattern and peak in hot flash occurrence in the hot humid environment of Hilo was similar to results from more temperate environments. Lack of variation in sternal vs. non-sternal measures, and in true positive measures across ethnicities suggests no appreciable effect of population variation in sweating patterns. PMID:20220538

Work strain in decontamination of hot cells, 2

International Nuclear Information System (INIS)

Kinouchi, Nobuyuki; Ikezawa, Yoshio

1991-01-01

In decontamination of hot cells, the workers should wear suitable protective clothing to protect them from internal exposure and skin contamination. But such protective clothing causes some work strain, especially heat-stress. As a simple method to evaluate quantitative work strain, we used sweat rates of the wearers. In the previous paper, sweat rates for workers with two types of protective clothing were reported. In the present paper, sweat rates under severer working conditions are measured for three types: (1) pressure ventilated blouse; (2) full-face mask and polyethylene coverall; (3) full-face mask and vinyl anorak. The measured values for 65 subjects widely scatter from 0.2 to 2.5 l/h for all the protective clothing. Based on these values, the effects of protective clothing and working conditions (ambient temperature and humidity) on work strain are discussed. (author)

A user friendly method for image based acquisition of constraint information during constrained motion of servo manipulator in hot-cells

International Nuclear Information System (INIS)

Saini, Surendra Singh; Sarkar, Ushnish; Swaroop, Tumapala Teja; Panjikkal, Sreejith; Ray, Debasish Datta

2016-01-01

In master slave manipulator, slave arm is controlled by an operator to manipulate the objects in remote environment using an iso-kinematic master arm which is located in the control room. In such a scenario, where the actual work environment is separated from the operator, formulation of techniques for assisting the operator to execute constrained motion (preferential inclusion or preferential exclusion of workspace zones) in the slave environment are not only helpful, but also essential. We had earlier demonstrated the efficacy of constraint motion with predefined geometrical constraints of various types. However, in a hot-cell scenario the generation of the constraint equations is difficult since we shall not have access to the cell for taking measurements. In this paper, a user friendly method is proposed for image based acquisition of the various constraint geometries thus eliminating the need to take in-cell measurements. For this purpose various hot cell tasks and required geometrical primitives pertaining to these tasks have been surveyed and an algorithm has been developed for generating the constraint geometry for each primitive. This methodology shall increase the efficiency and ease of use of the hot cell Telemanipulator by providing real time constraint acquisition and subsequent assistive force based constrained motion. (author)

Applying hot-wire anemometry to directly measure the water balance in a proton exchange membrane fuel cell for a pre-humidified hydrogen stream

DEFF Research Database (Denmark)

Berning, Torsten; Shakhshir, Saher Al

2016-01-01

In a recent publication it has been shown how the water balance in a proton exchange membrane fuel cell can be determined employing hot wire anemometry. The hot wire sensor has to be placed into the anode outlet pipe of the operating fuel cell, and the voltage signal E that is read from the senso....... Finally, it will be shown how previously developed dew point diagrams for the anode side in a fuel cell can be corrected for a humidified hydrogen inlet stream....

Multiweek Cell Culture Project for Use in Upper-Level Biology Laboratories

Science.gov (United States)

Marion, Rebecca E.; Gardner, Grant E.; Parks, Lisa D.

2012-01-01

This article describes a laboratory protocol for a multiweek project piloted in a new upper-level biology laboratory (BIO 426) using cell culture techniques. Human embryonic kidney-293 cells were used, and several culture media and supplements were identified for students to design their own experiments. Treatments included amino acids, EGF,…

Development and efficiency assessment of process lubrication for hot forging

Science.gov (United States)

Kargin, S.; Artyukh, Viktor; Ignatovich, I.; Dikareva, Varvara

2017-10-01

The article considers innovative technologies in testing and production of process lubricants for hot bulk forging. There were developed new compositions of eco-friendly water-graphite process lubricants for hot extrusion and forging. New approaches to efficiency assessment of process lubricants are developed and described in the following article. Laboratory and field results are presented.

Dismantling of a hot cell-block and the treatment of the produced concrete bars

International Nuclear Information System (INIS)

Rompf, U.; Brielmayer, M.; Graf, A.; Stutz, U.; Ambos, F.

2003-01-01

A building with hot cells had been operated in Karlstein/Main from 1968 to 1989 in order to perform check-ups at radiated fuel rods and nuclear components. The operation of the system was stopped after an operation period of approximately 20 years. The core part of the building to be disassembled is a U-shaped hot cell-block with nine individual cells, partly consisting of heavy reinforced concrete, located in the ground floor (fig. 1 and fig. 2). The major part of the cells was covered with 10 mm steel plate and provided with approx. 1,400 openings of all different kinds. The wall thickness of the cells was between 0.90 m and 1.10 m. Under these conditions a successful decontamination at the ''existing building structure'' was not possible. Therefore, the non-supporting structures of the hot cell-block were removed in individual blocks by means of sawing and the remaining walls and floors were peeled by using the diamond rope sawing technique. The dismantling took 17 months. A re-treatment of the produced concrete blocks (235 blocks, approx. 970 Mg) to reduce the radioactive waste to a minimum was performed at the Research Centre Karlsruhe, Central Decontamination Department (HDB). The Target of the concrete bar treatment at HDB is to reduce the volume of radioactive waste to a minimum and to add the major part of the concrete bars to harmless utilisation. To achieve the same, initially the more contaminated parts of the bars without openings, such as tubes, cable or ventilating shafts, are removed by means of wire cutting and packed into a KONRAD-Container as radioactive waste. The remaining bar is decontaminated by means of sandblasting and afterwards, following successful release measurement, released from the scope of the regulations under the Atomic Energy. Bars with openings are crushed into small pieces by means of the remote-controlled chisel excavator, in order to separate the individual kinds of material. The rubble is packed into drums and measured by

Summary of Laboratory Capabilities Fact Sheets Waste Sampling and Characterization Facility and 222-S Laboratory Complex

International Nuclear Information System (INIS)

HADLEY, R.M.

2002-01-01

This summary of laboratory capabilities is provided to assist prospective responders to the CH2M HILL Hanford Group, Inc. (CHG) Requests for Proposal (RFP) issued or to be issued. The RFPs solicit development of treatment technologies as categorized in the CHG Requests for Information (RFI): Solid-Liquid Separations Technology - SOL: Reference-Number-CHG01; Cesium and Technetium Separations Technology - SOL: Reference-Number-CHG02; Sulfate Removal Technology - SOL: Reference-Number-CHG03; Containerized Grout Technology - SOL: Reference-Number-CHG04; Bulk Vitrification Technology - SOL: Reference-Number-CHG05; and TRU Tank Waste Solidification for Disposal at the Waste Isolation Pilot Plant - SOL: Reference-Number-CHG06 Hanford Analytical Services, Technology Project Management (TPM), has the capability and directly related experience to provide breakthrough innovations and solutions to the challenges presented in the requests. The 222-S Complex includes the 70,000 sq ft 222-S Laboratory, plus several support buildings. The laboratory has 11 hot cells for handling and analyzing highly radioactive samples, including tank farm waste. Inorganic, organic, and radiochemical analyses are performed on a wide variety of air, liquid, soil, sludge, and biota samples. Capabilities also include development of process technology and analytical methods, and preparation of analytical standards. The TPM staff includes many scientists with advanced degrees in chemistry (or closely related fields), over half of which are PhDs. These scientists have an average 20 years of Hanford experience working with Hanford waste in a hot cell environment. They have hundreds of publications related to Hanford tank waste characterization and process support. These would include, but are not limited to, solid-liquid separations engineering, physical chemistry, particle size analysis, and inorganic chemistry. TPM has had revenues in excess of $1 million per year for the past decade in above

Laboratory evaluation of hot metal de siliconizing process in ladle; Avaliacao laboratorial do processo de dessiliciacao do gusa na panela

Energy Technology Data Exchange (ETDEWEB)

Passos, Sergio R.M.; Furtado, Henrique S.; Bentes, Miguel A.G.; Almeida, Pedro S. de [Companhia Siderurgica Nacional, Volta Redonda, RJ (Brazil). Centro de Pesquisas

1996-12-31

The attractiveness of hot metal de siliconizing in ladle, relative to the process in blast furnace runner, is the previous knowledge of silicon content of hot metal, without the constraints of slag removing by skimmer met in torpedo car, and the better efficiency in low range silicon content, making easier the process controllability. Meanwhile, the main question about this technology is the extent of the resulfurization of hot metal that may occur due to process be performed after the desulfurization. This work simulates de de siliconizing process in ladle by experiments in induction furnace to compare the efficiencies of various de siliconizing agents available at CSN iron and steel making plant, and to evaluate the resulfurization intensity able to occur during the process, as well as, unexpected increasing of refractory wear. (author) 4 refs., 8 figs., 6 tabs.

Hot spot mutations in Finnish non-small cell lung cancers.

Science.gov (United States)

Mäki-Nevala, Satu; Sarhadi, Virinder Kaur; Rönty, Mikko; Kettunen, Eeva; Husgafvel-Pursiainen, Kirsti; Wolff, Henrik; Knuuttila, Aija; Knuutila, Sakari

2016-09-01

Non-small cell lung cancer (NSCLC) is a common cancer with a poor prognosis. The aim of this study was to screen Finnish NSCLC tumor samples for common cancer-related mutations by targeted next generation sequencing and to determine their concurrences and associations with clinical features. Sequencing libraries were prepared from DNA isolated from formalin-fixed, paraffin-embedded tumor material of 425 patients using the AmpliSeq Colon and Lung panel covering mutational hot spot regions of 22 cancer genes. Sequencing was performed with the Ion Torrent Personal Genome Machine (PGM). Data analysis of the hot spot mutations revealed mutations in 77% of the patients, with 7% having 3 or more mutations reported in the Catalogue of Somatic Mutations in Cancer (COSMIC) database. Two of the most frequently mutated genes were TP53 (46%) and KRAS (25%). KRAS codon 12 mutations were the most recurrently occurring mutations. EGFR mutations were significantly associated with adenocarcinoma, female gender and never/light-smoking history; CTNNB1 mutations with light ex-smokers, PIK3CA and TP53 mutations with squamous cell carcinoma, and KRAS with adenocarcinoma. TP53 mutations were most prevalent in current smokers and ERBB2, ERBB4, PIK3CA, NRAS, NOTCH1, FBWX7, PTEN and STK11 mutations occurred exclusively in a group of ever-smokers, however the association was not statistically significant. No mutation was found that associated with asbestos exposure. Finnish NSCLC patients have a similar mutation profile as other Western patients, however with a higher frequency of BRAF mutations but a lower frequency of STK11 and ERBB2 mutations. Moreover, TP53 mutations occurred frequently with other gene mutations, most commonly with KRAS, MET, EGFR and PIK3CA mutations. Copyright © 2016 Elsevier Ireland Ltd. All rights reserved.

Waste processing to support 99Mo production at Sandia National Laboratories

International Nuclear Information System (INIS)

Longley, S.; Carson, S.; McDonald, M.

1997-01-01

As part of the isotope production program at Sandia National Laboratories (SNL), procedures are being finalized for the production of 99 Mo from the irradiation of 235 U-coated stainless-steel targets at the Technical Area (TA) V reactor and hot-cell facilities. Methods have been identified and tested for the management of the nonproduct (waste) material as the final step in the production process. These methods were developed utilizing the waste material from a series of cold and hot tests, beginning with depleted uranium powder and culminating with a test involving an irradiated 235 U target with an initial fission product inventory of ∼18000 Ci at the end of the irradiation cycle. This paper describes the radioactive waste management from the isotope production

Toward Complete Utilization of Miscanthus in a Hot-Water Extraction-Based Biorefinery

Directory of Open Access Journals (Sweden)

Kuo-Ting Wang

2017-12-01

Full Text Available Miscanthus (Miscanthus sp. Family: Poaceae was hot-water extracted (two h, at 160 °C at three scales: laboratory (Parr reactor, 300 cm3, intermediate (M/K digester, 4000 cm3, and pilot (65 ft3-digester, 1.841 × 106 cm3. Hot-water extracted miscanthus, hydrolyzate, and lignin recovered from hydrolyzate were characterized and evaluated for potential uses aiming at complete utilization of miscanthus. Effects of scale-up on digester yield, removal of hemicelluloses, deashing, delignification degree, lignin recovery and purity, and cellulose retention were studied. The scale-dependent results demonstrated that before implementation, hot-water extraction (HWE should be evaluated on a scale larger than a laboratory scale. The production of energy-enriched fuel pellets from hot-water extracted miscanthus, especially in combination with recovered lignin is recommended, as energy of combustion increased gradually from native to hot-water extracted miscanthus to recovered lignin. The native and pilot-scale hot-water extracted miscanthus samples were also subjected to enzymatic hydrolysis using a cellulase-hemicellulase cocktail, to produce fermentable sugars. Hot-water extracted biomass released higher amount of glucose and xylose verifying benefits of HWE as an effective pretreatment for xylan-rich lignocellulosics. The recovered lignin was used to prepare a formaldehyde-free alternative to phenol-formaldehyde resins and as an antioxidant. Promising results were obtained for these lignin valorization pathways.

Welcome to the home page of the Decontamination and Decommissioning Program at Argonne National Laboratory

International Nuclear Information System (INIS)

1996-01-01

This report presents the details of the Argonne National Laboratory Home Page. Topics discussed include decontamination and decommissioning of the following: hot cells; remedial action; Experimental Boiling Water Reactor; glove boxes; the Chicago Pile No. 5 Research Reactor Facility; the Janus Reactor; Building 310 Retention Tanks; Zero Power Reactors 6 and 9; Argonne Thermal Source Reactor; cyclotron facility; and Juggernaut reactor

Hot Fuel Examination Facility/South

Energy Technology Data Exchange (ETDEWEB)

1990-05-01

This document describes the potential environmental impacts associated with proposed modifications to the Hot Fuel Examination Facility/South (HFEF/S). The proposed action, to modify the existing HFEF/S at the Argonne National Laboratory-West (ANL-W) on the Idaho National Engineering Laboratory (INEL) in southeastern Idaho, would allow important aspects of the Integral Fast Reactor (IFR) concept, offering potential advantages in nuclear safety and economics, to be demonstrated. It would support fuel cycle experiments and would supply fresh fuel to the Experimental Breeder Reactor-II (EBR-II) at the INEL. 35 refs., 12 figs., 13 tabs.

Hot Fuel Examination Facility/South

International Nuclear Information System (INIS)

1990-05-01

This document describes the potential environmental impacts associated with proposed modifications to the Hot Fuel Examination Facility/South (HFEF/S). The proposed action, to modify the existing HFEF/S at the Argonne National Laboratory-West (ANL-W) on the Idaho National Engineering Laboratory (INEL) in southeastern Idaho, would allow important aspects of the Integral Fast Reactor (IFR) concept, offering potential advantages in nuclear safety and economics, to be demonstrated. It would support fuel cycle experiments and would supply fresh fuel to the Experimental Breeder Reactor-II (EBR-II) at the INEL. 35 refs., 12 figs., 13 tabs

The effect of side-chain substitution and hot processing on diketopyrrolopyrrole-based polymers for organic solar cells

NARCIS (Netherlands)

Heintges, G.H.L.; Leenaers, P.J.; Janssen, R.A.J.

2017-01-01

The effects of cold and hot processing on the performance of polymer-fullerene solar cells are investigated for diketopyrrolopyrrole (DPP) based polymers that were specifically designed and synthesized to exhibit a strong temperature-dependent aggregation in solution. The polymers, consisting of

Dynamic Multiaxial Response of a Hot-Pressed Aluminum Nitride

Science.gov (United States)

2012-01-05

Hutchinson, Adv. Appl . Mech. 29 (1992). [34] H. Ming-Yuan, J.W. Hutchinson, Int. J. Solids Struct. 25 (1989) 1053. [35] J. Salem , L. Ghosn, Int. J...Dynamic Multiaxial Response of a Hot- Pressed Aluminum Nitride by Guangli Hu, C. Q. Chen, K. T. Ramesh, and J. W. McCauley ARL-RP-0487...Laboratory Aberdeen Proving Ground, MD 21005-5066 ARL-RP-0487 June 2014 Dynamic Multiaxial Response of a Hot- Pressed Aluminum Nitride

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

International Nuclear Information System (INIS)

Menon, M.N.

1978-07-01

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

The effects of Hot Pepper Extract and Capsaicin on Adipocyte Metabolism

Directory of Open Access Journals (Sweden)

Ching Sheng, Chu

2008-03-01

Full Text Available Objectives : The purpose of this study is to investigate the effects of hot pepper extract and capsaicin on the adipogenesis in 3T3-L1 cells, lipolysis in rat epididymal adipocytes and histological changes in porcine adipose tissue. Methods : Inhibiton of preadipocyte differentiation and/or stimulation of lipolysis play important roles in reducing obesity. 3T3-L1 preadipocytes were differentiated with adipogenic reagents by incubating for 3 days in the absence or presence of hot pepper extract or capsaicin ranging from 0.01 to 1㎎/㎖. The effects of hot pepper extract and capsaicin on adipogenesis were examined by measuring GPDH activity and by Oil Red O staining. Mature adipocytes from rat epididymal fat pad was incubated with hot pepper extract or capsaicin ranging from 0.01 to 1㎎/㎖ for 3 hrs. The effects of hot pepper extract and capsaicin on lipolysis were examined by measuring free glycerol released. Fat tissue from pig skin was injected with hot pepper extract or capsaicinCFP ranging from 0.1 to 10㎎/㎖ to examine the effects of hot pepper extract and capsaicin on histological changes under light microscopy. Results : The following results were obtained from present study on adipogenesis of preadipocytes, lipolysis of adipocytes and histological changes in fat tissue. 1. Hot pepper extract and capsaicin inhibited adipogenic differentiation at the concentration of 0.1 and 0.01㎎/㎖, respectively, indicating that capsaicin was more effective in inhibiting adipogenesis than hot pepper extract. 2. Hot pepper extract and capsaicin decreased the activity of glycerol-3-phosphate dehydrogenase(GPDH at the concentration of 0.1 and 0.01㎎/㎖, respectively, indicating that capsaicin was more effective in inhibiting adipogenic differentiation than hot pepper extract. 3. Hot pepper extract and capsaicin increased glycerol release at the concentration of 0.1㎎/㎖. There was no difference in lipolytic activity between hot pepper extract and

HOT CELL SYSTEM FOR DETERMINING FISSION GAS RETENTION IN METALLIC FUELS

Energy Technology Data Exchange (ETDEWEB)

Sell, D. A.; Baily, C. E.; Malewitz, T. J.; Medvedev, P. G.; Porter, D. L.; Hilton, B. A.

2016-09-01

A system has been developed to perform measurements on irradiated, sodium bonded-metallic fuel elements to determine the amount of fission gas retained in the fuel material after release of the gas to the element plenum. During irradiation of metallic fuel elements, most of the fission gas developed is released from the fuel and captured in the gas plenums of the fuel elements. A significant amount of fission gas, however, remains captured in closed porosities which develop in the fuel during irradiation. Additionally, some gas is trapped in open porosity but sealed off from the plenum by frozen bond sodium after the element has cooled in the hot cell. The Retained fission Gas (RFG) system has been designed, tested and implemented to capture and measure the quantity of retained fission gas in characterized cut pieces of sodium bonded metallic fuel. Fuel pieces are loaded into the apparatus along with a prescribed amount of iron powder, which is used to create a relatively low melting, eutectic composition as the iron diffuses into the fuel. The apparatus is sealed, evacuated, and then heated to temperatures in excess of the eutectic melting point. Retained fission gas release is monitored by pressure transducers during the heating phase, thus monitoring for release of fission gas as first the bond sodium melts and then the fuel. A separate hot cell system is used to sample the gas in the apparatus and also characterize the volume of the apparatus thus permitting the calculation of the total fission gas release from the fuel element samples along with analysis of the gas composition.

Hot-carrier solar cells using low-dimensional quantum structures

Energy Technology Data Exchange (ETDEWEB)

Watanabe, Daiki; Kasamatsu, Naofumi; Harada, Yukihiro; Kita, Takashi [Department of Electrical and Electronic Engineering, Graduate School of Engineering, Kobe University, 1-1 Rokkodai, Nada, Kobe 657-8501 (Japan)

2014-10-27

We propose a high-conversion-efficiency solar cell (SC) utilizing the hot carrier (HC) population in an intermediate-band (IB) of a quantum dot superlattice (QDSL) structure. The bandgap of the host semiconductor in this device plays an important role as an energy-selective barrier for HCs in the QDSLs. According to theoretical calculation using the detailed balance model with an air mass 1.5 spectrum, the optimum IB energy is determined by a trade-off relation between the number of HCs with energy exceeding the conduction-band edge and the number of photons absorbed by the valence band−IB transition. Utilizing experimental data of HC temperature in InAs/GaAs QDSLs, the maximum conversion efficiency under maximum concentration (45 900 suns) has been demonstrated to increase by 12.6% as compared with that for a single-junction GaAs SC.

Geographical distribution of hot flash frequencies: considering climatic influences.

Science.gov (United States)

Sievert, Lynnette Leidy; Flanagan, Erin K

2005-10-01

Laboratory studies suggest that hot flashes are triggered by small elevations in core body temperature acting within a reduced thermoneutral zone, i.e., the temperature range in which a woman neither shivers nor sweats. In the present study, it was hypothesized that women in different populations develop climate-specific thermoneutral zones, and ultimately, population-specific frequencies of hot flashes at menopause. Correlations were predicted between hot flash frequencies and latitude, elevation, and annual temperatures. Data on hot flash frequencies were drawn from 54 studies. Pearson correlation analyses and simple linear regressions were applied, first using all studies, and second using a subset of studies that included participants only to age 60 (n = 36). Regressions were repeated with all studies, controlling for method of hot flash assessment. When analyses were restricted to studies that included women up to age 60, average temperature of the coldest month was a significant predictor of hot flash frequency (P hottest and coldest temperatures was also a significant predictor (P coldest month, difference between hottest and coldest temperatures, and mean annual temperature were significant predictors of hot flash frequency. Women reported fewer hot flashes in warmer temperatures, and more hot flashes with increasing seasonality. These results suggest that acclimatization to coldest temperatures or sensitivity to seasonality may explain part of the population variation in hot flash frequency.

Microscopic characterizations of membrane electrode assemblies prepared under different hot-pressing conditions

International Nuclear Information System (INIS)

Liang, Z.X.; Zhao, T.S.; Xu, C.; Xu, J.B.

2007-01-01

The durability of the membrane electrode assembly (MEA) for direct methanol fuel cells (DMFCs) is one of the most critical issues to be addressed before widespread commercialization of the DMFC technology. In this work, we investigated the effect of the hot-pressing duration on the performance and durability of the MEA prepared by hot-pressing technique. It was found that the 60-min hot pressing at 135 deg. C under the pressure of 4.0 MPa yielded a significantly improved MEA durability than did the 3-min hot pressing (a typical duration in practice) under the same condition, but no substantial difference was found in the cell performance of the MEAs prepared with the two different hot-pressing durations. The reason why the hot-pressing duration had no significant effect on cell performance is explained based on X-ray diffraction (XRD), X-ray photoelectron spectroscopy (XPS), and Fourier transform infrared spectroscopy (FT-IR) characterizations of the changes in the physiochemical properties of MEAs and their constituent components, including the anode, cathode and Nafion membrane, before and after hot pressing with different durations

Investigation af a solar heating system for space heating and domestic hot water supply with a high degree of coverage

DEFF Research Database (Denmark)

Vejen, Niels Kristian

1999-01-01

A solar storage tank for space heating and domestic hot water supply was designed and testet in af laboratory test facility.......A solar storage tank for space heating and domestic hot water supply was designed and testet in af laboratory test facility....

Cellular Cultivation: Growing HeLa Cells Using Standard High School Laboratory Equipment.

Science.gov (United States)

Woloschak, Gayle; And Others

1995-01-01

Describes experiments to culture cells in a laboratory that provide students with hands-on experience in manipulating cells and a chance to observe cell growth characteristics first hand. Exposes students to sterile technique, cell culture, cell growth concepts, and eukaryotic cell structure. (JRH)

Extracting hot carriers from photoexcited semiconductor nanocrystals

Energy Technology Data Exchange (ETDEWEB)

Zhu, Xiaoyang

2014-12-10

This research program addresses a fundamental question related to the use of nanomaterials in solar energy -- namely, whether semiconductor nanocrystals (NCs) can help surpass the efficiency limits, the so-called “Shockley-Queisser” limit, in conventional solar cells. In these cells, absorption of photons with energies above the semiconductor bandgap generates “hot” charge carriers that quickly “cool” to the band edges before they can be utilized to do work; this sets the solar cell efficiency at a limit of ~31%. If instead, all of the energy of the hot carriers could be captured, solar-to-electric power conversion efficiencies could be increased, theoretically, to as high as 66%. A potential route to capture this energy is to utilize semiconductor nanocrystals. In these materials, the quasi-continuous conduction and valence bands of the bulk semiconductor become discretized due to confinement of the charge carriers. Consequently, the energy spacing between the electronic levels can be much larger than the highest phonon frequency of the lattice, creating a “phonon bottleneck” wherein hot-carrier relaxation is possible via slower multiphonon emission. For example, hot-electron lifetimes as long as ~1 ns have been observed in NCs grown by molecular beam epitaxy. In colloidal NCs, long lifetimes have been demonstrated through careful design of the nanocrystal interfaces. Due to their ability to slow electronic relaxation, semiconductor NCs can in principle enable extraction of hot carriers before they cool to the band edges, leading to more efficient solar cells.

Hot Deformation Behavior of Hot-Extruded AA7175 Through Hot Torsion Tests.

Science.gov (United States)

Lee, Se-Yeon; Jung, Taek-Kyun; Son, Hyeon-Woo; Kim, Sang-Wook; Son, Kwang-Tae; Choi, Ho-Joon; Oh, Sang-Ho; Lee, Ji-Woon; Hyun, Soong-Keun

2018-03-01

The hot deformation behavior of hot-extruded AA7175 was investigated with flow curves and processing maps through hot torsion tests. The flow curves and the deformed microstructures revealed that dynamic recrystallization (DRX) occurred in the hot-extruded AA7175 during hot working. The failure strain was highest at medium temperature. This was mainly influenced by the dynamic precipitation of fine rod-shaped MgZn2. The processing map determined the optimal deformation condition for the alloy during hot working.

Risk assessment of hot beta-particles from the Chernobyl fallout in Bulgaria

International Nuclear Information System (INIS)

Uzunov, I.

1993-01-01

Research on hot particles (HP) was carried out in the Laboratory of Dosimetry and Radiation Protection. Field measurements with a Geiger-counter led to early discovery of HP on the ground in May 1986. Laboratory measurements of HP activity followed and their nuclide composition was determined. The carcinogenic risk of HP is discussed on the basis of a computer model assuming the radiation as initiator and all other factors as stimulators for cell proliferation (promoters). It is found that in the case of low radiation dose the probability for cancer is almost directly proportional to the number of cell divisions while at high radiation dose the slope is nearly vertical and reaches saturation point at about 5 cell divisions. An estimation of the number of inhaled HP was made by investigation of air filters. It is concluded that, besides iodine, inhaled HP are the most hazardous factor of the Chernobyl fallout. For some critical groups of the population, engaged in dusty outdoor operations, the carcinogenic risk was estimates as high as 0.1 - 1%. An average activity of 50 Bq per retained particle is proposed. It is stressed that Bulgarian population had not been informed adequately and no protection measures against HP intake had been taken. 3 figs., 12 refs

Risk assessment of hot beta-particles from the Chernobyl fallout in Bulgaria

Energy Technology Data Exchange (ETDEWEB)

Uzunov, I

1994-12-31

Research on hot particles (HP) was carried out in the Laboratory of Dosimetry and Radiation Protection. Field measurements with a Geiger-counter led to early discovery of HP on the ground in May 1986. Laboratory measurements of HP activity followed and their nuclide composition was determined. The carcinogenic risk of HP is discussed on the basis of a computer model assuming the radiation as initiator and all other factors as stimulators for cell proliferation (promoters). It is found that in the case of low radiation dose the probability for cancer is almost directly proportional to the number of cell divisions while at high radiation dose the slope is nearly vertical and reaches saturation point at about 5 cell divisions. An estimation of the number of inhaled HP was made by investigation of air filters. It is concluded that, besides iodine, inhaled HP are the most hazardous factor of the Chernobyl fallout. For some critical groups of the population, engaged in dusty outdoor operations, the carcinogenic risk was estimates as high as 0.1 - 1%. An average activity of 50 Bq per retained particle is proposed. It is stressed that Bulgarian population had not been informed adequately and no protection measures against HP intake had been taken. 3 figs., 12 refs.

Decommissioning of the radio chemical hot laboratory of the european commission joint research centre of Ispra - 59207

International Nuclear Information System (INIS)

Ugolini, Daniele; Rossi, Francesco; Basile, Francesco

2012-01-01

The construction of the Radio Chemical Hot Laboratory (RCHL) of the Joint Research Centre (JRC) of Ispra began in the early 1960's while the laboratory activities started in 1964. In 1976 an annex to the main building was built. At this time the RCHL main research activities were in environment and biochemistry by means of radioactive tracers; neutron activation analyses; extraction of actinides from radioactive liquid waste coming from the nuclear fuel reprocessing plants; and analyses of U, Pu, and Th in samples from the nuclear fuel cycle in order to determine the isotopic ratio and the burn-up. In 1978, a new area of laboratories named 'Stabularium' was built to study the metabolism of heavy metal on laboratory animals. Complementary to the laboratory three pneumatic transfer systems for irradiated sources connected the RCHL to two research reactors. The decommissioning activities of the 2650 m 2 facility started in January 2008 and they were completed at the end of 2010 with the release for unrestricted use of all the buildings of the facility. They consisted in five main tasks: pre-decommissioning, licensing, dismantling, waste management, and final survey. The main pre-decommissioning activities were the physical and radiological characterization of the facility. The principal licensing activity was the preparation of the de-licensing documentation to obtain the license termination from the safety authorities. Dismantling consisted in the removal of all the equipments and ancillary systems, of the pneumatic transfer system, and in the decontamination of the structures of the controlled zone. The waste management was limited to the transfer of the waste and of the clearable material to the centralized waste management facility. The final survey consisted in the final radiological characterization to quantify the concentration of any residual radioactivity remained after the completion of the dismantling activities for the release of the RCHL without any

Development of remote electrochemical decontamination for hot cell applications

International Nuclear Information System (INIS)

Turner, A.D.; Lain, M.J.; Fletcher, P.A.; Dawson, R.K.; Pottinger, J.S.

1989-01-01

The primary aim of the programme is to develop and evaluate remote electrochemical decontamination systems for metal surfaces. The bulk of the waste volume should be reduced to a reuse or low-level waste disposal category, while concentrating most of the activity in a small volume suitable for immobilisation. The goal of the development programme is to test these techniques in both alpha-active and alpha-beta-gamma hot cells in order to ascertain their usefulness as a component of an overall decommissioning strategy. As a result of the radiological environment, particular emphasis will be placed on remote operation in order to reduce occupational radiation exposure. Two types of technique based on the electrochemical dissolution of thin surface layers of the substrate will be investigated: immersion of small items in tanks for electroetching and in situ electropolishing. In both cases, reagents will be chosen with their subsequent disposal in mind. (Author)

Tandem solar cells deposited using hot-wire chemical vapor deposition

NARCIS (Netherlands)

Veen, M.K. van

2003-01-01

In this thesis, the application of the hot-wire chemical vapor deposition (HWCVD) technique for the deposition of silicon thin films is described. The HWCVD technique is based on the dissociation of silicon-containing gasses at the catalytic surface of a hot filament. Advantages of this technique

Results of work in the hot cells of Laboratory Testing Materials Irradiated Areva of Carina project for the expansion of the database of mechanical characteristics of fractures in materials of RPV German irradiated

International Nuclear Information System (INIS)

Barthelmes, J.; Schabel, H.; Hein, H.; Kein, E.; Eiselt, C.

2013-01-01

In the frame of the already completed research projects CARINA and its predecessor CARISMA a data base was created for pre-irradiated original RPV steels of German PWRs which allowed to examine the consequences if the Master Curve (T 0 ) approach instead of the RT N OT concept is applied to the RPV safety assessment. Furthermore in CARINA different irradiation conditions with respect to the accumulated neutron fluences and specific impact parameters were investigated. Besides a brief introduction of the CARINA project and an overview of the main results an overview on the requirements of the hot laboratory work in terms of specimen manufacturing and material testing is given and examples for realization are shown. (Author)

Modification of a scanning electron microscope for remote operation in a hot cell

International Nuclear Information System (INIS)

Reed, J.R.; Watson, H.E.; Smidt, F.A. Jr.

1982-01-01

Scanning electron microscopy (SEM) examination of broken fracture specimens is an essential part of the characterization of the failure mode of fracture toughness of specimens. The large specimen mass required for such examinations dictates the use of a shielded facility for performing such examinations on irradiated specimens. This report describes the modification of a commercial SEM for remote operation in a hot cell. The facility is used to examine specimens from several Navy and DOE-sponsored programs conducted at NRL which require the examination of radioactive materials

FABRICE process for the refrabrication of experimental pins in a hot cell, from pins pre-irradiated in power reactors

International Nuclear Information System (INIS)

Vignesoult, N.; Atabek, R.; Ducas, S.

1982-06-01

The Fabrice ''hot cell refabrication'' process for small pins from very long irradiated fuel elements was developed at the CEA to allow parametric studies of the irradiation behavior of pins from nuclear power plants. Since this operation required complete assurance of the validity of the process, qualification of the fabrication was performed on test pins, refabricated in the hot cell, as well as irradiation qualification. The latter qualification was intended to demonstrate that, in identical experimental irradiation conditions, the refabricated Fabrice pins behaved in the same way as whole pins with the same initial characteristics. This qualification of the Fabrice process, dealing with more than twenty pins at different burnups, showed that fabrication did not alter: the inherent characteristics of the sampled fuel element and the irradiation behavior of the sampled fuel element [fr

Operational safety at the radiometallurgy laboratory of Fontenay-aux-Roses

International Nuclear Information System (INIS)

Hayet, Lucien; Petit, Pierre; Conche, Roger.

1976-01-01

Opened in 1967, the Radiometallurgy Laboratory is responsible for the examination of plutonium 239 based nuclear fuels of breeder reactors such as Rapsodie and Phenix. Part of the same laboratory is also responsible for the manufacture of californium 252 sources. These neutron sources can have a neutron fluency yield of 2,3 10 10 n/s/4π (i.e. 10mg of 252cf). This large laboratory includes a total area of 117m 2 of hot surfaces. It also includes 14 high activity cells with a capacity of 100000Ci at 1MeV. Located only 7km from the center of Paris, it must incorporate a special design and a particularly sure safety policy. Several statistics are given: irradiations, contaminations, incidents, quantity of fissile material, solid and liquid wastes etc... The principles of safety management are outlined and an analysis given of this basic nuclear facility [fr

Hot gas cleaning, a targeted project

Energy Technology Data Exchange (ETDEWEB)

Romey, I. [University of Essen, Essen (Germany)

1998-11-01

Advanced hot gas cleaning systems will play a key role in future integrated combined cycle technologies. IGCC demonstration plants in operation or under construction are at present equipped with conventional wet gas scrubbing and cleaning systems. Feasibility studies for those IGCC plants have shown that the total efficiency of the processes can be improved using hot gas cleaning systems. However, this technology has not been developed and tested at a technical scale. Six well-known European industrial companies and research centres jointly worked together since January 1996 on a Targeted Project `Hot Gas Cleaning` to investigate and develop new hot gas cleaning systems for advanced clean coal power generation processes. In addition project work on chemical analysis and modelling was carried out in universities in England and Germany. The latest main findings were presented at the workshop. The main project aims are summarised as follows: to increase efficiency of advanced power generation processes; to obtain a reduction of alkalis and environmental emissions e.g. SO{sub 2}, NO{sub x}, CO{sub 2} and dust; and to develop the design basis for future industrial plants based on long-term operation of laboratory, pilot and demo-plants. To cover a range of possible process routes for future hot gas cleaning systems the following research programme is under investigation: removal of trace elements by different commercial and self developed sorbents; gas separation by membranes; separation of gas turbine relevant pollutants by hot filter dust and; H{sub 2}S removal and gas dedusting at high temperatures. 13 figs.

Archaeal Nitrification in Hot Springs

Science.gov (United States)

Richter, A.; Daims, H.; Reigstad, L.; Wanek, W.; Wagner, M.; Schleper, C.

2006-12-01

Biological nitrification, i.e. the aerobic conversion of ammonia to nitrate via nitrite, is a major component of the global nitrogen cycle. Until recently, it was thought that the ability to aerobically oxidize ammonia was confined to bacteria of the phylum Proteobacteria. However, it has recently been shown that Archaea of the phylum Crenarchaeota are also capable of ammonia oxidation. As many Crenarchaeota are thermophilic or hyperthermophilic, and at least some of them are capable of ammonia oxidation we speculated on the existence of (hyper)thermophilic ammonia-oxidizing archaea (AOA). Using PCR primers specifically targeting the archaeal ammonia monooxygenase (amoA) gene, we were indeed able to confirm the presence of such organisms in several hot springs in Reykjadalur, Iceland. These hot springs exhibited temperatures well above 80 °C and pH values ranging from 2.0 to 4.5. To proof that nitrification actually took place under these extreme conditions, we measured gross nitrification rates by the isotope pool dilution method; we added 15N-labelled nitrate to the mud and followed the dilution of the label by nitrate production from ammonium either in situ (incubation in the hot spring) or under controlled conditions in the laboratory (at 80 °C). The nitrification rates in the hot springs ranged from 0.79 to 2.22 mg nitrate-N per L of mud and day. Controls, in which microorganisms were killed before the incubations, demonstrated that the nitrification was of biological origin. Addition of ammonium increased the gross nitrification rate approximately 3-fold, indicating that the nitrification was ammonium limited under the conditions used. Collectively, our study provides evidence that (1) AOA are present in hot springs and (2) that they are actively nitrifying. These findings have major implications for our understanding of nitrogen cycling of hot environments.

The Hot Cell Radioactive Waste Concept of Forschungszentrum Juelich

International Nuclear Information System (INIS)

Pott, G.; Halaszovich, St.

1999-01-01

During the last 30 years extensive scientific examinations on radioactive metals,ceramics and fuel elements have been carried out, so that a high volume of waste has resulted. Also from the dismantling of irradiated facilities metallics waste has o be handed. Prior for equipment repair the hot cell involved has to be decontaminated and a large amount of lower active waste is produced. The waste is collected for conditioning and storing. There are different categories as: low active liquid waste, low active burnable waste, fuel waste, low and high active metallic waste. For each waste category special transport container are used. For the volume reduction our Waste Department is equipped with special facilities e.g.: furnace for burning, drying, liquids evaporators, hydraulic press for pelletizing, decontamination box for the dismantling ad cleaning of components. After conditioning the waste will be stored on site or transported to final storage in a salt mine (ERAM) . Special documentation has to be done for the acceptance of this waste

Lead Acetate Based Hybrid Perovskite Through Hot Casting for Planar Heterojunction Solar Cells

Science.gov (United States)

Shin, Gwang Su; Choi, Won-Gyu; Na, Sungjae; Gökdemir, Fatma Pinar; Moon, Taeho

2018-03-01

Flawless coverage of a perovskite layer is essential in order to achieve realistic high-performance planar heterojunction solar cells. We present that high-quality perovskite layers can be efficiently formed by a novel hot casting route combined with MAI (CH3NH3I) and non-halide lead acetate (PbAc2) precursors under ambient atmosphere. Casting temperature is controlled to produce various perovskite microstructures and the resulted crystalline layers are found to be comprised of closely packed islands with a smooth surface structure. Lead acetate employed perovskite solar cells are fabricated using PEDOT:PSS and PCBM charge transporting layers, in p- i- n type planar architecture. Especially, the outstanding open-circuit voltage demonstrates the high crystallinity and dense coverage of the produced perovskite layers by this facile route.

Modeling and characterization of double resonant tunneling diodes for application as energy selective contacts in hot carrier solar cells

Science.gov (United States)

Jehl, Zacharie; Suchet, Daniel; Julian, Anatole; Bernard, Cyril; Miyashita, Naoya; Gibelli, Francois; Okada, Yoshitaka; Guillemolles, Jean-Francois

2017-02-01

Double resonant tunneling barriers are considered for an application as energy selective contacts in hot carrier solar cells. Experimental symmetric and asymmetric double resonant tunneling barriers are realized by molecular beam epitaxy and characterized by temperature dependent current-voltage measurements. The negative differential resistance signal is enhanced for asymmetric heterostructures, and remains unchanged between low- and room-temperatures. Within Tsu-Esaki description of the tunnel current, this observation can be explained by the voltage dependence of the tunnel transmission amplitude, which presents a resonance under finite bias for asymmetric structures. This effect is notably discussed with respect to series resistance. Different parameters related to the electronic transmission of the structure and the influence of these parameters on the current voltage characteristic are investigated, bringing insights on critical processes to optimize in double resonant tunneling barriers applied to hot carrier solar cells.

Establishment of effective maintenance method based on the superior inspection technique for the deteriorating hot laboratory exhaust stack

International Nuclear Information System (INIS)

Mizukoshi, Yasutaka; Yasu, Tetsunori

2012-06-01

The Materials Monitoring Facility is equipped with an exhaust stack to emit air from a controlled area (the hot laboratory) into the atmosphere. Cracks and exfoliation have been observed for the surface of the exhaust stack, which is made of reinforced concrete and was constructed on the seacoast about 25 years ago, so exposed to a salt-corrosive condition. In order to get details of the present condition of the exhaust stack, an inspection was carried out using an electromagnetic wave radar method and chloride content method. Cracks and exfoliation were observed for the whole stack surface, especially for high positions. Moreover, salt damage was observed for the outer surface of the exhaust stack, and it was estimated that the infiltration of the chloride content was about 17 mm. Based on this detailed inspection of the exhaust stack, maintenance and repair work were carried out. (author)

An Applied Study on the Decontamination and Decommissioning of Hot Cell Facilities in the United States and Comparison with the Studsvik Facility for Solid and Liquid Waste

International Nuclear Information System (INIS)

Varley, Geoff; Rusch, Chris

2006-07-01

This report presents the plans, processes and results of the decontamination and decommissioning of the Hot Cell Facility in Building 23 at the General Atomics Torrey Pines Mesa Facility (HCF) and compares the program and cost of decommissioning HCF with the Swedish cost estimate for decontamination and decommissioning of the HM hot cell and wastes treatment facility at Studsvik in Sweden. The HCF had three main hot cells and was licensed to: Receive, handle and ship radioactive materials; Remotely handle, examine and store irradiated fuel materials; Extract tritium (engineering scale); Support new reactor production development; Develop, fabricate and inspect UO 2 - BeO fuel materials. The HM facility in Studsvik was constructed to handle and package medium-active solid and liquid wastes, prior to disposal. Central to the facility is a conventional hot cell including three work stations, serviced by master slave manipulators. Other parts of the facility include holding tanks for liquid wastes and slurries, a centrifuge room, as well as an encapsulation station where drummed wastes can be encapsulated in cement, offices, laboratories and workshops and so on, as well as building and cell ventilation systems. Decontamination and decommissioning of the HCF took place during 1993 through 2001. The objective was to obtain regulatory release of the site so that it could be used on an unrestricted basis. Based on data from extensive hazardous and radiological materials characterization, GA evaluated four decommissioning options and selected dismantling as the only option that would satisfy the decommissioning objective. The decontamination and decommissioning scope included the following actions. 1. Remove the legacy waste that consisted of radioactive wastes stored at the HCF consisting of 21,434 kg of irradiated fuel material (IFM) that was owned by the US DoE and store the waste in temporary storage set up at the GA site. 2. Actual Decontamination and Dismantlement

An Applied Study on the Decontamination and Decommissioning of Hot Cell Facilities in the United States and Comparison with the Studsvik Facility for Solid and Liquid Waste

Energy Technology Data Exchange (ETDEWEB)

Varley, Geoff; Rusch, Chris [NAC International, Atlanta, GA (United States)

2006-07-15

This report presents the plans, processes and results of the decontamination and decommissioning of the Hot Cell Facility in Building 23 at the General Atomics Torrey Pines Mesa Facility (HCF) and compares the program and cost of decommissioning HCF with the Swedish cost estimate for decontamination and decommissioning of the HM hot cell and wastes treatment facility at Studsvik in Sweden. The HCF had three main hot cells and was licensed to: Receive, handle and ship radioactive materials; Remotely handle, examine and store irradiated fuel materials; Extract tritium (engineering scale); Support new reactor production development; Develop, fabricate and inspect UO{sub 2} - BeO fuel materials. The HM facility in Studsvik was constructed to handle and package medium-active solid and liquid wastes, prior to disposal. Central to the facility is a conventional hot cell including three work stations, serviced by master slave manipulators. Other parts of the facility include holding tanks for liquid wastes and slurries, a centrifuge room, as well as an encapsulation station where drummed wastes can be encapsulated in cement, offices, laboratories and workshops and so on, as well as building and cell ventilation systems. Decontamination and decommissioning of the HCF took place during 1993 through 2001. The objective was to obtain regulatory release of the site so that it could be used on an unrestricted basis. Based on data from extensive hazardous and radiological materials characterization, GA evaluated four decommissioning options and selected dismantling as the only option that would satisfy the decommissioning objective. The decontamination and decommissioning scope included the following actions. 1. Remove the legacy waste that consisted of radioactive wastes stored at the HCF consisting of 21,434 kg of irradiated fuel material (IFM) that was owned by the US DoE and store the waste in temporary storage set up at the GA site. 2. Actual Decontamination and

TERT promoter hot spot mutations are frequent in Indian cervical and oral squamous cell carcinomas.

Science.gov (United States)

Vinothkumar, Vilvanathan; Arunkumar, Ganesan; Revathidevi, Sundaramoorthy; Arun, Kanagaraj; Manikandan, Mayakannan; Rao, Arunagiri Kuha Deva Magendhra; Rajkumar, Kottayasamy Seenivasagam; Ajay, Chandrasekar; Rajaraman, Ramamurthy; Ramani, Rajendren; Murugan, Avaniyapuram Kannan; Munirajan, Arasambattu Kannan

2016-06-01

Squamous cell carcinoma (SCC) of the uterine cervix and oral cavity are most common cancers in India. Telomerase reverse transcriptase (TERT) overexpression is one of the hallmarks for cancer, and activation through promoter mutation C228T and C250T has been reported in variety of tumors and often shown to be associated with aggressive tumors. In the present study, we analyzed these two hot spot mutations in 181 primary tumors of the uterine cervix and oral cavity by direct DNA sequencing and correlated with patient's clinicopathological characteristics. We found relatively high frequency of TERT hot spot mutations in both cervical [21.4 % (30/140)] and oral [31.7 % (13/41)] squamous cell carcinomas. In cervical cancer, TERT promoter mutations were more prevalent (25 %) in human papilloma virus (HPV)-negative cases compared to HPV-positive cases (20.6 %), and both TERT promoter mutation and HPV infection were more commonly observed in advanced stage tumors (77 %). Similarly, the poor and moderately differentiated tumors of the uterine cervix had both the TERT hot spot mutations and HPV (16 and 18) at higher frequency (95.7 %). Interestingly, we observed eight homozygous mutations (six 228TT and two 250TT) only in cervical tumors, and all of them were found to be positive for high-risk HPV. To the best of our knowledge, this is the first study from India reporting high prevalence of TERT promoter mutations in primary tumors of the uterine cervix and oral cavity. Our results suggest that TERT reactivation through promoter mutation either alone or in association with the HPV oncogenes (E6 and E7) could play an important role in the carcinogenesis of cervical and oral cancers.

Decommissioning of AECL Whiteshell Laboratories: progress from first five years of legacy funding

International Nuclear Information System (INIS)

Swartz, R.S.; Bilinsky, D.M.; Harding, J.W.; Ridgway, W.R.

2011-01-01

In 2006, the Government of Canada adopted a new long-term strategy to deal with the nuclear legacy liabilities and initiated a five-year start-up phase. The objective is to safely and cost-effectively reduce these liabilities, and associated risks, based on sound waste management and environmental principles in the best interests of Canadians. AECL's Whiteshell Laboratories is part of the long-term strategy and decommissioning activities are underway. Several redundant non-nuclear buildings have been removed/decommissioned, and redundant nuclear facilities (hot cell facilities, radiochemical laboratories) are being decontaminated and prepared for demolition. This paper describes the progress in the first five-year funding period (2006 April to 2011 March). (author)

Time to B. cereus about hot chocolate.

Science.gov (United States)

Nelms, P K; Larson, O; Barnes-Josiah, D

1997-01-01

To determine the cause of illnesses experienced by employees of a Minneapolis manufacturing plant after drinking hot chocolate bought from a vending machine and to explore the prevalence of similar vending machine-related illnesses. The authors inspected the vending machines at the manufacturing plant where employees reported illnesses and at other locations in the city where hot chocolate beverages were sold in machines. Tests were performed on dry mix, water, and beverage samples and on machine parts. Laboratory analyses confirmed the presence of B. cereus in dispensed beverages at a concentration capable of causing illness (170,000 count/gm). In citywide testing of vending machines dispensing hot chocolate, 7 of the 39 licensed machines were found to be contaminated, with two contaminated machines having B. cereus levels capable of causing illness. Hot chocolate sold in vending machines may contain organisms capable of producing toxins that under favorable conditions, can induce illness. Such illnesses are likely to be underreported. Even low concentrations of B. cereus may be dangerous for vulnerable populations such as the aged or immunosuppressed. Periodic testing of vending machines is thus warranted. The relationship between cleaning practices and B. cereus contamination is an issue for further study.

Microbiology of Kamchatka Peninsula Hot Springs

Science.gov (United States)

Bonch-Osmolovsk, E.

2005-12-01

Hot springs of Uzon Caldera, Geyser Valley, Moutnovsky Volcano (Kamchatka Peninsula) served as the sources of isolation of numerous thermophilic prokaryotes, many of them representing new taxa. Among new isolates there were hyperthermophilic archaea - neutrophilic or acidophilic anaerobic organotrophs, able to use a wide range of polymeric organic substrates. Bacterial isolates were in majority represented by moderate thermophiles - organotrophs and lithoautotrophs. Latter group consisted of anaerobes oxidizing molecular hydrogen in the course of sulfate, sulfur or iron reduction, and of anaerobic CO-oxidizing, hydrogen-producing bacteria. Some of new isolates represented deep phylogenetic lineages in Bacteria domain. Microbial activity in Kamchatka hot springs was studied by means of radioisotopic tracing. The rates of methanogenesis, acetogenesis, inorganic carbon assimilation, acetate oxidation were determined in three different hot springs with pH ranging from 3.0 to 8.5 and water temeperature being in the range from 55 to 85oC. The results indicated the presence and activity of novel metabolic groups of thermophilic prokaryotes that so far have not been known in laboratory cultures.

Solar 'hot spots' are still hot

Science.gov (United States)

Bai, Taeil

1990-01-01

Longitude distributions of solar flares are not random but show evidence for active zones (or hot spots) where flares are concentrated. According to a previous study, two hot spots in the northern hemisphere, which rotate with a synodic period of about 26.72 days, produced the majority of major flares, during solar cycles 20 and 21. The more prominent of these two hot spots is found to be still active during the rising part of cycle 22, producing the majority of northern hemisphere major flares. The synodic rotation period of this hot spot is 26.727 + or - 0.007 days. There is also evidence for hot spots in the southern hemisphere. Two hot spots separated by 180 deg are found to rotate with a period of 29.407 days, with one of them having persisted in the same locations during cycles 19-22 and the other, during cycles 20-22.

Clinical and laboratory profile of patients with sickle cell anemia

Directory of Open Access Journals (Sweden)

Phelipe Gabriel dos Santos Sant'Ana

Full Text Available Abstract Objective: This study aimed to describe and analyze clinical and laboratory characteristics of patients with sickle cell anemia treated at the Hemominas Foundation, in Divinópolis, Brazil. Furthermore, this study aimed to compare the clinical and laboratory outcomes of the group of patients treated with hydroxyurea with those patients that were not treated with hydroxyurea. Methods: Clinical and laboratorial data were obtained by analyzing medical records of patients with sickle cell anemia. Results: Data from the medical records of 50 patients were analyzed. Most of the patients were female (56%, aged between 20 and 29 years old. Infections, transfusions, cholecystectomy, splenectomy and systemic arterial hypertension were the most common clinical adverse events of the patients. The most frequent cause of hospitalization was painful crisis. The majority of patients had reduced values of hemoglobin and hematocrit (8.55 ± 1.33 g/dL and 25.7 ± 4.4%, respectively and increased fetal hemoglobin levels (12 ± 7%. None of the clinical variables was statistically significant on comparing the two groups of patients. Among hematological variables only hemoglobin and hematocrit levels were statistically different between patients treated with hydroxyurea and untreated patients (p-value = 0.005 and p-value = 0.001, respectively. Conclusion: Sickle cell anemia requires treatment and follow-up by a multiprofessional team. A current therapeutic option is hydroxyurea. This drug reduces complications and improves laboratorial parameters of patients. In this study, the use of the drug increased the hemoglobin and hematocrit levels of patients.

Solar hot spots are still hot

International Nuclear Information System (INIS)

Bai, T.

1990-01-01

Longitude distributions of solar flares are not random but show evidence for active zones (or hot spots) where flares are concentrated. According to a previous study, two hot spots in the northern hemisphere, which rotate with a synodic period of about 26.72 days, produced the majority of major flares, during solar cycles 20 and 21. The more prominent of these two hot spots is found to be still active during the rising part of cycle 22, producing the majority of northern hemisphere major flares. The synodic rotation period of this hot spot is 26.727 + or - 0.007 days. There is also evidence for hot spots in the southern hemisphere. Two hot spots separated by 180 deg are found to rotate with a period of 29.407 days, with one of them having persisted in the same locations during cycles 19-22 and the other, during cycles 20-22. 14 refs

Chapter 2. Experimental testing methods of materials under hot working conditions

International Nuclear Information System (INIS)

Rossard, C.

1976-01-01

The deformation under hot working conditions is defined and the purpose of laboratory tests is explained: strength, structure, hot-workability. The concepts of generalized stress strain and strain rate are introduced. These concepts find an interesting application in the equivalence principle. The different testing methods (tension, compression, torsion) and their possibilities are reviewed. The softening mechanisms are recalled: dynamic recovery and recrystallization, static and post-dynamic recrystallization. To explain the possibilities of simulation tests in hot working conditions, some examples are given: the evaluation of the stress-strain relationship (effect of the mechanical and thermal history); the determination of structural behavior (quenching, controled cooling law, decomposition kinetics) [fr

HOT 2015

DEFF Research Database (Denmark)

Hannibal, Sara Stefansen

2016-01-01

HOT samler og formidler 21 literacykyndiges bud på, hvad der er hot, og hvad der bør være hot inden for literacy – og deres begrundelser for disse bud.......HOT samler og formidler 21 literacykyndiges bud på, hvad der er hot, og hvad der bør være hot inden for literacy – og deres begrundelser for disse bud....

Performance analysis of high-concentrated multi-junction solar cells in hot climate

Science.gov (United States)

Ghoneim, Adel A.; Kandil, Kandil M.; Alzanki, Talal H.; Alenezi, Mohammad R.

2018-03-01

Multi-junction concentrator solar cells are a promising technology as they can fulfill the increasing energy demand with renewable sources. Focusing sunlight upon the aperture of multi-junction photovoltaic (PV) cells can generate much greater power densities than conventional PV cells. So, concentrated PV multi-junction solar cells offer a promising way towards achieving minimum cost per kilowatt-hour. However, these cells have many aspects that must be fixed to be feasible for large-scale energy generation. In this work, a model is developed to analyze the impact of various atmospheric factors on concentrator PV performance. A single-diode equivalent circuit model is developed to examine multi-junction cells performance in hot weather conditions, considering the impacts of both temperature and concentration ratio. The impacts of spectral variations of irradiance on annual performance of various high-concentrated photovoltaic (HCPV) panels are examined, adapting spectra simulations using the SMARTS model. Also, the diode shunt resistance neglected in the existing models is considered in the present model. The present results are efficiently validated against measurements from published data to within 2% accuracy. Present predictions show that the single-diode model considering the shunt resistance gives accurate and reliable results. Also, aerosol optical depth (AOD) and air mass are most important atmospheric parameters having a significant impact on HCPV cell performance. In addition, the electrical efficiency (η) is noticed to increase with concentration to a certain concentration degree after which it decreases. Finally, based on the model predictions, let us conclude that the present model could be adapted properly to examine HCPV cells' performance over a broad range of operating conditions.

TWRS tank waste pretreatment process development hot test siting report

International Nuclear Information System (INIS)

Howden, G.F.; Banning, D.L.; Dodd, D.A.; Smith, D.A.; Stevens, P.F.; Hansen, R.I.; Reynolds, B.A.

1995-02-01

This report is the sixth in a series that have assessed the hot testing requirements for TWRS pretreatment process development and identified the hot testing support requirements. This report, based on the previous work, identifies specific hot test work packages, matches those packages to specific hot cell facilities, and provides recommendations of specific facilities to be employed for the pretreatment hot test work. Also identified are serious limitations in the tank waste sample retrieval and handling infrastructure. Recommendations are provided for staged development of 500 mL, 3 L, 25 L and 4000 L sample recovery systems and specific actions to provide those capabilities

Evaluation of options for disposition of dispersible material in B-Cell

International Nuclear Information System (INIS)

Tokarz, R.D.; Defferding, L.J.; Adickes, M.D.; Keene, K.E.; Pilger, J.P.; Alzheimer, J.M.; Paxton, M.M.

1993-10-01

The radioactive contaminants in the dispersible material in B-cell of the 324 Building Radiochemical Energy (RE) hot-cell complex at the Hanford Site in southeastern Washington exceed the allowable level. In 1986, there was a spill of 1.3 million curies of concentrated cesium and strontium in B-cell. Cleanup is required, and candidate technologies for cleaning up or otherwise addressing problems associated with the dispersible material are being evaluated by Pacific Northwest Laboratory (PNL). The RE hot-cell complex in 324 Building was constructed in the late 1950s. From the early 1960s until today the complex has been the site of numerous research, development, and demonstration programs using radioactive and hazardous materials. In mid-FY 1988, a program to clean B-cell was initiated. At present, dispersible material has been collected from 45% of the cell floor area, and 64% of the equipment and support racks have been removed from the cell. The evaluation of decontamination procedures are described

Seismic modifications to the hot suspect repair area Argonne National Laboratory, West

International Nuclear Information System (INIS)

Malik, L.E.; Harris, B.G.

1993-01-01

The ANL-W WIPP Waste Facility Enhancement Project required substantial remodeling and upgrades to the Hot Fuels Examination Facility (HFEF) building, including the Hot and Suspect Repair Area (HSRA). The HSRA is an enclosed single-stoned area inside the HFEF. It is separated into several compartments, some of which are used for handling radioactive materials. The HSRA roof consists of 18 GA steel Robertson Q decking with 1.5 in. concrete topping, and is utilized for storage. Braced steel frames support the HSRA roof, except at the north side, where the steel beams arc connected to the HFEF columns. The HSRA has hollow block masonry perimeter and interior walls. Seismic evaluations concluded that the HSRA did not have a competent seismic force resisting system. The structure was upgraded by decoupling it from the HFEF framing for N/S motions, modifying two existing braced frames, adding a now braced frame that can be removed temporarily during maintenance and strengthening the roof diaphragm by a unique modification consisting of special epoxy grout and steel plates installed over the existing concrete roof

HotRegion: a database of predicted hot spot clusters.

Science.gov (United States)

Cukuroglu, Engin; Gursoy, Attila; Keskin, Ozlem

2012-01-01

Hot spots are energetically important residues at protein interfaces and they are not randomly distributed across the interface but rather clustered. These clustered hot spots form hot regions. Hot regions are important for the stability of protein complexes, as well as providing specificity to binding sites. We propose a database called HotRegion, which provides the hot region information of the interfaces by using predicted hot spot residues, and structural properties of these interface residues such as pair potentials of interface residues, accessible surface area (ASA) and relative ASA values of interface residues of both monomer and complex forms of proteins. Also, the 3D visualization of the interface and interactions among hot spot residues are provided. HotRegion is accessible at http://prism.ccbb.ku.edu.tr/hotregion.

Investigation of a low flow solar heating system for space heating and domestic hot water supply for Aidt Miljø A/S

DEFF Research Database (Denmark)

Vejen, Niels Kristian

1997-01-01

A low flow solar heating system for space heating and domestic hot water supply from Aidt Miljø A/Swas tested in a laboratory test facility.......A low flow solar heating system for space heating and domestic hot water supply from Aidt Miljø A/Swas tested in a laboratory test facility....

Experience of steam generator tube examination in the hot laboratory of EDF: analysis of recent events concerning the secondary side

International Nuclear Information System (INIS)

Thebault, Y.; Bouvier, O. de; Boccanfuso, M.; Coquio, N.; Barbe, V.; Molinie, E.

2011-01-01

Until 2010, more than 60 steam generator (SG) tubes have been removed and analysed in the EDF hot laboratory of CEIDRE/Chinon. This article is particularly related to three recent events that lead to the extraction of several tubes dedicated to laboratory destructive examinations. The first event that constitutes a first occurrence on the EDF Park, concerns the detection of a circumferential crack on the external surface of a tube located at tube support plate elevation. After this observation, several tubes have been extracted from Bugey 3 and Fessenheim 2 nuclear power plants with steam generators equipped with 600 MA bundle. The other two events concern the consequences of chemical cleaning of the tube bundle steam generators. The examples chosen are from Cruas 4 et Chinon B2 units whose tubes were extracted following non destructive testing performed immediately after or at the completion of cycle following the chemical cleaning. In the case of Cruas 4, Eddy Current Testing (ET) were performed for requalification of steam Generators after chemical cleaning. They allowed the detection of an indication located at the bottom of tube for a large number of tubes; the ET signal was similar to that corresponding to 'deposit' corrosion. Moreover, inspections of Chinon-B2 SGs at the end of the operation cycle following the chemical cleaning, showed the presence of conductor deposits at the bottom of some tubes. The first part of this document presents the major results of laboratory examinations of the pulled tubes of Bugey 3 and Fessenheim 2 and their analysis. Hypothesis concerning damage mechanisms of the tubes are also proposed. The second part of the paper relates the results of the laboratory examinations of the pulled tubes of Cruas 4 and Chinon B 2 after chemical cleaning and their analysis. (authors)

Perpendicular electron cyclotron emission from hot electrons in TMX-U

International Nuclear Information System (INIS)

James, R.A.; Ellis, R.F.; Lasnier, C.J.; Casper, T.A.; Celata, C.M.

1984-01-01

Perpendicular electron cyclotron emission (PECE) from the electron cyclotron resonant heating of hot electrons in TMX-U is measured at 30 to 40 and 50 to 75 GHz. This emission is optically thin and is measured at the midplane, f/sub ce/ approx. = 14 GHz, in either end cell. In the west end cell, the emission can be measured at different axial positions thus yielding the temporal history of the hot electron axial profile. These profiles are in excellent agreement with the axial diamagnetic signals. In addition, the PECE signal level correlates well with the diamagnetic signal over a wide range of hot electron densities. Preliminary results from theoretical modeling and comparisons with other diagnostics are also presented

Investigation of a solar heating system for space heating and domestic hot water supply for Sol&Træ A.m.b.a

DEFF Research Database (Denmark)

Vejen, Niels Kristian

1999-01-01

A solar heating system for space heating and domestic hot water supply from "Sol&Træ A.m.b.a." was tested in a laboratory test facility.......A solar heating system for space heating and domestic hot water supply from "Sol&Træ A.m.b.a." was tested in a laboratory test facility....

Specular Reflectivity and Hot-Electron Generation in High-Contrast Relativistic Laser-Plasma Interactions

Energy Technology Data Exchange (ETDEWEB)

Kemp, Gregory Elijah [The Ohio State Univ., Columbus, OH (United States)

2013-01-01

Ultra-intense laser (> 1018 W/cm2) interactions with matter are capable of producing relativistic electrons which have a variety of applications in state-of-the-art scientific and medical research conducted at universities and national laboratories across the world. Control of various aspects of these hot-electron distributions is highly desired to optimize a particular outcome. Hot-electron generation in low-contrast interactions, where significant amounts of under-dense pre-plasma are present, can be plagued by highly non-linear relativistic laser-plasma instabilities and quasi-static magnetic field generation, often resulting in less than desirable and predictable electron source characteristics. High-contrast interactions offer more controlled interactions but often at the cost of overall lower coupling and increased sensitivity to initial target conditions. An experiment studying the differences in hot-electron generation between high and low-contrast pulse interactions with solid density targets was performed on the Titan laser platform at the Jupiter Laser Facility at Lawrence Livermore National Laboratory in Livermore, CA. To date, these hot-electrons generated in the laboratory are not directly observable at the source of the interaction. Instead, indirect studies are performed using state-of-the-art simulations, constrained by the various experimental measurements. These measurements, more-often-than-not, rely on secondary processes generated by the transport of these electrons through the solid density materials which can susceptible to a variety instabilities and target material/geometry effects. Although often neglected in these types of studies, the specularly reflected light can provide invaluable insight as it is directly influenced by the interaction. In this thesis, I address the use of (personally obtained) experimental specular reflectivity measurements to indirectly study hot-electron generation in the context of high-contrast, relativistic

Solid oxide cell R&D at Riso National Laboratory-and its transfer to technology

DEFF Research Database (Denmark)

Linderoth, Søren

2009-01-01

Risø National Laboratory has conducted R&D on solid oxide cells for almost 20 years—all the time together with industries with interest in deploying the technology when mature. Risø National Laboratory (Risø) and Topsoe Fuel Cell A/S (TOFC) have for several years jointly carried out a development...... programme focusing on low cost manufacturing of flat planar anode-supported cells and stacks employing metallic interconnects. The consortium of Risø and TOFC has up-scaled its production capacity of anode-supported cells to about 1,100 per week. New generations of SOFCs are being developed...

Blasting in hot zone - a case study

Energy Technology Data Exchange (ETDEWEB)

Nabiullah, B.M.P.; Pingua, J.; Dhar, B.B. [Central Mining Research Institute, Dhanbad (India)

1997-12-31

A significant quantity of coking coal reserves in the country are under fire particularly in Jharia coalfield. To control the fire and prevent loss of coal, an opencast mining method is adopted. The main problem with these opencast mines is drilling in hot strata and selection of suitable explosives and blasting in the fire zone. Trial blasts were conducted at two open cast mines. The problem was tackled by quenching the hot blast holes with water. Temperature of blast holes were recorded soon after drilling, after quenching with water and just before charging with explosives. The rise in temperature of charged explosives with time was also recorded until blasting. The thermal behaviour of commercially available explosives (including slurry, emulsion, ANFO and detonating cord) was investigated in laboratory and field simulated conditions. Emulsion, slurry compositions and detonating cord were found safe to use in hot holes up to 120{degree}C for duration of two hours. This paper describes the blasting practices adopted in the fire zones. 4 refs., 6 figs., 8 tabs.

An application of Brookhaven National Laboratory's hot particle methodology for determining the most effective beta particle energy in causing skin ulcers

International Nuclear Information System (INIS)

Schaefer, C.

1994-11-01

The purpose of this project was to compare the effectiveness of hot particles with different energy betas in producing ulcers on skin. The sources were man-made hot particles similar in size and activity to those found in the commercial nuclear power industry. Four different particle types were used. These were thulium (Tm-170) with a 0.97 MeV maximum energy beta, ytterbium (Yb-175) with a maximum beta energy of 0.47 MeV, scandium (Sc-46) with a 0.36 MeV beta, which was used as a surrogate for cobalt-60 (0.31 MeV beta) and uranium (in the carbide form) with an average maximum beta energy of about 2.5 MeV. Since higher energy beta particles penetrate further in skin, they will affect a higher number and different populations of target cells. The experiments were designed as threshold studies such that the dose needed to produce ulcers ten percent of the time (ED 10%) for each particle type could be compared against each other

The evolutionary turnover of recombination hot spots contributes to speciation in mice.

Science.gov (United States)

Smagulova, Fatima; Brick, Kevin; Pu, Yongmei; Camerini-Otero, R Daniel; Petukhova, Galina V

2016-02-01

Meiotic recombination is required for the segregation of homologous chromosomes and is essential for fertility. In most mammals, the DNA double-strand breaks (DSBs) that initiate meiotic recombination are directed to a subset of genomic loci (hot spots) by sequence-specific binding of the PRDM9 protein. Rapid evolution of the DNA-binding specificity of PRDM9 and gradual erosion of PRDM9-binding sites by gene conversion will alter the recombination landscape over time. To better understand the evolutionary turnover of recombination hot spots and its consequences, we mapped DSB hot spots in four major subspecies of Mus musculus with different Prdm9 alleles and in their F1 hybrids. We found that hot spot erosion governs the preferential usage of some Prdm9 alleles over others in hybrid mice and increases sequence diversity specifically at hot spots that become active in the hybrids. As crossovers are disfavored at such hot spots, we propose that sequence divergence generated by hot spot turnover may create an impediment for recombination in hybrids, potentially leading to reduced fertility and, eventually, speciation. Published by Cold Spring Harbor Laboratory Press.

Developments in hot-filament metal oxide deposition (HFMOD)

International Nuclear Information System (INIS)

Durrant, Steven F.; Trasferetti, Benedito C.; Scarminio, Jair; Davanzo, Celso U.; Rouxinol, Francisco P.M.; Gelamo, Rogerio V.; Bica de Moraes, Mario A.

2008-01-01

Hot-filament metal oxide deposition (HFMOD) is a variant of conventional hot-filament chemical vapor deposition (HFCVD) recently developed in our laboratory and successfully used to obtain high-quality, uniform films of MO x , WO x and VO x . The method employs the controlled oxidation of a filament of a transition metal heated to 1000 deg. C or more in a rarefied oxygen atmosphere (typically, of about 1 Pa). Metal oxide vapor formed on the surface of the filament is transported a few centimetres to deposit on a suitable substrate. Key system parameters include the choice of filament material and diameter, the applied current and the partial pressures of oxygen in the chamber. Relatively high film deposition rates, such as 31 nm min -1 for MoO x , are obtained. The film stoichiometry depends on the exact deposition conditions. MoO x films, for example, present a mixture of MoO 2 and MoO 3 phases, as revealed by XPS. As determined by Li + intercalation using an electrochemical cell, these films also show a colouration efficiency of 19.5 cm 2 C -1 at a wavelength of 700 nm. MO x and WO x films are promising in applications involving electrochromism and characteristics of their colouring/bleaching cycles are presented. The chemical composition and structure of VO x films examined using IRRAS (infrared reflection-absorption spectroscopy), RBS (Rutherford backscattering spectrometry) and XPS (X-ray photoelectron spectrometry) are also presented

Glucose Transport in Cultured Animal Cells: An Exercise for the Undergraduate Cell Biology Laboratory

Science.gov (United States)

Ledbetter, Mary Lee S.; Lippert, Malcolm J.

2002-01-01

Membrane transport is a fundamental concept that undergraduate students of cell biology understand better with laboratory experience. Formal teaching exercises commonly used to illustrate this concept are unbiological, qualitative, or intricate and time consuming to prepare. We have developed an exercise that uses uptake of radiolabeled nutrient…

Prognostic classification with laboratory parameters or imaging techniques in small-cell lung cancer

NARCIS (Netherlands)

de Jong, Wouter K.; Fidler, Vaclav; Groen, Harry J. M.

PURPOSE: Our aim in this study was to compare prognostic models based on laboratory tests with a model including imaging information in small-cell lung cancer. PATIENTS AND METHODS: A retrospective analysis was performed on 156 consecutive patients. Three existing models based on laboratory tests

Immune changes during whole body hot water immersion: the role of growth hormone.

Science.gov (United States)

Kappel, M; Poulsen, T D; Hansen, M B; Galbo, H; Pedersen, B K

1997-07-01

Studies examined the role of growth hormone, catecholamines, and beta-endorphins in changes in natural killer cell activity, subtypes of blood mononuclear cells, and leukocyte concentration in response to hot water immersion in humans. The response of leukocytes and neutrophils to 2 hours of hot water immersion and simultaneous administration of propranolol, somatostatin, naloxone, or isotonic saline are reported.

Using hot lab to increase pre-service physics teacher’s critical thinking skills related to the topic of RLC circuit

Science.gov (United States)

Malik, A.; Setiawan, A.; Suhandi, A.; Permanasari, A.; Samsudin, A.; Safitri, D.; Lisdiani, S. A. S.; Sapriadil, S.; Hermita, N.

2018-05-01

This research purposes to explore the used of Higher Order Thinking Laboratory (HOT-Lab) in enhancing the critical thinking skills of pre-service teachers related to the topic of Resistors, Inductors, Capacitor (RLC circuit). This study utilised a quasi-experiment method with Pretest-Posttest Control Group design. The sample of the study was 60 students that were divided into two groups covering in experiment and control group, consists of 30 students. The instrument for measuring critical thinking skills is essay test. Data has been analyzed using normalized gain average, effect size, and t-test. The results show that students’ critical thinking skills using the HOT Lab are higher than the verification lab. Using HOT-lab was implemented in the form of activity in the laboratory can improve high-order thinking skills. Hence, it was concluded that the use of HOT Lab had a greater impact on improving students’ critical thinking skills on RLC topic. Finally, HOT Lab can be used for other physics topics.

HOT 2012

DEFF Research Database (Denmark)

Lund, Henriette Romme

Undersøgelse af, hvad der er hot - og hvad der burde være hot på læseområdet med 21 læsekyndige. Undersøgelsen er gennemført siden 2010. HOT-undersøgelsen er foretaget af Nationalt Videncenter for Læsning - Professionshøjskolerne i samarb. med Dansklærerforeningen......Undersøgelse af, hvad der er hot - og hvad der burde være hot på læseområdet med 21 læsekyndige. Undersøgelsen er gennemført siden 2010. HOT-undersøgelsen er foretaget af Nationalt Videncenter for Læsning - Professionshøjskolerne i samarb. med Dansklærerforeningen...

Hot Cell Post-Irradiation Examination and Poolside Inspection of Nuclear Fuel. Proceedings of the IAEA-HOTLAB Technical Meeting

International Nuclear Information System (INIS)

2013-04-01

The growing operational requirements for nuclear fuel, such as longer fuel cycles, higher burnups and wider use of transient regimes, require more robust fuel designs and more radiation resistant materials. Development of such advanced fuels is only possible with testing and analysis of their performance and application of adequate post-irradiation examination (PIE) methods and techniques. In addition, operational feedback data from poolside and PIE facilities are absolutely necessary for verification of fuel modelling codes and analysis of fuel failure mechanisms. For these reasons, the International Atomic Energy Agency (IAEA) has supported the international exchange of knowledge and sharing of best practices in the application of modern destructive and non-destructive methods of investigation of highly radioactive materials through a series of technical meetings (TMs), the last of which was held in 2006 in Buenos Aires. Since 1963, similar meetings, initially at the European level, have been organized by the Hot Laboratories and Remote Handling Working Group (HOTLAB), a partner in the development of the IAEA's Post Irradiation Examination Facilities Database (PIEDB), part of the IAEA's Integrated Nuclear Fuel Cycle Information System. With this successful partnership in mind, in 2010 the IAEA Technical Working Group on Fuel Performance and Technology recommended that a joint IAEA-HOTLAB TM be held on 'Hot Cell Post-Irradiation Examination and Pool-Side Inspection of Nuclear Fuel', covering questions relevant to the IAEA sub-programmes on 'Nuclear Power Reactor Fuel Engineering' and 'Management of Spent Fuel from Nuclear Power Reactors'. The TM was held on 23-27 May 2011, in Smolenice, Slovakia, with the participation of a large number of interested organizations and comprehensive coverage of major PIE and poolside inspection issues relating to both operation and storage of fuel for nuclear power reactors. The proceedings, summaries and conclusions of that joint

Experimental evidence of hot carriers solar cell operation in multi-quantum wells heterostructures

Energy Technology Data Exchange (ETDEWEB)

Rodière, Jean; Lombez, Laurent, E-mail: laurent.lombez@chimie-paristech.fr [IRDEP, Institute of R and D on Photovoltaic Energy, UMR 7174, CNRS-EDF-Chimie ParisTech, 6 Quai Watier-BP 49, 78401 Chatou Cedex (France); Le Corre, Alain; Durand, Olivier [INSA, FOTON-OHM, UMR 6082, F-35708 Rennes (France); Guillemoles, Jean-François [IRDEP, Institute of R and D on Photovoltaic Energy, UMR 7174, CNRS-EDF-Chimie ParisTech, 6 Quai Watier-BP 49, 78401 Chatou Cedex (France); NextPV, LIA CNRS-RCAST/U. Tokyo-U. Bordeaux, 4-6-1 Komaba, Meguro-ku, Tokyo 153-8904 (Japan)

2015-05-04

We investigated a semiconductor heterostructure based on InGaAsP multi quantum wells (QWs) using optical characterizations and demonstrate its potential to work as a hot carrier cell absorber. By analyzing photoluminescence spectra, the quasi Fermi level splitting Δμ and the carrier temperature are quantitatively measured as a function of the excitation power. Moreover, both thermodynamics values are measured at the QWs and the barrier emission energy. High values of Δμ are found for both transition, and high carrier temperature values in the QWs. Remarkably, the quasi Fermi level splitting measured at the barrier energy exceeds the absorption threshold of the QWs. This indicates a working condition beyond the classical Shockley-Queisser limit.

Ceramide-Enriched Membrane Domains in Red Blood Cells and the Mechanism ofSphingomyelinase-Induced Hot-Cold Hemolysis

DEFF Research Database (Denmark)

Montes, Ruth; Lopez, David; Sot, Jesus

2008-01-01

Hot-cold hemolysis is the phenomenon whereby red blood cells, preincubated at 37 °C in the presence of certain agents, undergo rapid hemolysis when transferred to 4 °C. The mechanism of this phenomenon is not understood. PlcHR2, a phospholipase C/sphingomyelinase from Pseudomonas aeruginosa......) but also in goat erythrocytes, which lack PC. However, in horse erythrocytes, with a large proportion of PC and almost no SM, hot-cold hemolysis induced by PlcHR2 is not observed. Fluorescence microscopy observations confirm the formation of ceramide-enriched domains as a result of PlcHR2 activity. After......-cold hemolysis. Differential scanning calorimetry of erytrocyte membranes treated with PlcHR2 demonstrates the presence of ceramide-rich domains that are rigid at 4 °C but fluid at 37 °C. Ceramidase treatment causes the disapperance of the calorimetric signal assigned to ceramide-rich domains. Finally...

Factors affecting the hot-dip zinc coatings structure

International Nuclear Information System (INIS)

Sere, P.R.; Cuclcasi, J.D.; Elsner, C.I.; Sarli, A.R.

1997-01-01

Coating solidification during hot-dip galvanizing is a very complex process due to Al-Fe, Al-Fe-Zn and Fe-Zn intermetallic compounds development . Fe-Zn intermetallics are brittle and detrimental for the coating ductility, while the diffusion towards the surface of a segregated insoluble alloying such as antimonium causes the sheet darkness. Steel of different roughness were hot-dip galvanized under different operation conditions using a laboratory scale simulator. The effect of steel roughness and process parameters upon coating characteristics were analysed. Experimental results showed that the steel roughness affects the coating thickness, zinc grain size and texture as well as the out-bursts development, while the process parameters affects the Fe 2 Al 5 morphology and antimonium segregation. (Author) 11 refs

Progress in hot pressing

International Nuclear Information System (INIS)

Brodhag, C.; Thevenot, F.

1988-01-01

An experimental technique is described to study hot pressing of ceramics under conditions of controlled temperature and pressure during both the heating and final sintering stages. This method gives a better control of the final microstructure of the material. Transformation mechanisms can be studied during initial heating stage (impurity degasing, reaction, phase transformation, mechanical behavior of intergranular phase...) using computer control and graphical data representations. Some examples will be given for different systems studied in our laboratory: B (α, β, amorphous), B 12 O 2 (reaction of B + B 2 O 3 ), Si 3 N 4 ( + additives), TiN, Al 2 O 3 + AlON,ZrC

Seismic modifications to the Hot and Suspect Repair area Argone National Laboratory - West

International Nuclear Information System (INIS)

Malik, L.E.; Harris, B.G.

1993-01-01

The ANL-W WIPP Waste Facility Enhancement Project required substantial remodeling and upgrades to the Hot Fuels Examination Facility (HFEF) building, including the Hot and Suspect Repair Area (HSRA). The HSRA is an enclosed single-storied area inside the HFEF. It is separated into several compartments, some of which are used for handling radioactive materials. The HSRA roof consists of 18 GA steel Robertson Q decking with 1.5 in. concrete topping, and is utilized for storage. Braced steel frames support the HSRA roof, except at the north side, where the steel beams are connected to the HFEF columns. The HSRA has hollow block masonry perimeter and interior walls. Seismic evaluations concluded that the HSRA did not have a competent seismic force resisting system. The structure was upgraded by decoupling it from the HFEF framing for N/S motions, modifying two existing braced frames, adding a new braced frame that can be removed temporarily during maintenance and strengthening the roof diaphragm by a unique modification consisting of special epoxy grout and steel plates installed over the existing concrete roof

Archaeal diversity in Icelandic hot springs

DEFF Research Database (Denmark)

Kvist, Thomas; Ahring, Birgitte Kiær; Westermann, Peter

2007-01-01

Whole-cell density gradient extractions from three solfataras (pH 2.5) ranging in temperature from 81 to 90 degrees C and one neutral hot spring (81 degrees C, pH 7) from the thermal active area of Hveragerethi (Iceland) were analysed for genetic diversity and local geographical variation...... of Archaea by analysis of amplified 16S rRNA genes. In addition to the three solfataras and the neutral hot spring, 10 soil samples in transects of the soil adjacent to the solfataras were analysed using terminal restriction fragment length polymorphism (t-RFLP). The sequence data from the clone libraries...... enzymes AluI and BsuRI. The sequenced clones from this solfatara belonged to Sulfolobales, Thermoproteales or were most closest related to sequences from uncultured Archaea. Sequences related to group I.1b were not found in the neutral hot spring or the hyperthermophilic solfatara (90 degrees C)....

Environmental Assessment for decontaminating and decommissioning the General Atomics Hot Cell Facility. Final [report

International Nuclear Information System (INIS)

1995-08-01

This EA evaluates the proposed action to decontaminate and decommission GA's hot cell facility in northern San Diego, CA. This facility has been used for DOE and commercial nuclear R ampersand D for > 30 years. About 30,000 cubic feet of decontamination debris and up to 50,000 cubic feet of contaminated soil are to be removed. Low-level radioactive waste would be shipped for disposal. It was determined that the proposal does not constitute a major federal action significantly affecting the human environment according to NEPA; therefore, a finding of no significant impact is made, and an environmental impact statement is not required

Environmental Assessment for decontaminating and decommissioning the General Atomics Hot Cell Facility. Final [report

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-08-01

This EA evaluates the proposed action to decontaminate and decommission GA`s hot cell facility in northern San Diego, CA. This facility has been used for DOE and commercial nuclear R&D for > 30 years. About 30,000 cubic feet of decontamination debris and up to 50,000 cubic feet of contaminated soil are to be removed. Low-level radioactive waste would be shipped for disposal. It was determined that the proposal does not constitute a major federal action significantly affecting the human environment according to NEPA; therefore, a finding of no significant impact is made, and an environmental impact statement is not required.

Hot-mix asphalt testing for the South African pavement design method

CSIR Research Space (South Africa)

Anochie-Boateng, Joseph

2010-08-01

Full Text Available of local and international hot-mix asphalt (HMA) test methods and modify or adapt them to suit South African road pavement conditions. This paper presents various laboratory HMA test protocols developed as part of the project to revise SAPDM. Large scale...

Employing Hot Wire Anemometry to Directly Measure the Water Balance in a Proton Exchange membrane Fuel Cell

DEFF Research Database (Denmark)

Shakhshir, Saher Al; Hussain, Nabeel; Berning, Torsten

2015-01-01

Water management in proton exchange membrane fuel cells (PEMFC’s) remains a critical problem for their durability, cost, and performance. Because the anode side of this fuel cell has the tendency to become dehydrated, measuring the water balance can be an important diagnosis tool during fuel cell...... operation. The water balance indicates how much of the product water leaves at the anode side versus the cathode side. Previous methods of determining the fuel cell water balance often relied on condensing the water in the exhaust gas streams and weighing the accumulated mass which is a time consuming...... process that has limited accuracy. Currently, our group is developing a novel method to accurately determine the water balance in a PEMFC in real time by employing hot-wire anemometry. The amount of heat transferred from the wire to the anode exhaust stream can be translated into a voltage signal which...

Pungency Quantitation of Hot Pepper Sauces Using HPLC

Science.gov (United States)

Betts, Thomas A.

1999-02-01

A class of compounds known as capsaicinoids are responsible for the "heat" of hot peppers. To determine the pungency of a particular pepper or pepper product, one may quantify the capsaicinoids and relate those concentrations to the perceived heat. The format of the laboratory described here allows students to collectively develop an HPLC method for the quantitation of the two predominant capsaicinoids (capsaicin and dihydrocapsaicin) in hot-pepper products. Each small group of students investigated one of the following aspects of the method: detector wavelength, mobile-phase composition, extraction of capsaicinoids, calibration, and quantitation. The format of the lab forced students to communicate and cooperate to develop this method. The resulting HPLC method involves extraction with acetonitrile followed by solid-phase extraction clean-up, an isocratic 80:20 methanol-water mobile phase, a 4.6 mm by 25 cm C-18 column, and UV absorbance detection at 284 nm. The method developed by the students was then applied to the quantitation of capsaicinoids in a variety of hot pepper sauces. Editor's Note on Hazards in our April 2000 issue addresses the above.

Hot Flashes

Science.gov (United States)

Hot flashes Overview Hot flashes are sudden feelings of warmth, which are usually most intense over the face, neck and chest. Your skin might redden, as if you're blushing. Hot flashes can also cause sweating, and if you ...

Possibilities and prospects of investigation of irradiated structural and fuel materials using scanning electron microscope PHILLIPS XL 30 ESEM-TMP installed in the hot cell

International Nuclear Information System (INIS)

Golovanov, V. N.; Novoselov, A.E.; Kuzmin, S.V.; Yakovlev, V. V.

2005-01-01

Scanning electron microscope Philips XL 30 ESEM - TMP with X-ray microanalysis system INCA has been installed at SSC RF RIAR. The microscope is placed in the hot cell. Monitoring and control system is installed in the operator's room. Irradiated specimens are supplied to the hot cell through the transport terminal and installed into the microscope by manipulators. Direct contact of the personnel with radioactive materials is impossible. In addition it is developed the system of remote placement of the irradiated specimens into the specimen chamber of microscope. The system includes a stage with three seats, holders for different types of specimens and equipment for their remote loading in the holders. (Author)

Feasibility study of medical isotope production at Sandia National Laboratories

International Nuclear Information System (INIS)

Massey, C.D.; Miller, D.L.; Carson, S.D.

1995-12-01

In late 1994, Sandia National Laboratories in Albuquerque, New Mexico, (SNL/NM), was instructed by the Department of Energy (DOE) Isotope Production and Distribution Program (IPDP) to examine the feasibility of producing medically useful radioisotopes using the Annular Core Research Reactor (ACRR) and the Hot Cell Facility (HCF). Los Alamos National Laboratory (LANL) would be expected to supply the targets to be irradiated in the ACRR. The intent of DOE would be to provide a capability to satisfy the North American health care system demand for 99 Mo, the parent of 99m Tc, in the event of an interruption in the current Canadian supply. 99m Tc is used in 70 to 80% of all nuclear medicine procedures in the US. The goal of the SNL/NM study effort is to determine the physical plant capability, infrastructure, and staffing necessary to meet the North American need for 99 Mo and to identify and examine all issues with potential for environmental impact

Inter-laboratory comparison of cell lines for susceptibility to three viruses: VHSV, IHNV and IPNV

DEFF Research Database (Denmark)

Lorenzen, Ellen; Carstensen, Bendix; Olesen, Niels Jørgen

1999-01-01

Eleven European National Reference Laboratories participated in an inter-laboratory comparison of the susceptibility of 5 selected cell lines to 3 fish pathogenic viruses. The test included viral hemorrhagic septicaemia virus (VHSV), infectious hematopoietic necrosis virus (IHNV) and infectious...... pancreatic necrosis Virus (IPNV), and the cell lines derived from bluegill fry (BF-2), chinook salmon embryo (CHSE-214), epithelioma papulosum cyprini (EPC), fathead minnow (FHM) and rainbow trout gonad (RTG-2). The results showed that for isolation of VHSV, BF-2 and RTG-2 cells performed equally well...

Development of a new miniature short-residence-time annular centrifugal solvent extraction contactor for tests of process flowsheets in hot cells

International Nuclear Information System (INIS)

Lanoe, J.Y.; Rivalier, P.

2000-01-01

Researches undertaken on new nuclear fuel reprocessing extraction processes need tests of process flowsheets in hot cells. To this goal, a new miniature short residence-time annular centrifugal solvent extraction contactor was conceived and developed at Marcoule. This single stage contactor is composed of an outer stationary cylinder (made of transparent plexiglas on prototype and of stainless steel on models for hot cells) and a suspended inner rotating cylinder of stainless steel; the inside diameter of the rotor is 12 mm. Aqueous and organic phases are fed into the gap between the two cylinders. The mixture flows down the annular space and then up through an orifice at the bottom of the rotor. Into the rotor, the emulsion breaks rapidly under the centrifugal force (up to 600 g with rotor speed of 10,000 rpm). The separated phases flow over their weirs and discharge at the top in their collector rings. The liquid hold-up of this centrifugal contactor is approximately 6 mL. The use in hots cells needed original designs for: - the assembly of a single-stage contactor: every part (motor, rotor, stationary housing) is simply inserted on the other one without screws and nuts; - the assembly of multistage group: every stage is stacking in two rails and an intermediate part (supported on the two rails) links exit ports and their corresponding inlet ports. All the parts are pressed and sealed against a terminal plate with a screw. Separating capacity tests with. a prototype were conducted using water as the aqueous phase and hydrogenated tetra-propylene (TPH) as the organic phase with aqueous to organic (A/O) flow ratio equal to 1. The best performances were obtained with rotor speed ranging from 4000 to 5000 rpm; the total throughput was then up to 2 L.h -1 . For a total throughput of 300 mL.h -1 , the hold-up in the annular mixing zone varied from 0.5 to 1.5 mL according to the A/O ratio and the starting mode. A number of tests were also performed to measure the

The reliability improvement plan of hot cell examination data by introducing of Kolas

International Nuclear Information System (INIS)

Hong, Kwon Pyo; Park, Dae Gyu; Ahn, Sang Bok; Choo, Yong Sun; Song, Wung Sup; Jung, Yang Hong; Yoo, Byung Ok; Baik, Seung Je; Lim, Nam Jin; Nam Ju Hee

2000-01-01

For enhancement of hot cell data reliability produced at Irradiated Material Examination Facility in KAERI,Korea a project to introduce Kolas of National Quality Assurance Institute. By Kolas introduction the examination data currently produced would be reinforced by additional function of uncertainty evaluation and would obtained more reliable data. The all of data collected would be quality controlled, so that it would be re-traceable. Presently at IMEF shock test, tension test, dimension measurement test, hardness test, density test, and composition analysis test will be subject to Kolas. It is also planned to expand the number of test items in near future. At the end of 2000 year IMEF aims to secure the certificate issued by the National Quality Assurance Institute. (Hong, J. S.)

Small-scale hot facility for reprocessing and alpha research

International Nuclear Information System (INIS)

Abdel-Rassoul, A.A.

1976-01-01

The experimental hot facility at Inchas is planned for research activities related to the decontamination of radioactive wastes, analytical chemistry of alpha emitters and chemical treatment of spent UO 2 -Mg fuel samples. The design concept permits safe handling of source materials with radioactivity levels up to 10000Ci. The laboratory includes a reception area, process hall, a number of research laboratories and other facilities for chemical and physical analysis, nuclear measurements and health physics control. The radioactive waste management plant allows for control and decontamination of intermediate- and low-level laboratory effluents. Fixation of radioactive residues will be carried out in the sludge immobilization plant. High-level fission-product waste liquors are subject to preconcentration and transformation to a glassy matrix before ultimate storage. (author)

Developments in hot-filament metal oxide deposition (HFMOD)

Energy Technology Data Exchange (ETDEWEB)

Durrant, Steven F. [Laboratorio de Plasmas Tecnologicos, Campus Experimental de Sorocaba, Universidade Estadual Paulista (UNESP), Avenida Tres de Marco, 511, Alto de Boa Vista, 18087-180 Sorocaba, SP (Brazil)], E-mail: steve@sorocaba.unesp.br; Trasferetti, Benedito C. [Departamento de Policia Federal, Superintendencia Regional no Piaui, Setor Tecnico-Cientifico, Avenida Maranhao, 1022/N, 64.000-010, Teresina, PI (Brazil); Scarminio, Jair [Departamento de Fisica, Universidade Estadual de Londrina (UEL), 86051-990, Londrina, PR (Brazil); Davanzo, Celso U. [Instituto de Quimica, Universidade Estadual de Campinas (UNICAMP), 13083-970, Campinas, SP (Brazil); Rouxinol, Francisco P.M.; Gelamo, Rogerio V.; Bica de Moraes, Mario A. [Laboratorio de Processos de Plasma, Departamento de Fisica Aplicada, Instituto de Fisica Gleb Wataghin, Universidade Estadual de Campinas (UNICAMP), 13083-970, Campinas, SP (Brazil)

2008-01-15

Hot-filament metal oxide deposition (HFMOD) is a variant of conventional hot-filament chemical vapor deposition (HFCVD) recently developed in our laboratory and successfully used to obtain high-quality, uniform films of MO{sub x}, WO{sub x} and VO{sub x}. The method employs the controlled oxidation of a filament of a transition metal heated to 1000 deg. C or more in a rarefied oxygen atmosphere (typically, of about 1 Pa). Metal oxide vapor formed on the surface of the filament is transported a few centimetres to deposit on a suitable substrate. Key system parameters include the choice of filament material and diameter, the applied current and the partial pressures of oxygen in the chamber. Relatively high film deposition rates, such as 31 nm min{sup -1} for MoO{sub x}, are obtained. The film stoichiometry depends on the exact deposition conditions. MoO{sub x} films, for example, present a mixture of MoO{sub 2} and MoO{sub 3} phases, as revealed by XPS. As determined by Li{sup +} intercalation using an electrochemical cell, these films also show a colouration efficiency of 19.5 cm{sup 2} C{sup -1} at a wavelength of 700 nm. MO{sub x} and WO{sub x} films are promising in applications involving electrochromism and characteristics of their colouring/bleaching cycles are presented. The chemical composition and structure of VO{sub x} films examined using IRRAS (infrared reflection-absorption spectroscopy), RBS (Rutherford backscattering spectrometry) and XPS (X-ray photoelectron spectrometry) are also presented.

Research and design of module supporting and rotary device in hot cell

International Nuclear Information System (INIS)

Wu Wenguang; Song Changfei; Chen Mingchi

2013-01-01

Background: This paper introduced a device for tandem accelerator project, designed for the radioactive target source module maintaining and testing. Purpose: The module is required to be lifting, rotary and precise orientation in technology. Methods: We designed the structure of rotary drum, supporting drum and screw lifting device to achieve the function. In circumference, we adopt the project with electro-motion cursory locate, hand-motion precise locate, sensor location detect and cylinder locate pin, the measure is safe and trustiness. Results: Via experimentation, all technology targets are fulfilled, and the rationality and reliability of the device has been validated. Conclusions: The successful development of this device provides a good direction and reference for radioactive areas such as accelerator, hot cell, reactor etc., and can be adapted to its capability of long-distance shield operating, maintaining or testing. (authors)

HOT 2011

DEFF Research Database (Denmark)

Lund, Henriette Romme

En undersøgelse af, hvad der er hot - og burde være hot på læseområdet. I undersøgelsen deltager 21 læsekyndige fra praksisfeltet, professionshøjskolerne og forskningsområdet.......En undersøgelse af, hvad der er hot - og burde være hot på læseområdet. I undersøgelsen deltager 21 læsekyndige fra praksisfeltet, professionshøjskolerne og forskningsområdet....

PIE technology on mechanical tests for HTTR core component and structural materials developed at Research Hot Laboratory

International Nuclear Information System (INIS)

Kizaki, Minoru; Honda, Junichi; Usami, Kouji; Ouchi, Asao; Oeda, Etsuro; Matsumoto, Seiichiro

2001-02-01

The high temperature engineering test reactor (HTTR) with the target operation temperature of 950degC established the first criticality on November, 1998 based on a large amount of R and D results on fuel and materials. In such R and D works, the development of reactor materials are one of the key issues from the view point of reactor environments such as extremely high temperature, neutron irradiation and so on for the HTTR. The Research Hot Laboratory (RHL) had carried out much kind of post irradiation examinations (PIEs) on core component and pressure vessel materials for during more than a quarter century. And obtained data played an important role in development, characterization and licensing of those materials for the HTTR. This paper describes the PIE technology developed at RHL and typical results on mechanical tests such as elevated temperature tensile and creep rupture tests for Hasteloy-X, Incolloy 800H and so on, and Charpy impact, J IC fracture toughness, K Id fracture toughness and small punch tests for normalized and tempered 2 1/4Cr-1Mo steel from historical view. In addition, an electrochemical test technique established for investigating the irradiation embrittlement mechanism on 2 1/4Cr-1Mo steel is also mentioned. (author)

Impacts of Implosion Asymmetry And Hot Spot Shape On Ignition Capsules

Science.gov (United States)

Cheng, Baolian; Kwan, Thomas J. T.; Wang, Yi-Ming; Yi, S. Austin; Batha, Steve

2017-10-01

Implosion symmetry plays a critical role in achieving high areal density and internal energy at stagnation during hot spot formation in ICF capsules. Asymmetry causes hot spot irregularity and stagnation de-synchronization that results in lower temperatures and areal densities of the hot fuel. These degradations significantly affect the alpha heating process in the DT fuel as well as on the thermonuclear performance of the capsules. In this work, we explore the physical factors determining the shape of the hot spot late in the implosion and the effects of shape on Î+/-particle transport. We extend our ignition theory [1-4] to include the hot spot shape and quantify the effects of the implosion asymmetry on both the ignition criterion and capsule performance. We validate our theory with the NIF existing experimental data Our theory shows that the ignition criterion becomes more restrictive with the deformation of the hot spot. Through comparison with the NIF data, we demonstrate that the shape effects on the capsules' performance become more explicit as the self-heating and yield of the capsules increases. The degradation of the thermonuclear burn by the hot spot shape for high yield shots to date can be as high as 20%. Our theory is in good agreement with the NIF data. This work was performed under the auspices of the U.S. Department of Energy by the Los Alamos National Laboratory under Contract No. W-7405-ENG-36.

Solar Hot Water Heater

Science.gov (United States)

1978-01-01

The solar panels pictured below, mounted on a Moscow, Idaho home, are part of a domestic hot water heating system capable of providing up to 100 percent of home or small business hot water needs. Produced by Lennox Industries Inc., Marshalltown, Iowa, the panels are commercial versions of a collector co-developed by NASA. In an effort to conserve energy, NASA has installed solar collectors at a number of its own facilities and is conducting research to develop the most efficient systems. Lewis Research Center teamed with Honeywell Inc., Minneapolis, Minnesota to develop the flat plate collector shown. Key to the collector's efficiency is black chrome coating on the plate developed for use on spacecraft solar cells, the coating prevents sun heat from "reradiating," or escaping outward. The design proved the most effective heat absorber among 23 different types of collectors evaluated in a Lewis test program. The Lennox solar domestic hot water heating system has three main components: the array of collectors, a "solar module" (blue unit pictured) and a conventional water heater. A fluid-ethylene glycol and water-is circulated through the collectors to absorb solar heat. The fluid is then piped to a double-walled jacket around a water tank within the solar module.

Effects of Hot-Spot Geometry on Backscattering and Down-Scattering Neutron Spectra

Science.gov (United States)

Mohamed, Z. L.; Mannion, O. M.; Forrest, C. J.; Knauer, J. P.; Anderson, K. S.; Radha, P. B.

2017-10-01

The measured neutron spectrum produced by a fusion experiment plays a key role in inferring observable quantities. One important observable is the areal density of an implosion, which is inferred by measuring the scattering of neutrons. This project seeks to use particle-transport simulations to model the effects of hot-spot geometry on backscattering and down-scattering neutron spectra along different lines of sight. Implosions similar to those conducted at the Laboratory of Laser Energetics are modeled by neutron transport through a DT plasma and a DT ice shell using the particle transport codes MCNP and IRIS. Effects of hot-spot geometry are obtained by ``detecting'' scattered neutrons along different lines of sight. This process is repeated for various hot-spot geometries representing known shape distortions between the hot spot and the shell. This material is based upon work supported by the Department of Energy National Nuclear Security Administration under Award Number DE-NA0001944.

Importance of Electrode Hot-Pressing Conditions for the Catalyst Performance of Proton Exchange Membrane Fuel Cells

DEFF Research Database (Denmark)

Andersen, Shuang Ma; Dhiman, Rajnish; Larsen, Mikkel Juul

2015-01-01

The catalyst performance in a proton exchange membrane fuel cell (PEMFC) depends on not only the choice of materials, but also on the electrode structure and in particular on the interface between the components. In this work, we demonstrate that the hot-pressing conditions used during electrode...... lamination have a great influence on the catalyst properties of a low-temperature PEMFC, especially on its durability. Lamination pressure, temperature and duration were systematically studied in relation to the electrochemical surface area, platinum dissolution, platinum particle size and electrode surface...

Effects of sulphuric acid and hot water treatments on seed ...

African Journals Online (AJOL)

A study was carried out to investigate the effects of sulphuric acid and hot water treatments on the germination of Tamarind (Tamarindus indica L). Seeds were placed on moistened filter papers in 28 cm diameter Petri dishes under laboratory condition for germination. 330 seeds of T. indica (10 seeds per Petri dish) with ...

Solid Oxide Fuel Cell Development at Topsoe Fuel Cell A/S and Risø National Laboratory

DEFF Research Database (Denmark)

Christiansen, Niels; Hansen, J B.; Larsen, H H.

2007-01-01

The consortium of Topsoe Fuel Cell A/S and Riso National Laboratory has up-scaled its production capacity of anode-supported cells to about 1100 per week. Stacks are based on a compact thin plate multilayer design with metallic interconnects and 12x12 cm(2) or 18x18 cm(2) foot print. Larger (500 ...... to include ethanol and coal syngas by development of a new coke resistant catalyst suitable for future SOFC technology....

Characterization report for Building 301 Hot Cell Facility

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-07-01

During the period from October, 1997, through March, 1998, ANL-E Health Physics conducted a pre-D and D characterization of Building 301, referred to as the Hot Cell Facility. While primary emphasis was placed on radiological evaluation, the presence of non-nuclear hazardous and toxic material was also included in the scope of the characterization. This is one of the early buildings on the ANL-E site, and was heavily used in the 1950`s and 1960`s for various nuclear reaction and reactor design studies. Some degree of cleanup and contamination fixation was done in the 1970`s, so that the building could be used with a minimum of risk of personnel contamination. Work records are largely nonexistent for the early history of the building, so that any assumptions about extent and type of contamination had to be kept very open in the survey planning process. The primary contaminant was found to be painted-over Cs-137 embedded in the concrete floors, although a variety of other nuclides consistent with the work said to have been performed were found in smaller quantities. Due to leaks and drips through the floor, a relatively modest amount of soil contamination was found in the service trench under the building, not penetrating deeply. Two contaminated, disconnected drain lines leaving the building could not be traced by site records, and remain a problem for remediation. The D and D Characterization Plan was fulfilled.

Characterization report for Building 301 Hot Cell Facility

International Nuclear Information System (INIS)

1998-07-01

During the period from October, 1997, through March, 1998, ANL-E Health Physics conducted a pre-D and D characterization of Building 301, referred to as the Hot Cell Facility. While primary emphasis was placed on radiological evaluation, the presence of non-nuclear hazardous and toxic material was also included in the scope of the characterization. This is one of the early buildings on the ANL-E site, and was heavily used in the 1950's and 1960's for various nuclear reaction and reactor design studies. Some degree of cleanup and contamination fixation was done in the 1970's, so that the building could be used with a minimum of risk of personnel contamination. Work records are largely nonexistent for the early history of the building, so that any assumptions about extent and type of contamination had to be kept very open in the survey planning process. The primary contaminant was found to be painted-over Cs-137 embedded in the concrete floors, although a variety of other nuclides consistent with the work said to have been performed were found in smaller quantities. Due to leaks and drips through the floor, a relatively modest amount of soil contamination was found in the service trench under the building, not penetrating deeply. Two contaminated, disconnected drain lines leaving the building could not be traced by site records, and remain a problem for remediation. The D and D Characterization Plan was fulfilled

Murine leukemia virus vector integration favors promoter regions and regional hot spots in a human T-cell line

International Nuclear Information System (INIS)

Tsukahara, Tomonori; Agawa, Hideyuki; Matsumoto, Sayori; Matsuda, Mizuho; Ueno, Shuichi; Yamashita, Yuki; Yamada, Koichiro; Tanaka, Nobuyuki; Kojima, Katsuhiko; Takeshita, Toshikazu

2006-01-01

Genomic analysis of integration will be important in evaluating the safety of human gene therapy with retroviral vectors. Here, we investigated MLV vector integration sites in human T-cells, since they are amenable to gene transfer studies, and have been used therapeutically in clinical trials. We mapped 340 MLV vector integration sites in the infected human T-cell clones we established. The data showed that MLV preferred integration near the transcription start sites (±5 kb), near CpG islands (±1 kb), and within the first intron of RefSeq genes. We also identified MLV integration hot spots that contained three or more integrations within a 100 kb region. RT-PCR revealed that mRNA-levels of T-cell clones that contained MLV integrations near transcription start sites or introns were dysregulated compared to the uninfected cells. These studies help define the profile of MLV integration in T-cells and the risks associated with MLV-based gene therapy

Hot cell works and related irradiation tests in fission reactor for development of new materials for nuclear application

International Nuclear Information System (INIS)

Shikama, Tatsuo

1999-01-01

Present status of research works in Oarai Branch, Institute for Materials Research, Tohoku University, utilizing Japan Materials Testing Reactor and related hot cells will be described.Topics are mainly related with nuclear materials studies, excluding fissile materials, which is mainly aiming for development of materials for advanced nuclear systems such as a nuclear fusion reactor. Conflict between traditional and routined procedures and new demands will be described and future perspective is discussed. (author)

Laboratory investigation of fire protection coatings for creosote-treated timber railroad bridges

Science.gov (United States)

Carol A. Clausen; Robert H. White; James P. Wacker; Stan T. Lebow; Mark A. Dietenberger; Samuel L. Zelinka; Nicole M. Stark

2014-01-01

As the incidence of timber railroad bridge fires increases, so has the need to develop protective measures to reduce the risk from accidental ignitions primarily caused by hot metal objects. Of the six barrier treatments evaluated in the laboratory for their ability to protect timbers from fires sourced with ignition from hot metal objects only one intumescent coating...

Cell Migration Analysis: A Low-Cost Laboratory Experiment for Cell and Developmental Biology Courses Using Keratocytes from Fish Scales

Science.gov (United States)

Prieto, Daniel; Aparicio, Gonzalo; Sotelo-Silveira, Jose R.

2017-01-01

Cell and developmental processes are complex, and profoundly dependent on spatial relationships that change over time. Innovative educational or teaching strategies are always needed to foster deep comprehension of these processes and their dynamic features. However, laboratory exercises in cell and developmental biology at the undergraduate level…

Learning Experience on Transformer Using HOT Lab for Pre-service Physics Teacher’s

Science.gov (United States)

Malik, A.; Setiawan, A.; Suhandi, A.; Permanasari, A.

2017-09-01

This study aimed at investigating pre-service teacher’s critical thinking skills improvement through Higher Order Thinking (HOT) Lab on transformer learning. This research used mix method with the embedded experimental model. Research subjects are 60 students of Physics Education in UIN Sunan Gunung Djati Bandung. The results showed that based on the results of the analysis of practical reports and observation sheet shows students in the experimental group was better in carrying out the practicum and can solve the real problem while the control group was going on the opposite. The critical thinking skills of students applying the HOT Lab were higher than the verification lab. Critical thinking skills could increase due to HOT Lab based problems solving that can develop higher order thinking skills through laboratory activities. Therefore, it was concluded that the application of HOT Lab was more effective than verification lab on improving students’ thinking skills on transformer topic learning. Finally, HOT Lab can be implemented in other subject learning and could be used to improve another higher order thinking skills.

Action Memorandum for Decommissioning of TAN-607 Hot Shop Area

Energy Technology Data Exchange (ETDEWEB)

M. A. Pinzel

2007-05-01

The Department of Energy is documenting the selection of an alternative for the TAN-607 Hot Shop Area using a Comprehensive Environmental Response, Compensation, and Liability Act non-time-critical removal action (NTCRA). The scope of the removal action is limited to TAN-607 Hot Shop Area. An engineering evaluation/cost analysis (EE/CA) has assisted the Department of Energy Idaho Operations Office in identifuomg the most effective method for performing the decommissioning of this structure whose mission has ended. TAN-607 Hot Shop Area is located at Test Area North Technical Support Facility within the Idaho National Laboratory Site. The selected alternative consists of demolishing the TAN-607 aboveground structures and components, removing belowground noninert components (e.g. wood products), and removing the radiologically contaminated debris that does not meet remedial action objectives (RAOs), as defined in the Record of Decision Amendment for the V-Tanks and Explanation of Significant Differences for the PM-2A Tanks at Test Area North, Operable Unit 1-10.

HOT 2014

DEFF Research Database (Denmark)

Lund, Henriette

Undersøgelse af, hvad der er hot - og hvad der burde være hot på læseområdet med 21 læsekyndige. Undersøgelsen er gennemført siden 2010. HOT-undersøgelsen er foretaget af Nationalt Videncenter for Læsning - Professionshøjskolerne i samarb. med Dansklærerforeningen...

Management of hot cell waste in Atalante Facilities (abstract and presentation slides)

International Nuclear Information System (INIS)

Dancausse, Jean-Philippe; Ferlay, Gilles; Eysseric, Catherine

2005-01-01

In solution R and D experiments on nuclear fuel from dissolution to liquid extraction lead to produce a large set of wastes. This paper present how these highly contaminated solid and liquid wastes is managed in Hot Cells and in Atalante. Firstly, an inventory of several types of generated wastes is made: 1) Solid wastes. 2) Glass reactors and liquid solution containers. 3) Plastic and Teflon materials for sampling, Highly corrosive solutions. 4) Metallic containers for solid storage like fuels, crucibles. 5) Miscellaneous mixed solid materials. 6) Liquid wastes. 7) Rinsing liquids. 8) Highly corrosive waste containing fluorhydric acid. 9) Analytical solution with sulphate ions. 10) Organic solvent coming from liquid-liquid extraction. A focus will be made on optimised treatment of 1) solid wastes: Mechanically and chemically 2) liquid wastes containing sulphate ions and hydrogen fluoride, 3) organic liquid waste: to remove activity before hydrothermal oxidation. (Author)

Treatment of concrete bars from the dismantling of hot cells

International Nuclear Information System (INIS)

Graf, A.; Stutz, U.; Valencia, L.

2002-01-01

The Central Decontamination Operations Department (HDB) of the Karlsruhe Research Center operates facilities for the disposal of radioactive waste. In general, their objective is to decontaminate radioactive residues for unrestricted release in order to minimize the volume of waste products suitable for repository storage. In the case of about 120 concrete bars from the dismantling of hot cells, we reduce the volume of radioactive waste by sawing off the most contaminated parts of the bar. If there are no insertions such as cables or ventilation systems, the rest of the bar is sandblasted and its activity manually measured to ensure compliance with the release criteria. Otherwise, the bar is minced into small pieces by a power shovel. Afterwards, the rubble is filled into drums and its activity is measured by the clearance measurement facility. If the rubble and the sandblasted bars do not exceed the activity limit specified by the release criteria, the material is disposed of without further regulations for unrestricted use. Those parts of the bars which can not be released must be stored in special containers suitable for the KONRAD final disposal. Using this method, about 70 % of the total mass can be released. (author)

Analytical Chemistry Laboratory (ACL) procedure compendium

International Nuclear Information System (INIS)

1993-01-01

This volume contains the interim change notice for the safety operation procedure for hot cell. It covers the master-slave manipulators, dry waste removal, cell transfers, hoists, cask handling, liquid waste system, and physical characterization of fluids

A new stack effluent monitoring system at the Risoe Hot Cell plant

International Nuclear Information System (INIS)

Boetter-Jensen, L.; Hedemann Jensen, P.; Lauridsen, B.

1984-06-01

This report describes a new stack effluent monitoring system that has been installed at the Hot Cell facility. It is an integrating iodine/particulate system consisting of a γ-shielded flow house in which a continous air sample from the ventilation channel ia sucked through coal and glass filter papers. Activity is accumulated on the filter papers and a thin plastic scintillator detects the β-radiation from the trapped iodine or particulate activity. The stack effluent monitoring system has a two-step regulating function as applied to the ventilation system, first switching it to a recirculating mode, and finally to building-seal after given releases of 131 I. The collection efficiency for iodine in form of elementary iodine (I 2 ) and methyliodide (CH 3 I) has been determined experimentally. The unwanted response from a noble gas release has also been determined from experiments. The noble gas response was determined from puff releases of the nuclide 41 Ar in the concrete cells. It is concluded that the iodine/particulate system is extremely sensitive and that it can easily detect iodine or particulate releases as low as a few MBq. A gamma monitor placed in connection with the iodine/particulate system detects Xe/Kr-releases as low as a few tens of MBq per second. (author)

Criticality safety training at the Hot Fuel Examination Facility

International Nuclear Information System (INIS)

Garcia, A.S.; Courtney, J.C.; Thelen, V.N.

1983-01-01

HFEF comprises four hot cells and out-of-cell support facilities for the US breeder program. The HFEF criticality safety program includes training in the basic theory of criticality and in specific criticality hazard control rules that apply to HFEF. A professional staff-member oversees the implementation of the criticality prevention program

HOT 2010

DEFF Research Database (Denmark)

Lund, Henriette Romme

En undersøgelse af, hvad der er hot - og burde være hot på læseområdet. I undersøgelsen deltager en række læsekyndige fra praksisfeltet, professionshøjskolerne og forskningsområdet. Undersøgelsen er gentaget hvert år siden 2010.......En undersøgelse af, hvad der er hot - og burde være hot på læseområdet. I undersøgelsen deltager en række læsekyndige fra praksisfeltet, professionshøjskolerne og forskningsområdet. Undersøgelsen er gentaget hvert år siden 2010....

HOT 2013

DEFF Research Database (Denmark)

Lund, Henriette Romme

En undersøgelse af, hvad der er hot - og burde være hot på læseområdet. I undersøgelsen deltager en række læsekyndige fra praksisfeltet, professionshøjskolerne og forskningsområdet. Undersøgelsen er gentaget hvert år siden 2010.......En undersøgelse af, hvad der er hot - og burde være hot på læseområdet. I undersøgelsen deltager en række læsekyndige fra praksisfeltet, professionshøjskolerne og forskningsområdet. Undersøgelsen er gentaget hvert år siden 2010....

Suppression of sawtooth oscillations due to hot electrons and hot ions

International Nuclear Information System (INIS)

Zhang, Y.Z.; Berk, H.L.

1989-01-01

The theory of m = 1 kink mode stabilization is discussed in the presence of either magnetically trapped hot electrons or hot ions. For instability hot ion requires particles peaked inside the q = 1 surface, while hot electrons require that its pressure profile be increasing at the q = 1 surface. Experimentally observed sawtooth stabilization usually occurs with off-axis heating with ECRH and near axis heating with ICRH. Such heating may produce the magnetically trapped hot particle pressure profiles that are consistent with theory. 17 refs., 2 figs

Robot Work Platform for Large Hot Cell Deactivation

International Nuclear Information System (INIS)

BITTEN, E.J.

2000-01-01

The 324 Building, located at the Hanford Site near Richland, Washington, is being deactivated to meet state and federal cleanup commitments. The facility is currently in its third year of a nine-year project to complete deactivation and closure for long-term surveillance and maintenance. The 324 building contains large hot cells that were used for high-radiation, high-contamination chemical process development and demonstrations. A major obstacle for the 324 deactivation project is the inability to effectively perform deactivation tasks within highly radioactive, contaminated environments. Current strategies use inefficient, resource intensive technologies that significantly impact the cost and schedule for deactivation. To meet mandated cleanup commitments, there is a need to deploy rapid, more efficient remote/robot technologies to minimize worker exposure, accelerate work tasks, and eliminate the need for multiple specialized tool design and procurement efforts. This paper describes the functions and performance requirements for a crane-deployed remote/robot Work Platform possessing full access capabilities. The remote/robot Work Platform will deploy commercially available off-the-shelf tools and end effectors to support Project cleanup goals and reduce overall project risk and cost. The intent of this system is to maximize the use of off-the-shelf technologies that minimize additional new, unproven, or novel designs. This paper further describes procurement strategy, the selection process, the selected technology, and the current status of the procurement and lessons learned. Funding, in part, has been provided by the US Department of Energy, Office of Science and Technology, Deactivation and Decommissioning Focus Area

NuSTAR observations of WISE J1036+0449, a galaxy at z ∼ 1 obscured by hot dust

DEFF Research Database (Denmark)

Ricci, C.; Assef, R. J.; Stern, D.

2017-01-01

Hot dust-obscured galaxies (hot DOGs), selected from Wide-Field Infrared Survey Explorer’s all-sky infrared survey, host some of the most powerful active galactic nuclei known and may represent an important stage in the evolution of galaxies. Most known hot DOGs are located at z > 1.5, due in part...... to a strong bias against identifying them at lower redshift related to the selection criteria. We present a new selection method that identifies 153 hot DOG candidates at z ~ 1, where they are significantly brighter and easier to study. We validate this approach by measuring a redshift z = 1.009 and finding...... the mid-infrared/X-ray correlation. We also find that other hot DOGs observed by X-ray facilities show a similar deficiency of X-ray flux. We discuss the origin of the X-ray weakness and the absorption properties of hot DOGs. Hot DOGs at z ≲ 1 could be excellent laboratories to probe the characteristics...

Hot tearing susceptibility of binary Mg–Y alloy castings

International Nuclear Information System (INIS)

Wang, Zhi; Huang, Yuanding; Srinivasan, Amirthalingam; Liu, Zheng; Beckmann, Felix; Kainer, Karl Ulrich; Hort, Norbert

2013-01-01

Highlights: ► Quantitatively and qualitatively assessing hot tearing susceptibility for different alloys. ► Monitoring the hot tearing propagation process. ► Detecting the hot tearing initiation/onset temperature. ► Recording the stress and strain evolution during the casting solidification and the subsequent cooling. - Abstract: The influence of Y content on the hot tearing susceptibility (HTS) of binary Mg–Y alloys has been predicted using thermodynamic calculations based on Clyne and Davies model. The calculated results are compared with experimental results determined using a constrained rod casting (CRC) apparatus with a load cell and data acquisition system. Both thermodynamic calculations and experimental measurements indicate that the hot tearing susceptibility as a function of Y content follows the “λ” shape. The experimental results show that HTS first increases with increase in Y content, reaches the maximum at about 0.9 wt.%Y and then decreases with further increase the Y content. The maximum susceptibility observed in Mg–0.9 wt.%Y alloy is attributed to its coarsened columnar microstructure, large solidification range and small amount of eutectic at the time of hot tearing. The initiation of hot cracks is monitored during CRC experiments. It corresponds to a drop in load increment on the force curves. The critical solid fractions at which the hot cracks are initiated are in the range from 0.9 to 0.99. It is also found that it decreases with increasing the content of Y. The hot cracks propagate along the dendritic or grain boundaries through the interdendritic separation or tearing of interconnected dendrites. Some of the formed cracks are possible to be healed by the subsequent refilling of the remained liquids

Exosomes surf on filopodia to enter cells at endocytic hot spots, traffic within endosomes, and are targeted to the ER.

Science.gov (United States)

Heusermann, Wolf; Hean, Justin; Trojer, Dominic; Steib, Emmanuelle; von Bueren, Stefan; Graff-Meyer, Alexandra; Genoud, Christel; Martin, Katrin; Pizzato, Nicolas; Voshol, Johannes; Morrissey, David V; Andaloussi, Samir E L; Wood, Matthew J; Meisner-Kober, Nicole C

2016-04-25

Exosomes are nanovesicles released by virtually all cells, which act as intercellular messengers by transfer of protein, lipid, and RNA cargo. Their quantitative efficiency, routes of cell uptake, and subcellular fate within recipient cells remain elusive. We quantitatively characterize exosome cell uptake, which saturates with dose and time and reaches near 100% transduction efficiency at picomolar concentrations. Highly reminiscent of pathogenic bacteria and viruses, exosomes are recruited as single vesicles to the cell body by surfing on filopodia as well as filopodia grabbing and pulling motions to reach endocytic hot spots at the filopodial base. After internalization, exosomes shuttle within endocytic vesicles to scan the endoplasmic reticulum before being sorted into the lysosome as their final intracellular destination. Our data quantify and explain the efficiency of exosome internalization by recipient cells, establish a new parallel between exosome and virus host cell interaction, and suggest unanticipated routes of subcellular cargo delivery. © 2016 Heusermann et al.

Enhancing pre-service physics teachers' creative thinking skills through HOT lab design

Science.gov (United States)

Malik, Adam; Setiawan, Agus; Suhandi, Andi; Permanasari, Anna

2017-08-01

A research on the implementation of HOT (Higher Order Thinking) Laboratory has been carried out. This research is aimed to compare increasing of creative thinking skills of pre-service physics teachers who receive physics lesson with HOT Lab and with verification lab for the topic of electric circuit. This research used a quasi-experiment methods with control group pretest-posttest design. The subject of the research is 40 Physics Education pre-service physics teachers of UIN Sunan Gunung Djati Bandung. Research samples were selected by class random sampling technique. Data on pre-service physics teachers' creative thinking skills were collected using test of creative thinking skills in the form of essay. The results of the research reveal that average of N-gain of creative thinking skills are for pre-service physics teachers who received lesson with HOT Lab design and for pre-service physics teachers who received lesson with verification lab, respectively. Therefore, we conclude that application of HOT Lab design is more effective to increase creative thinking skills in the lesson of electric circuit.

The evolution of hot-stage microscopy to aid solid-state characterizations of pharmaceutical solids

International Nuclear Information System (INIS)

Vitez, I.M.; Davidovich, M.; Newman, A.W.; Kiesnowski, C.

1998-01-01

A variety of techniques can be used to characterize the physical properties of pharmaceutical solids, including thermal analysis, hot-stage microscopy, X-ray powder diffraction, spectroscopic and micromeritic analysis. Comprehensive characterizations of the physical properties of pharmaceutical solids require a multi-disciplinary approach, since no single technique is capable of characterizing the materials completely.The combination of traditional hot-stage microscopy with new technologies such as high-resolution micrography, image capture, storage manipulation, and presentation, have permitted more comprehensive physical property characterizations to be conducted. As a result of these technological advances, it is possible to present the results of these microscopic analyses, as they were initially collected by the microscopist, outside of the laboratory.An evolutionary trail detailing the use of hot-stage microscopy in the Materials Science Group, from a simple melting point apparatus to the current hot-stage DSC microscopy instrument, will be presented. Examples of materials characterized using the hot-stage microscopy system will also be presented. (Copyright (c) 1998 Elsevier Science B.V., Amsterdam. All rights reserved.)

The feasibility study of hot cell decontamination by the PFC spray method

International Nuclear Information System (INIS)

Hui-Jun Won; Chong-Hun Jung; Jei-Kwon Moon

2008-01-01

module. A performance test on each module was executed and the results have been reported. A combined test of the four modules, however, has not been performed as yet. The main objective of the present study is to demonstrate the feasibility of the full PFC spray decontamination process. Decontamination of the inside of the IMEF hot cell by the PFC spray method was also performed. PFC spray decontamination process was demonstrated by using a surrogate wall contaminated with Eu 2 O 3 powder. The spray pressure was 41 kgf/cm 2 , the orifice diameter was 0.2 mm and the spray velocity was 0.2 L/min. And, the decontaminated area was 100 cm 2 . From previous test results, we found that the decontamination factor of the PFC spray method was in the range from 9.6 to 62.4. When the decontamination efficiency of Co-60 was high, then the decontamination efficiency of Cs-137 was also high. As the surface roughness of the specimen increased, the PFC spray decontamination efficiency decreased. Inferring from the previous results, the surface of the surrogate wall was cleaned by the PFC spray method. The vacuum cup of the collection module operated well and gathered more than 99 % of the PFC solution. Also, filtration and distillation modules operated well. All the filtered PFC solution flowed to the storage chamber where some of the PFC solution was distilled. The coolant of the distillation module was a dry ice. And, the recycled solution was transferred to the spray module by a high pressure pump. To evaluate the PFC spray decontamination efficiency, a smear device was fabricated and operated by a manipulator. Before and after decontamination, a smear test was performed. The tested area was 100 cm 2 and the radioactivity was estimated indirectly by measuring the radioactivity of the filter paper. The average decontamination factor was in the range between 10 and 15. One application time was 2 minutes. The sprayed PFC solution was collected by the vacuum cup and it was stored in the

Energy Yield Determination of Concentrator Solar Cells using Laboratory Measurements: Preprint

Energy Technology Data Exchange (ETDEWEB)

Geisz, John F.; Garcia, Ivan; McMahon, William E.; Steiner, Myles A.; Ochoa, Mario; France, Ryan M.; Habte, Aron; Friedman, Daniel J.

2015-09-14

The annual energy conversion efficiency is calculated for a four junction inverted metamorphic solar cell that has been completely characterized in the laboratory at room temperature using measurements fit to a comprehensive optoelectronic model of the multijunction solar cells. A simple model of the temperature dependence is used to predict the performance of the solar cell under varying temperature and spectra characteristic of Golden, CO for an entire year. The annual energy conversion efficiency is calculated by integrating the predicted cell performance over the entire year. The effects of geometric concentration, CPV system thermal characteristics, and luminescent coupling are highlighted. temperature and spectra characteristic of Golden, CO for an entire year. The annual energy conversion efficiency is calculated by integrating the predicted cell performance over the entire year. The effects of geometric concentration, CPV system thermal characteristics, and luminescent coupling are highlighted.

In Situ Hot-Spot Assembly as a General Strategy for Probing Single Biomolecules.

Science.gov (United States)

Liu, Huiqiao; Li, Qiang; Li, Mingmin; Ma, Sisi; Liu, Dingbin

2017-05-02

Single-molecule detection using surface-enhanced Raman spectroscopy (SERS) has attracted increasing attention in chemical and biomedical analysis. However, it remains a major challenge to probe single biomolecules by means of SERS hot spots owing to the small volume of hot spots and their random distribution on substrates. We here report an in situ hot-spot assembly method as a general strategy for probing single biomolecules. As a proof-of-concept, this proposed strategy was successfully used for the detection of single microRNA-21 (miRNA-21, a potential cancer biomarker) at the single-cell level, showing great capability in differentiating the expression of miRNA-21 in single cancer cells from normal cells. This approach was further extended to single-protein detection. The versatility of the strategy opens an exciting avenue for single-molecule detection of biomarkers of interest and thus holds great promise in a variety of biological and biomedical applications.

HOT STARS WITH HOT JUPITERS HAVE HIGH OBLIQUITIES

International Nuclear Information System (INIS)

Winn, Joshua N.; Albrecht, Simon; Fabrycky, Daniel; Johnson, John Asher

2010-01-01

We show that stars with transiting planets for which the stellar obliquity is large are preferentially hot (T eff > 6250 K). This could explain why small obliquities were observed in the earliest measurements, which focused on relatively cool stars drawn from Doppler surveys, as opposed to hotter stars that emerged more recently from transit surveys. The observed trend could be due to differences in planet formation and migration around stars of varying mass. Alternatively, we speculate that hot-Jupiter systems begin with a wide range of obliquities, but the photospheres of cool stars realign with the orbits due to tidal dissipation in their convective zones, while hot stars cannot realign because of their thinner convective zones. This in turn would suggest that hot Jupiters originate from few-body gravitational dynamics and that disk migration plays at most a supporting role.

Partial Replacement of Cement with Bagasse Ash in Hot Mix Asphalt ...

African Journals Online (AJOL)

It is in this light that a laboratory based investigation for the replacement of cement with BA in Hot Mix Asphalt (HMA) was conducted. Tests on the suitability of materials used and their performance in terms of known engineering properties was carried out. Bitumen content of 4.5%, 5.5%, 6.5% and 7.5% was adopted.

Hot-electron plasma formation and confinement in the tandem mirror experiment-upgrade

International Nuclear Information System (INIS)

Ress, D.B.

1988-06-01

The tandem mirror experiment-upgrade (TMX-U) at the Lawrence Livermore National Laboratory (LLNL) is the first experiment to investigate the thermal-barrier tandem-mirror concept. One attractive feature of the tandem magnetic mirror as a commercial power reactor is that the fusion reactions occur in an easily accessible center-cell. On the other hand, complicated end-cells are necessary to provide magnetohydrodynamic (MHD) stability and improved particle confinement of the center-cell plasma. In these end-cells, enhanced confinement is achieved with a particular axial potential profile that is formed with electron-cyclotron range-of-frequency heating (ECRF heating, ECRH). By modifying the loss rates of electrons at spatially distinct locations within the end-cells, the ECRH can tailor the plasma potential profile in the desired fashion. Specifically, the thermal-barrier concept requires generation of a population of energetic electrons near the midplane of each end-cell. To be effective, the transverse (to the magnetic field) spatial structure of the hot-electron plasma must be fairly uniform. In this dissertation we characterize the spatial structure of the ECRH-generated plasma, and determine how the structure builds up in time. Furthermore, the plasma should efficiently absorb the ECRF power, and a large fraction of the electrons must be well confined near the end-cell midplane. Therefore, we also examine in detail the ECRH power balance, determining how the ECRF power is absorbed by the plasma, and the processes through which that power is confined and lost. 43 refs., 69 figs., 6 tabs

Preliminary draft: environmental impact statement for Hot Engineering Test Project at Oak Ridge National Laboratory

International Nuclear Information System (INIS)

Boyle, J.W.; Baxter, B.J.; Carpenter, J.A.

1978-08-01

The project considered is the Hot Engineering Test Project (HETP), which is to be located in largely existing facilities at Oak Ridge National Laboratory (ORNL). The project is a part of the National High Temperature Gas-Cooled Reactor Fuel Recycle Program, which seeks to demonstrate the technological feasibility of the recycle processes. The HETP will attempt to confirm the operability of the processes (proven feasible in cold or nonradioactive, benchtop experimentation) under the more realistic radioactive condition. As such, the operation will involve the reprocessing and refabrication of spent HTGR fuel rods obtained from the Fort St. Vrain reactor. The reference fuel is highly enriched uranium. No significant radiological impacts are expected from routine operation of the facility to any biota or ecosystem. Concentrations of one or more radionuclides in Whiteoak Lake will increase as a result of the combination of HETP wastes with other ORNL wastes. Nonradiological effects from construction activities and routine operation should be insignificant on land and water use and on terrestrial and aquatic ecosystems. No significant socioeconomic impacts should occur from either construction or operation of the facility. Some conservative accident scenarios depict significant releases of radioactivity. Effects should be localized and would not be severe for all but the most unlikely of such incidents. No significant long-term commitment of resources is expected to be required for the project. Nor are any large quantities of scarce or critical resources likely to be irreversibly or irretrievably committed to the project. Principal alternatives considered were: relocation of the project site, postponement of the project schedule, project cancellation, and chemical process variations

Proceedings of the second NATO-CCMS information meeting on dry hot rock geothermal energy

Energy Technology Data Exchange (ETDEWEB)

Mortensen, J.J. (comp.)

1977-11-01

A summary is presented of the second and last NATO-CCMS (North Atlantic Treaty Organization--Committee on Challenges of Modern Society) Geothermal Pilot Study Information Meeting on Dry Hot Rock Geothermal Energy. Only summaries of the formal presentations are included. Overviews of the Energy Research and Development Administration (ERDA) and the U.S. Geological Survey (USGS) geothermal projects are included with emphasis on the Los Alamos Scientific Laboratory (LASL) Hot Dry Rock Geothermal Energy Development Project. Reports of developments in nine foreign countries and on geothermal projects in US universities are also presented.

Preliminary report for the license of a hot cell that will be use in the technology development for the obtention of Mo-99

International Nuclear Information System (INIS)

Fucugauchi, L.A.; Millan S, S.; Lopez M, A.E.; Lopez C, R; Sanchez M, V.; Reynoso V, R.; Vera, A.

1991-05-01

A preliminary report for the license of a hot cell that will be used in the development of the technology for the obtaining of Mo-99 is presented. The following topics are also included: objective of the project, technical description, description of the prototype cell, handling of radioactive wastes, lists of equipment that will be used, risk analysis, curricula, quality assurance plan and an annex with the report on handling of radioactive wastes presented to the PAGD-IAEA. (Author)

A Hot-Wire Method Based Thermal Conductivity Measurement Apparatus for Teaching Purposes

Science.gov (United States)

Alvarado, S.; Marin, E.; Juarez, A. G.; Calderon, A.; Ivanov, R.

2012-01-01

The implementation of an automated system based on the hot-wire technique is described for the measurement of the thermal conductivity of liquids using equipment easily available in modern physics laboratories at high schools and universities (basically a precision current source and a voltage meter, a data acquisition card, a personal computer…

The Spatial Predilection for Early Esophageal Squamous Cell Neoplasia: A "Hot Zone" for Endoscopic Screening and Surveillance.

Science.gov (United States)

Wang, Wen-Lun; Chang, I-Wei; Chen, Chien-Chuan; Chang, Chi-Yang; Lin, Jaw-Town; Mo, Lein-Ray; Wang, Hsiu-Po; Lee, Ching-Tai

2016-04-01

Early esophageal squamous cell neoplasias (ESCNs) are easily missed with conventional white-light endoscopy. This study aimed to assess whether early ESCNs have a spatial predilection and the patterns of recurrence after endoscopic treatment. We analyzed the circumferential and longitudinal location of early ESCNs, as well as their correlations with exposure to carcinogens in a cohort of 162 subjects with 248 early ESCNs; 219 of which were identified by screening and 29 by surveillance endoscopy. The circumferential location was identified using a clock-face orientation, and the longitudinal location was identified according to the distance from the incisor. The most common circumferential and longitudinal distributions of the early ESCNs were found in the 6 to 9 o'clock quadrant (38.5%) and at 26 to 30 cm from the incisor (41.3%), respectively. A total of 163 lesions (75%) were located in the lower hemisphere arc, and 149 (68.4%) were located at 26 to 35 cm from the incisor. One hundred eleven (51%) early ESCNs were centered within the "hot zone" (i.e., lower hemisphere arc of the esophagus at 26 to 35 cm from the incisor), which comprised 20% of the esophageal area. Exposure to alcohol, betel nut, or cigarette was risk factors for the development of early ESCNs in the lower hemisphere. After complete endoscopic treatment, the mean annual incidence of metachronous tumors was 10%. In addition, 43% of the metachronous recurrent neoplasias developed within the "hot zone." Cox regression analysis revealed that the index tumor within the hot zone (hazard ratio [HR]: 3.19; 95% confidence interval [CI]: 1.17-8.68; P = 0.02) and the presence of numerous Lugol-voiding lesions in the esophageal background mucosa were independent predictors for metachronous recurrence (HR: 4.61; 95% CI: 1.36-15.56; P = 0.01). We identified a hot zone that may be used to enhance the detection of early ESCNs during endoscopic screening and surveillance, especially in areas that

Remote waste handling at the Hot Fuel Examination Facility

International Nuclear Information System (INIS)

Vaughn, M.E.

1982-01-01

Radioactive solid wastes, some of which are combustible, are generated during disassembly and examination of irradiated fast-reactor fuel and material experiments at the Hot Fuel Examination Facility (HFEF). These wastes are remotely segregated and packaged in doubly contained, high-integrity, clean, retrievable waste packages for shipment to the Radioactive Waste Management Complex (RWMC) at the Idaho National Engineering Laboratory (INEL). This paper describes the equipment and techniques used to perform these operations

Hürthle cell tumor dwelling in hot thyroid nodules: preoperative detection with technetium-99m-MIBI dual-phase scintigraphy.

Science.gov (United States)

Vattimo, A; Bertelli, P; Cintorino, M; Burroni, L; Volterrani, D; Vella, A; Lazzi, S

1998-05-01

Single injection dual-phase scintigraphy (early and late acquisitions) with 99mTc-MIBI was used to differentiate benign and malignant hot thyroid nodules. Thirteen euthyroid and two hyperthyroid patients displaying a hot thyroid nodule on the 99mTc scan due to an autonomously functioning thyroid nodule (AFTN) underwent early (15-30 min) and late (3-4 hr) thyroid scintigraphy after the administration of 740-1000 MBq 99mTc-MIBI. Visual scoring was done to assess nodular tracer uptake and retention. In addition, the nodular-to-thyroid (N/T) uptake ratio in the early and late image and the washout rates (WO) from the nodule and thyroidal tissue were measured. All patients underwent thyroid surgery. Histopathology revealed a Hürthle cell tumor in three nodules, a benign adenoma with oxyphilic metaplasia in two nodules and a benign adenoma without oxyphilic cells in the remaining 10 nodules. The Hürthle cell tumor nodules displayed intense and persistent uptake of 99mTc-MIBI (N/T was 2.81 +/- 0.52 and 5.53 +/- 1.06 in early and late images, respectively; WO from the nodule was 12.33 +/- 0.47, WO from the thyroidal tissue was 22.00 +/- 3.56). The benign nodules showed intense uptake in the early image and intense uptake to absent retention in the late image (N/T was 2.94 +/- 1.31 and 1.62 +/- 0.50 in the early and late images, respectively; WO from the nodule was 20.25 +/- 2.92, WO from the thyroidal tissue was 20.33 +/- 2.92). Single injection dual-phase 99mTc-MIBI scintigraphy of the thyroid with AFTN can identify nodules as a result of the activity of a Hürthle cell tumor, since these tumors cause intense and persistent tracer uptake in contrast with a benign AFTN.

Techniques and devices developed by the CEA for hot cell and in-situ examinations of PWR components and PWR fuel assembliess after irradiation

International Nuclear Information System (INIS)

Van Craeynest, J.C.; Leseur, A.; Lhermenier, A.; Cytermann, R.

1981-11-01

Within the framework of the electro-nuclear development of the PWR system, the CEA has provided itself with facilities for developing techniques for analyzing assemblies, pins and fuels. These are examinations and tests on irradiated heads and assemblies with the aid of the Fuel Examination Module (FEM), of machining of assemblies and examinations in the Celimene hot laboratory or detailed examinations and analyses on fuel elements using eddy currents, the electronic microprobe and the Fisher ''permeascope'' which enables the outline of the oxide coat present on the cladding to be followed [fr

LASP-01: Distribution of Mouse Embryonic Stem Cells Expressing MicroRNAs | Frederick National Laboratory for Cancer Research

Science.gov (United States)

The Laboratory Animal Sciences Program manages the expansion, processing, and distribution of1,501 genetically engineered mouse embryonic stem cell (mESC) linesharboring conditional microRNA transgenes. The Laboratory Animal Sciences Prog

A Statistical Analysis of Student Questions in a Cell Biology Laboratory

Science.gov (United States)

Keeling, Elena L.; Polacek, Kelly M.; Ingram, Ella L.

2009-01-01

Asking questions is an essential component of the practice of science, but question-asking skills are often underemphasized in science education. In this study, we examined questions written by students as they prepared for laboratory exercises in a senior-level cell biology class. Our goals were to discover 1) what types of questions students…

Hot spot mix in ICF implosions on the NIF

Science.gov (United States)

Ma, Tammy

2016-10-01

In the quest to achieve ignition through the inertial confinement fusion scheme, one of the critical challenges is to drive a symmetric implosion at high velocity without hydrodynamic instabilities becoming detrimental. These instabilities, primarily at the ablation front and the fuel-ablator interface, can cause mix of the higher-Z shell into the hot spot, resulting in increased radiation loss and thus reduced temperature and neutron yield. To quantify the level of mix, we developed a model that infers the level of hot spot contamination using the ratio of the enhanced x-ray production relative to the neutron yield. Applying this methodology to the full ensemble of indirect-drive National Ignition Facility (NIF) cryogenically layered DT implosions provides insight on the sensitivity of performance to the level of ablator-hot spot mix. In particular, the improvement seen with the High Foot design can be primarily attributed to a reduction in ablation-front instability mix that enabled the implosions to be pushed to higher velocity and performance. This work was performed under the auspices of the U.S. Department of Energy by Lawrence Livermore National Laboratory under Contract DE-AC52-07NA27344, Lawrence Livermore National Security, LLC.

Encapsulation of tritiated wastes in hot laboratories

International Nuclear Information System (INIS)

Hayet, L.; Bourdinaud, P.

1982-06-01

From 1962 to 1976, one of the laboratories called ''Cellule 4'', was equipped to produce large quantities of tritium. The decisions taken in June 1976 to redirect the activities of the Radioisotopes Department included the suspension of the tritium activities of ''Cellule 4'' at the Saclay Nuclear Research Center. From 1976 to 1981, many CEA departments contributed to the design and implementation of a packaging procedure for tritiated wastes resulting from the dismantling of ''Cellule 4''. A classification into three groups was adopted for this purpose. (1) Packaging in a welded stainless steel container. (2) Packaging in a reinforced concrete shell lined internally with a thick coat of epoxy resin charged with sand. (3) Packaging in a reinforced concrete shell lined internally with a thin coat of epoxy resin. The dismantling operations were carried out in three phases. (1) (2 1/2 months): the T activity remained unchanged during this period and waste selection was carried out. (2) (2 1/2 months): waste dismantling and packaging of groups (2) and (3) were carried out in this phase. Activity decayed rapidly. (3) (2 months): the work performed included the loosening and cutting of the general structures [fr

Evaluating the effects of compaction of hot mix asphalt on selected laboratory tests

CSIR Research Space (South Africa)

Kekana, SL

2008-07-01

Full Text Available of the gyratory prepared samples for standard laboratory design mix and the field prepared samples, while the short-term aged (SA) sample shows similar rut rates to the field compacted samples. Early failure was evident after 2 000 wheel passes for the short.... The laboratory design mixed is represented by short-term aged mixed and design mix (fresh mix in the laboratory). The type of mix discussed in this study is summarised in Tables 1 and 2 and Figure 1. Detailed information about the mix is discussed in Denneman...

Friction and wear in hot forging of steels

International Nuclear Information System (INIS)

Daouben, E.; Dubar, L.; Dubar, M.; Deltombe, R.; Dubois, A.; Truong-Dinh, N.; Lazzarotto, L.

2007-01-01

In the field of hot forging of steels, the mastering of wear phenomena enables to save cost production, especially concerning tools. Surfaces of tools are protected thanks to graphite. The existing lubrication processes are not very well known: amount and quality of lubricant, lubrication techniques have to be strongly optimized to delay wear phenomena occurrence. This optimization is linked with hot forging processes, the lubricant layers must be tested according to representative friction conditions. This paper presents the first part of a global study focused on wear phenomena encountered in hot forging of steels. The goal is the identification of reliable parameters, in order to bring knowledge and models of wear. A prototype testing stand developed in the authors' laboratory is involved in this experimental analysis. This test is called Warm and Hot Upsetting Sliding Test (WHUST). The stand is composed of a heating induction system and a servo-hydraulic system. Workpieces taken from production can be heated until 1200 deg. C. A nitrided contactor representing the tool is heated at 200 deg. C. The contactor is then coated with graphite and rubs against the workpiece, leaving a residual track on it. Friction coefficient and surface parameters on the contactor and the workpiece are the most representative test results. The surface parameters are mainly the sliding length before defects occurrence, and the amplitude of surface profile of the contactor. The developed methodology will be first presented followed by the different parts of the experimental prototype. The results of experiment show clearly different levels of performance according to different lubricants

Carbonate ion-enriched hot spring water promotes skin wound healing in nude rats.

Directory of Open Access Journals (Sweden)

Jingyan Liang

Full Text Available Hot spring or hot spa bathing (Onsen is a traditional therapy for the treatment of certain ailments. There is a common belief that hot spring bathing has therapeutic effects for wound healing, yet the underlying molecular mechanisms remain unclear. To examine this hypothesis, we investigated the effects of Nagano hot spring water (rich in carbonate ion, 42°C on the healing process of the skin using a nude rat skin wound model. We found that hot spring bathing led to an enhanced healing speed compared to both the unbathed and hot-water (42°C control groups. Histologically, the hot spring water group showed increased vessel density and reduced inflammatory cells in the granulation tissue of the wound area. Real-time RT-PCR analysis along with zymography revealed that the wound area of the hot spring water group exhibited a higher expression of matrix metalloproteinases-2 and -9 compared to the two other control groups. Furthermore, we found that the enhanced wound healing process induced by the carbonate ion-enriched hot spring water was mediated by thermal insulation and moisture maintenance. Our results provide the evidence that carbonate ion-enriched hot spring water is beneficial for the treatment of skin wounds.

Enhancing Communication Skills of Pre-service Physics Teacher through HOT Lab Related to Electric Circuit

Science.gov (United States)

Malik, A.; Setiawan, A.; Suhandi, A.; Permanasari, A.; Dirgantara, Y.; Yuniarti, H.; Sapriadil, S.; Hermita, N.

2018-01-01

This study aimed to investigate the improvement to pre-service teacher’s communication skills through Higher Order Thinking Laboratory (HOT Lab) on electric circuit topic. This research used the quasi-experiment method with pretest-posttest control group design. Research subjects were 60 students of Physics Education in UIN Sunan Gunung Djati Bandung. The sample was chosen by random sampling technique. Students’ communication skill data collected using a communication skills test instruments-essays form and observations sheets. The results showed that pre-service teacher communication skills using HOT Lab were higher than verification lab. Student’s communication skills in groups using HOT Lab were not influenced by gender. Communication skills could increase due to HOT Lab based on problems solving that can develop communication through hands-on activities. Therefore, the conclusion of this research shows the application of HOT Lab is more effective than the verification lab to improve communication skills of pre-service teachers in electric circuit topic and gender is not related to a person’s communication skills.

Haptic shared control improves hot cell remote handling despite controller inaccuracies

International Nuclear Information System (INIS)

Oosterhout, J. van; Abbink, D.A.; Koning, J.F.; Boessenkool, H.; Wildenbeest, J.G.W.; Heemskerk, C.J.M.

2013-01-01

Highlights: Haptic shared control is generally based upon perfect environment information. A realistic implementation holds model errors with respect to the environment. Operators were aided with inaccurate guiding forces during a peg-in-hole task. The results showed that small guiding inaccuracies still aid the operator. -- Abstract: A promising solution to improve task performance in ITER hot cell remote handling is the use of haptic shared control. Haptic shared control can assist the human operator along a safe and optimal path with continuous guiding forces from an intelligent autonomous controller. Previous research tested such controllers with accurate knowledge of the environment (giving flawless guiding forces), while in a practical implementation guidance forces will sometimes be flawed due to inaccurate models or sensor information. This research investigated the effect of zero and small (7.5 mm) errors on task performance compared to normal (unguided) operation. In a human factors experiment subjects performed a three dimensional virtual reality peg-in-hole type task (30 mm diameter; 0.1 mm clearance), with and without potentially flawed haptic shared control. The results showed that the presence of guiding forces, despite of small guiding errors, still improved task performance with respect to unguided operations

Haptic shared control improves hot cell remote handling despite controller inaccuracies

Energy Technology Data Exchange (ETDEWEB)

Oosterhout, J. van, E-mail: J.vanOosterhout@differ.nl [Delft University of Technology, Faculty of 3mE, BioMechanical Engineering Department, Mekelweg 2, 2628 CD Delft (Netherlands); Abbink, D.A. [Delft University of Technology, Faculty of 3mE, BioMechanical Engineering Department, Mekelweg 2, 2628 CD Delft (Netherlands); Koning, J.F. [Heemskerk Innovative Technology B.V., Jonckerweg 12, 2201 DZ Noordwijk (Netherlands); Boessenkool, H. [FOM Institute DIFFER (Dutch Institute for Fundamental Energy Research), Association EURATOM-FOM, Partner in the Trilateral Euregio Cluster, PO Box 1207, 3430 BE Nieuwegein (Netherlands); Wildenbeest, J.G.W. [Delft University of Technology, Faculty of 3mE, BioMechanical Engineering Department, Mekelweg 2, 2628 CD Delft (Netherlands); Heemskerk Innovative Technology B.V., Jonckerweg 12, 2201 DZ Noordwijk (Netherlands); Heemskerk, C.J.M. [Heemskerk Innovative Technology B.V., Jonckerweg 12, 2201 DZ Noordwijk (Netherlands)

2013-10-15

Highlights: Haptic shared control is generally based upon perfect environment information. A realistic implementation holds model errors with respect to the environment. Operators were aided with inaccurate guiding forces during a peg-in-hole task. The results showed that small guiding inaccuracies still aid the operator. -- Abstract: A promising solution to improve task performance in ITER hot cell remote handling is the use of haptic shared control. Haptic shared control can assist the human operator along a safe and optimal path with continuous guiding forces from an intelligent autonomous controller. Previous research tested such controllers with accurate knowledge of the environment (giving flawless guiding forces), while in a practical implementation guidance forces will sometimes be flawed due to inaccurate models or sensor information. This research investigated the effect of zero and small (7.5 mm) errors on task performance compared to normal (unguided) operation. In a human factors experiment subjects performed a three dimensional virtual reality peg-in-hole type task (30 mm diameter; 0.1 mm clearance), with and without potentially flawed haptic shared control. The results showed that the presence of guiding forces, despite of small guiding errors, still improved task performance with respect to unguided operations.

Sampling of airborne radioactivity in a hot fuel examination facility

International Nuclear Information System (INIS)

Courtney, J.C.; Madison, J.P.; Holson, C.E.; Black, R.L.; Dilorenzo, F.L.; Anderson, J.B.; Hylsky, E.; Lau, L.D.

1980-01-01

To ensure the maintenance of a safe working environment, and provide data of interest to operations personnel, a fixed air sampling system (FASS) has been installed at the Hot Fuel Examination Facility/North at Argonne National Laboratory's Idaho site. A design requirement is that the system be operated with a minimum number of person-hours. Sixty-six sampling stations are located throughout the facility to gather data from areas where personnel are normally present without respiratory protection. The effectiveness of in-cell contamination-control programs and materials-handling procedures can be evaluated. Long-term trends are valuable guides to improving radiological controls while airborne activities are still well below operational guidelines. Since the beginning of operation in August 1976, the concentrations have averaged between 1x10 -15 and 5x10 -15 μCi/cm 3 for α emitters and from 4x10 -14 to 4x10 -13 μCi/cm 3 for β-γ emitters. Such values are well below the radiation concentration guides. (author)