Investigation of UFO defect on DUV CAR and BARC process

Science.gov (United States)

Yet, Siew Ing; Ko, Bong Sang; Lee, Soo Man; May, Mike

2004-05-01

Photo process defect reduction is one of the most important factors to improve the process stability and yield in sub-0.18um DUV process. In this paper, a new approach to minimize the Deep-UV (DUV) Chemically Amplified Resist (CAR) and Bottom Anti-Reflective Coating (BARC) induced defect known as UFO (UnidentiFied Object) defect will be introduced. These defects have mild surface topography difference on BARC; it only exists on the wide exposed area where there is no photoresist pattern. In this test, Nikon KrF Stepper & Scanner and TEL Clean track were used. Investigation was carried out on the defect formulation on both Acetal and ESCAP type of photoresist while elemental analysis was done by Atomic Force Microscope (AFM) & Auger Electron Spectroscopy (AES). Result indicated that both BARC and photoresist induce this UFO defect; total defect quantity is related with Post Exposure Bake (PEB) condition. Based on the elemental analysis and process-split test, we can conclude that this defect is caused by lack of acid amount and low diffusivity which is related to PAG (Photo Acid Generator) and TAG (Thermal Acid Generator) in KrF photoresist and BARC material. By optimizing photoresist bake condition, this UFO defect as well as other related defect such as Satellite defect could be eliminated.

7-MeV electron LINAC based pulse radiolysis facility at RPCD, BARC

International Nuclear Information System (INIS)

Naik, C.B.; Nadkarni, S.A.; Toley, M.A.; Shinde, S.J.; Naik, P.D.

2017-01-01

7-MeV electron LINAC based pulse radiolysis facility is operational in Chemistry Group of BARC since 1986. The Accelerator is housed in B-132 room in basement of Modular Labs. BARC Accelerator was procured from Radiation Dynamics Inc. UK and its detection system was indigenously developed

Popularization of groundnut varieties through BARC-UASD collaboration

International Nuclear Information System (INIS)

Madhusudan, K.; Nadaf, H.L.; Hanchinal, R.R.; Krishna Naik, L.; Motagi, B.N.; Biradar Patil, N.K.; Hunje, Ravi; D'Souza, S.F.; Badigannavar, A.M.

2009-01-01

To boost the productivity of groundnut, farmers need to have an access to improved seeds of the right variety, at the right time, at the right place, at an affordable price. The awareness and benefits of the improved varieties and quality seeds of groundnut was carried out by carefully planned co-ordinated educational systems such as field trials, demonstrations, field days, training farmers, interface meetings through the well established network of the University and mass media promotional tools. The BARC-UASD collaboration led to the popularization of BARC groundnut varieties like TAG-24, TG-26, TPG-41 and TDG-39 among the farming community of north Karnataka. (author)

Safety margin evaluation of pre-stressed concrete nuclear containment vessel model with BARC code ULCA

International Nuclear Information System (INIS)

Basha, S.M.; Patnaik, R.; Ramanujam, S.; Singh, R.K.; Kushwaha, H.S.; Venkat Raj, V.

2002-01-01

Full text: Ultimate load capacity assessment of nuclear containments has been a thrust research area for Indian pressurised heavy water reactor (PHWR) power programme. For containment safety assessment of Indian PHWRs a finite element code ULCA was developed at BARC, Trombay. This code has been extensively benchmarked with experimental results and for prediction of safety margins of Indian PHWRs. The present paper highlights the analysis results for prestressed concrete containment vessel (PCCV) tested at Sandia National Labs, USA in a round robin analysis activity co-sponsored by Nuclear Power Engineering Corporation (NUPEC), Japan and the U.S Nuclear Regulatory Commission (NRC). Three levels of failure pressure predictions namely the upper bound, the most probable and the lower bound (all with 90% confidence) were made as per the requirements of the round robin analysis activity. The most likely failure pressure is predicted to be in the range of 2.95 Pd to 3.15 Pd (Pd = design pressure of 0.39 MPa for the PCCV model) depending on the type of liners used in the construction of the PCCV model. The lower bound value of the ultimate pressure of 2.80 Pd and the upper bound of the ultimate pressure of 3.45 Pd are also predicted from the analysis. These limiting values depend on the assumptions of the analysis for simulating the concrete tendon interaction and the strain hardening characteristics of the steel members. The experimental test has been recently concluded at Sandia Laboratory and the peak pressure reached during the test is 3.3 Pd that is enveloped by our upper bound prediction of 3.45 Pd and is close to the predicted most likely pressure of 3.15 Pd

Development of optically stimulated luminescence reader systems in BARC

International Nuclear Information System (INIS)

Kulkarni, M.S.

2008-01-01

BARC has very vast experience in the development of thermoluminescence (TL) reader systems both for routine personnel monitoring and research application. However, optically stimulated luminescence (OSL) related instrumentation is a recent development in BARC. The increasing popularity of OSL technique in the radiation dosimetry applications in the recent past has driven investigation and developmental programme in the OSL measurement facilities at BARC. As the consequence of the efforts directed towards the indigenous development of OSL reader system, OSL readers with various readout modes like continuous wave (CW) OSL mode, linear intensity modulated OSL (LM-OSL), pulsed OSL (POSL) have been developed. In addition to these conventional modes of operation a novel non-linear OSL mode (NL-OSL) has also been developed for the OSL measurements. This paper reviews the details of the development of OSL reader system including experience with high intensity blue/green LED stimulation light source and detection system. Also discussed are recently developed versatile integrated TL/OSL reader systems for TL and OSL measurements. (author)

Evolution of nuclear safety regulation for BARC Facilities

International Nuclear Information System (INIS)

Jayarajan, K.; Taly, Y.K.

2017-01-01

Safety programmes in BARC stared during the formative years and grown its stature, as the years passed by. Seventeen years of BSC, with one hundred meetings, have been quite eventful with several achievements. BSC could bring all facilities of BARC under its safety umbrella and could streamline many safety and regulatory activities. BSC aims at incident free operation of all facilities and protection of the workers, the public, the environment from radiation and other hazards. Although, incidents could not be entirely prevented, BSC have taken every event as a lesson and used the experience for improving safety. Safety enhancement is an endless journey, which has to be performed by joining hands of the managers, designers, manufacturers, inspectors and operators, in addition to the regulators

Advancement adopted for physical protection system at BARC facilities Tarapur

International Nuclear Information System (INIS)

Jaroli, Manish; Ameta, Rohit; Patil, V.H.; Dubey, K.

2015-01-01

Considering the prevailing security situation and threat perception to the nuclear installations in particular, it has become essential to strengthen security system at BARC Tarapur in an effective manner to avert any attempt of sabotage and to ensure smooth functioning of security and safety of the nuclear installations. International Atomic Energy Agency (IAEA) and Atomic Energy Regulatory Board (AERB) have provided various security guides for the physical protection system (PPS) for nuclear installations and there has been advancement in physical and personnel protection system due to evolution of new technologies. In line with this, latest technologies have been adopted in PPS for BARC facilities, Tarapur recently. This includes state of art RFID card based access control, visitor and contractor management system, electronic key management system. Digital signature based biometric visitor and contractor management system; Digital signature based leave management system; Distress alarm system (DAS); Guard tour monitoring system (GTMS); Secure network access system (SNAS) as well as multilayered access control system at plant level. This will strengthen the surveillance and monitoring of personnel and visitors at BARC facilities. (author)

Development and performance evaluation of high speed cryogenic turboexpanders at BARC, India

Science.gov (United States)

Chakravarty, A.; Menon, R. S.; Goyal, M.; Ahmed, N.; Jadhav, M.; Rane, T.; Nair, S. R.; Kumar, J.; Kumar, N.; Bharti, S. K.; Jain, A.; Joemon, V.

2017-12-01

Turboexpanders are a key focus area for Bhabha Atomic Research Centre (BARC), Mumbai, India in the program for development of helium refrigerators and liquefiers for intra departmental requirements. To start with, a turbine impeller with major diameter 16 mm and design speed of 264,000 RPM, suited for use in the 1st stage of a modified Claude cycle/reverse Brayton cycle based standard helium liquefier/refrigerator, is developed. Later on, a second series of turboexpander with the same major diameter (16 mm) and design speed of 260,000 RPM is developed with “splitter” blades at the major diameter end. Yet another turboexpander series, size 16.5 mm and design speed 168,000 RPM, is also developed suited for use in the 2nd stage of a standard helium liquefier/refrigerator. The present article describes these turboexpander development efforts at BARC, including results obtained during field trials with the BARC helium refrigerator and liquefier.

Role of ESLs in reaching BARC technologies to rural India - experience at Kaiga

International Nuclear Information System (INIS)

Nayak, P.D.; Ujjappa, K.M.; Ravi, P.M.; Hegde, A.G.

2009-01-01

Considering the various site selection requirements, most of the nuclear power plants in India under Nuclear Power Corporation of India Limited (NPCIL), are located in very remote locations. The Environmental Survey Laboratories (ESLs) under Health Physics Division, BARC are located at all Nuclear Power Stations. This paper presents the experience gained at ESL, KGS, Kaiga in acting as an interface between BARC, the technology developer and the rural public, the end user of the technology. (author)

Assessment of Ultimate Load Capacity for Pre-Stressed Concrete Containment Vessel Model of PWR Design With BARC Code ULCA

International Nuclear Information System (INIS)

Basha, S.M.; Singh, R.K.; Patnaik, R.; Ramanujam, S.; Kushwaha, H.S.; Venkat Raj, V.

2002-01-01

Ultimate load capacity assessment of nuclear containments has been a thrust research area for Indian Pressurised Heavy Water Reactor (PHWR) power programme. For containment safety assessment of Indian PHWRs a finite element code ULCA was developed at BARC, Trombay. This code has been extensively benchmarked with experimental results. The present paper highlights the analysis results for Prestressed Concrete Containment Vessel (PCCV) tested at Sandia National Labs, USA in a Round Robin analysis activity co-sponsored by Nuclear Power Engineering Corporation (NUPEC), Japan and the U.S Nuclear Regulatory Commission (NRC). Three levels of failure pressure predictions namely the upper bound, the most probable and the lower bound (all with 90% confidence) were made as per the requirements of the round robin analysis activity. The most likely failure pressure is predicted to be in the range of 2.95 Pd to 3.15 Pd (Pd= design pressure of 0.39 MPa for the PCCV model) depending on the type of liners used in the construction of the PCCV model. The lower bound value of the ultimate pressure of 2.80 Pd and the upper bound of the ultimate pressure of 3.45 Pd are also predicted from the analysis. These limiting values depend on the assumptions of the analysis for simulating the concrete-tendon interaction and the strain hardening characteristics of the steel members. The experimental test has been recently concluded at Sandia Laboratory and the peak pressure reached during the test is 3.3 Pd that is enveloped by our upper bound prediction of 3.45 Pd and is close to the predicted most likely pressure of 3.15 Pd. (authors)

Molecular laser isotope separation programme at BARC

International Nuclear Information System (INIS)

Sarkar, Sisir K.; Parthasarathy, Venkatachari

2007-09-01

Little over thirty years ago, BARC ventured into a new frontier of scientific research: Molecular Laser Isotope Separation (MLIS) programme based on the interaction of lasers with molecules. The initial project was a scheme to produce enriched uranium. The idea was to use the intense, monochromatic light of lasers to break the chemical bonds of only those molecules containing the fissionable isotope uranium-235. At present the programme is evolving around separation of low and middle mass isotopes, namely sulphur 34/33/32, oxygen 17/18, carbon 13/12, hydrogen T/D/H to be followed by an advanced engineering programme designed to lead to a demonstration plant. The latest results have come very close to the design parameters specified for a full-scale separation of carbon isotopes. All these expertise provide an infra structure for future front line R and D activities in the general area of Laser Photochemical Technology which would include i) LIS of other useful elements ii) Material processing and iii) Fuel reprocessing/ waste management (author)

BARC-TIFR Pelletron Linac facility

International Nuclear Information System (INIS)

Gore, J.A.; Gupta, A.K.; Saxena, A.

2017-01-01

The Pelletron Accelerator, set up as a collaborative project between the Bhabha Atomic Research Centre and the Tata Institute of Fundamental Research, has been serving as the workhorse for the heavy ion accelerator based research in India since its commissioning in December 30, 1988. The facility was augmented with an indigenously developed superconducting Linac booster to enhance the energy of the Pelletron accelerated beams and was fully commissioned on November 28, 2007. The augmented facility is renamed as Pelletron Linac facility (PLF). While the PLF is predominantly utilized by the experimental users from BARC and TIFR, the users include researchers from other research institutions and universities within India and abroad

Status report on the folded tandem ion accelerator at BARC

Indian Academy of Sciences (India)

Folded tandem ion accelerator; charged particle beams; voltage stability; Rutherford backscattering; ion optics; beam lines. Abstract. The folded tandem ion accelerator (FOTIA) facility set up at BARC has become operational. At present, it is used for elemental analysis studies using the Rutherford backscattering technique.

Indigenous development and performance evaluation of BARC aerodynamic size separator (BASS)

CERN Document Server

Singh, S; Khan, A; Mayya, Y S; Narayanan, K P; Purwar, R C; Sapra, B K; Sunny, F

2002-01-01

Commercially available cascade impactors, commonly used for aerodynamic size separation of aerosol particles, are based on the principle of inertial impaction. As of now, these instruments are imported at a cost of several lakhs of rupees; hence an effort has been made to develop an aerodynamic particle sizer indigenously in BARC. This unit, referred to as BARC Aerodynamic Size Separator (BASS), separates aerosols into seven size classes ranging from 0.53 mu m to 10 mu m and operates at a flow rate of 45 Ipm. Intercomparison studies between the standard Andersen Mark-II (Grasbey Andersen Inc.) impactor and BASS using nebulizer generated aerosols have consistently shown excellent performance by BASS in all respects. In particular, BASS yielded the parameters of polydisperse aerosols quite accurately. Experiments to evaluate the individual stage cut-off diameters show that these are within 8% of their designed value for all stages except the higher two stages which indicate about 30% lower values than the desig...

Prediction and Analysis of students Behavior using BARC Algorithm

OpenAIRE

M.Sindhuja; Dr.S.Rajalakshmi; S.M.Nandagopal

2013-01-01

Educational Data mining is a recent trends where data mining methods are experimented for the improvement of student performance in academics. The work describes the mining of higher education students’ related attributes such as behavior, attitude and relationship. The data were collected from a higher education institution in terms of the mentioned attributes. The proposed work explored Behavior Attitude Relationship Clustering (BARC) Algorithm, which showed the improvement in students’ per...

Control system for BARC-TIFR Pelletron

International Nuclear Information System (INIS)

Singh, S.; Singh, P.; Gore, J.; Kulkarni, S.

2012-01-01

BARC-TIFR Pelletron is a 14 MV tandem accelerator in operation from more than 20 years. It was having a DOS based control system software which was running on a 486 PC and it was not possible to port it on new PCs. It was based on serial highway and Uport adapter based CAMAC crate controller which are now not available and all spares were used. Hence we have changed CAMAC controller with in house developed Ethernet based CAMAC controller and new software has been developed. New Control system software is based on LINUX operating system with graphical user interface developed using Trolltech's QT API, but can be easily ported on MS windows. (author)

Bio-organic chemistry at BARC

International Nuclear Information System (INIS)

Sharma, A.; Ghosh, S.K.; Chattopadhyay, S.

2009-01-01

Bioorganic chemistry plays a pivotal role of co-ordination amongst the research and developmental activities of physical, biological, material and nuclear sciences. Understandably, the domain of bioorganic chemistry encompasses overlapping scientific fields, and often involves multi-disciplinary subjects. The research activities of bioorganic research at BARC are, therefore directed with reference to deliverables, relevant to various nuclear and non-nuclear programmes of the department. Also, the activities of the division are fine tuned to address the contemporary needs. It is now well recognized that organic compounds are essential in various programmes of nuclear technology. These include solvents and membranes for the back-end process, carrier molecules for radiopharmaceuticals, optoelectrical materials and sensors for high tech applications etc. Coupled with this, bioorganics also form integral part of the departmental mission-oriented societal programmes in the areas of health and agriculture

Modal data for the BARC challenge problem Test Report

Energy Technology Data Exchange (ETDEWEB)

Rohe, Daniel Peter [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

2018-01-22

Modal testing was performed on the uncut BARC structure as a whole and broken into its two sub-assemblies. The structure was placed on soft foam during the test. Excitation was provided with a small modal hammer attached to an actuator. Responses were measured using a 3D Scanning Laser Doppler Vibrometer. Data, shapes, and geometry from this test can be downloaded in Universal File Format from the Sandia Connect SharePoint site.

Track Etch Membranes (TEMS) for separation sciences from BARC-TIFR Pelletron accelerator

International Nuclear Information System (INIS)

Nair, J.P.; Surendran, P.; Sparrow, Hillary; Gupta, A.K.; Kailas, S.; Bhagwat, P.V.

2014-01-01

TEMs are very much in need for the separation of desirable/undesirable metals from industrial effluents and radioactive wastes as well as in the field of biology and gas separation. It is necessary to optimize pore size and pore density for a specific application. TEMs available in market are imported and are used for laboratory scale activity. To carry the success of these activities on industrial scale large scale production of TEMs is needed. The availability of heavy ion accelerator made possible the production of TEMs in wide range of sizes. Many countries have set up facilities for continuous production of TEMs. BARC-TIFR Pelletron Accelerator at Mumbai delivers MeV energies of heavy ions for research in basic as well as applied sciences. Heavy ions of various species and energies from BARC-TIFR Pelletron Accelerator were used to make TEMs using polyethylene terephthalate (PET/Mylar) films of 25 micron thickness. The films used were procured from reputed manufactures in India

Research and development work on NAA at RCD, BARC

International Nuclear Information System (INIS)

Acharya, R.; Nair, A.G.C.; Burte, P.P.; Sudarshan, K.; Pandey, A.K.; Scindia, Y.M.; Goswami, A.; Reddy, A.V.R.; Manohar, S.B.

2006-01-01

Radiochemistry Division is engaged in R and D using NAA. They have standardized single comparator method of NAA called k 0 -based NAA using different irradiation sites of reactors at BARC Trombay. In addition, methodologies for large sample analysis, internal mono standard NAA and chemical NAA namely radiochemical, derivative and speciation NAA have been developed and are being used in different R and D works. The work on k 0 NAA and chemical NAA carried out till date are described in brief

Development of hybrid micro circuit based multi-channel programmable HV supply for BARC-pelletron experimental facility

International Nuclear Information System (INIS)

Manna, A.; Thombare, S.; Moitra, S.; Kuswarkar, M.; Punna, M.; Nair, P.M.; Diwakar, M.P.; Pithawa, C.K.

2013-01-01

Electronics Division, BARC has developed a Multi channel programmable HV bias supply system for charge particle detector array for use in BARC-TIFR Pelletron-LINAC facility. The HV supplies are compact in size due to use of hybrid micro-circuits developed indigenously and are modular in construction to achieve versatility, scalability and serviceability. All programming operations and monitoring are performed remotely through PC over Ethernet. Each supply has a built-in over voltage, over current and thermal overload protections for safe operation and employs a Zero Voltage Switching (ZVS) technique to reduce thermal stress on the inverter switches. This article describes salient design aspects and performance of the HV supply system. (author)

Bhabha Atomic Research Centre (BARC) annual report 1985-86

International Nuclear Information System (INIS)

1987-01-01

The research and development (R and D) activities and accomplishments during the financial year 1985-86 of the Bhabha Atomic Research Centre, Bombay are reported. The BARC is a multidisciplinary laboratory engaged in R and D activities in the field of nuclear energy. The main thrust of the R and D activities of the Centre is aimed at: (1) achieving targets of India's nuclear power programme, (2) indigenisation of the various steps in the nuclear fuel cycle, (3) developing and propagating peaceful applications of nuclear science and technology in the country in fields such as agriculture, medicine and industry, (4) providing scientific support to regulatory functions associated with nuclear facilities and radiation protection activities in the country. The salient features of these R and D activities are described in the chapters entitled: (1) physical sciences, (2) chemical sciences, (3) materials and materials sciences, (4) life sciences, (5) radioisotopes, (6) reactors, (7) fuel cycle, (8) health and safety, (9) electronics and instrumentation, and (10) technical services. A list of publications by the staff-members during the report period is given at the end of each chapter. The R and D activities of the outstation units of BARC, namely, Nuclear Research Laboratory at Srinagar, High Altitude Research Laboratory at Gulmarg, Variable Energy Cyclotron Centre at Calcutta and Gauribidanur Seismic Array near Bangalore are also covered in the report. Other activities of the Centre include technology transfer and manpower training which are also described briefly. (M.G.B.)

6 MV Folded Tandem Ion Accelerator facility at BARC

International Nuclear Information System (INIS)

Gupta, S.K.

2010-01-01

The 6 MV Folded Tandem Ion Accelerator (FOTIA) facility is operational round the clock and accelerated beams of both light and heavy ions are being used extensively by various divisions of BARC, Universities, lIT Bombay and other R and D labs across the country. The FOTIA is an upgraded version of the old 5.5 MV single stage Van-de-Graaff accelerator (1962-1992). Since its commissioning in the year 2000, the poor beam transmission through the 180 deg folding magnet was a matter of concern. A systematic study for beam transmission through the accelerator was carried out and progressive modifications in folding magnet chamber, foil stripper holder and improvement in average vacuum level through the accelerator have resulted in large improvement of beam transmission leading to up to 2.0 micro-amp analyzed proton beams on target. Now the utilization of the beams from the accelerator has increased many folds for basic and applied research in the fields of atomic and nuclear physics, material science and radiation biology etc. Few new beam lines after the indigenously developed 5-port switching magnet are added and the experimental setup for PIXE, PIGE, External PIXE, 4 neutron detector, Proton Induced Positron Annihilation Spectroscopy (PIPAS) setup and the general purpose scattering chamber etc have been commissioned in the beam hall. The same team has developed a Low Energy Accelerator Facility (LEAF) which delivers negative ions of light and heavy ions for application in implantation, irradiation damage studies in semiconductor devices and testing of new beam line components being developed for Low Energy High Intensity Proton Accelerator (LEHIPA) programme at BARC. The LEAF has been developed as stand alone facility and can deliver beam quickly with minimum intervention of the operator. Few more features are being planned to deliver uniform scanned beams on large targets. (author)

R and D in vibration engineering at BARC

International Nuclear Information System (INIS)

Bhattacharjee, B.

2002-01-01

A comprehensive capability for design, experimental verifications to validate the computational codes involved in the vibration analysis of highly complex structures, equipment and piping belonging to all seismic categories have been firmly established at BARC. All the major pending issues in seismic design, viz ground motion, damping of piping system, design rules for piping and requalification and retrofitting of existing nuclear facilities are being rigorously pursued for enhancing the current level of knowledge base for seismic analysis through experimental verification of the theoretical models of the seismic behaviours of various structures, equipment and piping system. This has not only enabled requalification and retrofitting in the existing nuclear facilities for their usage over extended life span without compromising the safety but also led to development of various special devices for seismic response control design

Proceedings of the national symposium on BARC technologies for development of rural India

International Nuclear Information System (INIS)

Mishra, R.K.; Wadawale, Amey; Bhadauria, Y.S.; Joseph, Daisy; Kumar, Manoj; Girija, K.G.; Gautam, S; Rawat, A.S.; Misra, S.K.

2009-01-01

For empowering Indian villages, science and technology (S and T) based eco-friendly work plan have to be evolved. Sustainable techno-economic growth of rural sector in a country of vast size such as India requires technology innovations and their ingenious adaptation. This can be achieved to a great extent by adopting such technologies for varied local conditions so that it can be applied quickly to enhance the quality of life of larger population. Considering the wealth of technology and innovative capability generated in BARC, as an off-shoot of R and D in nuclear energy and its applications in power and non-power areas, Department of Atomic Energy (DAE), India has launched - Societal Initiative for utilization of Non-Power Applications (NPAs) and Spin off technologies (Spin-offs) in the area of water, land, agriculture, food processing and urban-rural waste management. Within this framework of societal initiative, structured programme called 'AKRUTI - KRUTIK - FORCE' has been formulated and is being implemented by BARC for techno-economic growth of the rural sector, as one of the many schemes for large-scale deployment of NPAs and spin-offs. This symposium consisting of invited lectures and poster presentations covered the topics like food and agriculture, health and environment, energy and conservation. Papers relevant to INIS are indexed separately

Indigenous development and performance evaluation of BARC aerodynamic size separator (BASS)

International Nuclear Information System (INIS)

Singh, Sanjay; Purwar, R.C.; Das, Tanmoy; Narayanan, K.P.; Sapra, B.K.; Sunny, Faby; Khan, Arshad; Mayya, Y.S.

2002-06-01

Commercially available cascade impactors, commonly used for aerodynamic size separation of aerosol particles, are based on the principle of inertial impaction. As of now, these instruments are imported at a cost of several lakhs of rupees; hence an effort has been made to develop an aerodynamic particle sizer indigenously in BARC. This unit, referred to as BARC Aerodynamic Size Separator (BASS), separates aerosols into seven size classes ranging from 0.53 μm to 10 μm and operates at a flow rate of 45 Ipm. Intercomparison studies between the standard Andersen Mark-II (Grasbey Andersen Inc.) impactor and BASS using nebulizer generated aerosols have consistently shown excellent performance by BASS in all respects. In particular, BASS yielded the parameters of polydisperse aerosols quite accurately. Experiments to evaluate the individual stage cut-off diameters show that these are within 8% of their designed value for all stages except the higher two stages which indicate about 30% lower values than the designed ones. The replotting of all the mass distribution data using the experimental cut-off diameters showed perfect lognormal fits, thereby indicating that these diameters are closer to the true stage cut-off diameters for BASS. The studies show that BASS will be suitable for determining the particle size distributions in the context of the radiological safety programmes of DAE. Being indigenous in design, it may be fabricated on a commercial scale at a cost far less than that of the imported units. Such a venture will greatly help several national programmes on atmospheric pollution being carried out by many laboratories and institutions across the country. (author)

Setting up of a PIXE facility at FOTIA at BARC

International Nuclear Information System (INIS)

Joseph, Daisy; Saxena, A.

2005-01-01

PIXE-(Proton Induced X-ray Emission) -an ideal technique for material characterization has been set up at the Folded Tandem Ion Accelerator (FOTIA) at BARC, Trombay. A separate beam line at 45 deg port in which a dedicated PIXE chamber has been installed is being used for PIXE studies. PIXE studies on gold standards were carried out using protons of energy 3.3 MeV. Caritage values of gold standards were obtained which agree well with the certified values. Single element standard solutions (100 μg/ml) for low-Z elements such as Cr, Mn, Fe, Co, Cu and Zn were analyzed by PIXE. Well resolved α and β components of the x-rays were seen with detection limits in the range of 0.8-4 μg/g. (author)

Installation and commissioning of Scandiflash-450 flash X-ray generator at BARC, Visakhapatnam

International Nuclear Information System (INIS)

Banerjee, P.; Verma, R.; Shukla, R.; Sharma, S.K.; Das, B.; Prabaharan, T.; Deb, P.; Das, R.; Adhikary, B.; Meena, M.; Sagar, K.; Shyam, A.

2014-08-01

Energetics and Electromagnetics Division, BARC, Visakhapatnam has possessed a Flash X-ray radiography (FXR) system, make: Scandiflash, Sweden. This installation and commissioning of the system has been done by ourselves. Few problems have been detected during installation and commissioning. The troubleshooting of the system has been done. Somewhere we needed to replace the original components by indigenously made one. The complete installation and commissioning has been reportedly as far as detailed possible. Presently the system is working with satisfaction. The installed facility is being used as one of the primary means of diagnostics in many of the ongoing experiments. (author)

Proceedings of the national symposium on BARC technologies for development of rural India

International Nuclear Information System (INIS)

2013-01-01

Empowering villages with Science and Technology (S and T) based on eco-friendly work plan for sustainable Techno-Economic growth of rural sector in a country of vast size, technology innovations and adaptations have to be evolved. This can be achieved to a great measure particularly since such technology will fit with varied local conditions and can be applied quickly to enhance the quality of life of larger population. Considering the wealth of technology and innovative capability generated in BARC, as an off-shoot of R and D in Nuclear Energy and its applications in power and non-power areas, Department of Atomic Energy (DAE) has launched - Societal Initiative for utilization of Non-Power Applications (NPAs) and Spinoff technologies (Spinoffs) in the area of water, land, agriculture, food processing and urban-rural waste management. Within this framework of societal initiative, structured programme called 'AKRUTI - KRUTIK - FORCE' has been formulated and is being implemented by BARC for techno-economic growth of the rural sector, as one of the many schemes for large-scale deployment of NPAs and spinoffs. Bhabha Atomic Research Centre Officer's Association (BARCOA) is making a maiden attempt to hold a symposium where the scientists, technologists, agriculturists and the consumers will come on a common platform to discuss these issues. This symposium is organized to enable to take the fruits of technology to grass-root level to every villager in the remote corner and provide inclusive growth to the rural sector and tap the hidden innovative capability of large rural India. This symposium describes the various technologies developed indigenously by Bhabha Atomic Research Centre for the development of rural India. Papers relevant to INIS are indexed separately

Fenceline water quality monitoring of effluents from BARC establishment

International Nuclear Information System (INIS)

Prathibha, P.; Kothai, P.; Saradhi, I.V.; Pandit, G.G.; Puranik, V.D.

2007-01-01

Wastewater generated from various sources (industrial, residential, rain water runoff etc.,) is either discharged into water bodies or reused/recycled for various purposes. Continuous monitoring of the wastewater is necessary to check whether these effluents are meeting the stringent limits proposed for discharge into water bodies or recycled/reused. Monitoring of these effluents also helps in designing the wastewater treatment system required to meet the standards. In this paper, water quality monitoring carried out during each quarter of the year 2005 for the effluents discharged from different utilities of BARC into Trombay bay is presented. The results indicate that the Bio-chemical oxygen demand (BOD) and chemical oxygen demand (COD) are in the range of 7.9 to 38.9 mg/l and 29.4 to 78.9 mg/l respectively. The nitrates and sulphates are in the range of 0.5 to 7.2 mg/l and 7.8 to 52.3 mg/l respectively. The water quality data of the parameters analyzed are well within the limits stipulated by Central Pollution Control Board. (author)

Beam transport calculations for BARC-TIFR 14UD pelletron

International Nuclear Information System (INIS)

Prasad, K.G.

1993-01-01

The 14UD pelletron tandem accelerator installed at Tata Institute of Fundamental Research (TIFR) as a joint BARC-TIFR project, is supplied by National Electrostatic Corporation (NEC), U.S.A. To optimise the parameters of various elements along the beam path, it is essential to work out the beam optics of the entire system. There are various computer codes in use for such calculations. All these codes, except the detailed ray tracing programs, use matrix formulation. Thus each ion optical element is characterised in terms of a transport matrix, whose elements are assumed to be independent of particle trajectory. We have performed only the first order calculations, meaning thereby that no aberrations are included. Further, all calculations are carried out assuming ideal conditions like axial beam injection, perfectly aligned beam line elements, etc. The main code that has been employed in our calculations is based on the one at the Australian National University, Canberra, suitably modified for use with CYBER 170/730 computer at TIFR. However, codes at NEC and Stony Brook were also used for the checking the results. The results of calculations are given and discussed. (author). 2 figs

Hot target assembly at 14 UD Pelletron Accelerator Facility, BARC- TIFR, Mumbai

International Nuclear Information System (INIS)

Sharma, S.C.; Ramjilal; Ninawe, N.G.; Bhagwat, P.V.; Ahmeabadhai, P.; Kain, V.

2005-01-01

BARC-TIFR 14 UD Pelletron Accelerator Facility at Mumbai is operational since 1989 with progressively increased efficiency. The accelerator has been serving as major facility for heavy ion based research in India. There is an increased demand for high current proton beam, especially on heated targets for reactor physics based experiments. A proton beam setup is commissioned in the tower area of the existing facility itself, which provide proton beam of energy 2 MeV to 26 MeV with maximum 3 μA current. This setup is being used to produce radioisotopes and tracer packets. Proton beam of few MeV in μA current range is also needed to study radiation effects on metals at higher temperature, for use in reactors. For this purpose a hot target assembly has been designed and is being currently used at the Pelletron Accelerator

Hydrogen related safety issues in the context of containments of Indian PHWRs

International Nuclear Information System (INIS)

Markendeya, S.G.; Ghosh, A.K.; Kushwaha, H.S.; Venkat Raj, V.

2002-01-01

Full text: Assessment of risk due to hydrogen released during postulated hypothetical accident scenarios in the nuclear power plants (NPPs) has been an important area of R and D studies world over. The issues, such as appropriate methodologies for estimation of hydrogen source term and for hydrogen dispersion calculations, technology development for hydrogen mitigation in containment of NPPs and assessment of damage due to deflagration/detonation of hydrogen (if it occurs) are being addressed as a part of some of the multidisciplinary study programs currently underway in BARC. While a significant overall progress has been achieved in general as a result of these programs, requirements of further fine-tuning of these studies have also emerged. The present paper takes a brief look at the current state-of the-art technology available to address these issues. The progress of R and D studies underway at BARC has also been critically reviewed in the paper to bring out necessary planning of further studies so as to enhance the safety of Indian NPPs

Modification in existing SF6 gas handling system at 14UD BARC-TIFR Pelletron Accelerator, Mumbai

International Nuclear Information System (INIS)

Ninawe, N.G.; Gupta, S.K.; Ramjilal; Sparrow, Hillary; Sharma, S.C.; Bhagwat, P.V.; Salvi, S.B.

2003-01-01

BARC-TIFR 14 UD Pelletron Accelerator facility at TIFR, Mumbai is operational since inception 1989. The accelerator is housed inside a pressure vessel of 6 metre diameter, 25 metre long and 525m 3 volume. The accelerator tank is pressurized with SF 6 at 80 to 100 psig in order to achieve 14MV. The inventory of SF 6 gas is about 18,000 Kg (approximately) at 80 psig. SF 6 gas can be transported from Accelerator tank to storage tank using gas handling system, which consists of oil free compressor, vacuum pump, dust filters, oil filters, dryers etc

BARC golden jubilee and DAE-BRNS life sciences symposium 2006 on trends in research and technologies in agriculture and food sciences: abstracts

International Nuclear Information System (INIS)

2006-01-01

Better methods of agricultural production, availability of hybrid and mutant varieties of crop plants, irrigation, fertilizers and pesticides have all helped boost up agricultural production, and famines and droughts remain restricted to a few pockets in the world. Innovative approach to step up agricultural production, especially of food crops symbolize synergy and synthesis of conventional and mutation breeding aided by modern biotechnological tools like DNA markers and gene manipulation in tune with the policy of environmental and soil conservation. It has increased the production of oil seeds in India during the last decade with a shift from groundnut and mustard to soybean and sunflower. Bhabha Atomic Research Centre (BARC), Mumbai which has strongly pursued the important societal programmes using nuclear technology in agriculture and health, has made a very significant impact on the country's agriculture by developing 27 new crop varieties mostly of oil seeds and pulses. Further, radiation processing of food, pioneered in India by BARC, is now gaining global acceptance and has opened new vistas for agriculture exports. The present symposium is dedicated to trends in research of technologies in agriculture and food sciences. The papers relevant to INIS are indexed separately

Comparative study on TSPM levels, anions and trace metal concentrations at BARC during the years 2000-2002

International Nuclear Information System (INIS)

Saradhi, I.V.; Prathibha, P.; Kothai, G.; Mahadevan, T.N.; Venkat Raj, V.; Kumar, Shaji C.

2003-01-01

Both total and respirable suspended particulate matter in the ambient air of Mumbai have been identified as the single largest pollutant associated with the health impacts in the community. This study deals with the extensive monitoring work carried out at BARC, Trombay during the period 2000-2002. The paper also deals with the comparative status of the TSPM levels and select trace metal and anion concentrations. While Pb levels have stabilized over the years following the introduction of unleaded gasoline, sulphate as a major contributor in the fine fraction of SPM assumes importance. The possible source profiles are presented and discussed. (author)

Integrated safety assessment of Indian nuclear power plants for ...

Indian Academy of Sciences (India)

to minimize release of radioactivity and avoid serious impact in public domain. A .... a large number of experimental programs, round robin exercises, benchmarks ...... numerical codes with BARCOM test data in terms of the loss of pre-stress in.

Development of a compact 25-channel preamplifier module for Si-pad detectors of the BARC-CPDA

International Nuclear Information System (INIS)

Inkar, A.; John, Bency; Vind, R.P.; Kinage, L.; Jangale, R.V.; Biswas, D.C.; Nayak, B.K.

2011-01-01

The BARC Charged Particle Detector Array modules use indigenously developed Si pad detectors as their first element. Total number of charge sensitive pre-amplifiers required for the Si-pad detectors is 250. One of the main ideas here is a layout of five pre-amplifiers connected with one Si-pad detector (called a bank of preamplifiers). In the present work, a 25-channel pre-amplifier module that can cater to 5 independent Si-pad detectors, or a five-bank module, has been developed. This module uses pre-amp hybrid chips A1422H from CAEN S.p.A. and is housed in a double width NIM standard box. The module has been tested for performance using proton and ''7Li beams from FOTIA facility, Trombay

Containment aerosol behaviour simulation studies in the BARC nuclear aerosol test facility

International Nuclear Information System (INIS)

Mayya, Y.S.; Sapra, B.K.; Khan, Arshad; Sunny, Faby; Nair, R.N.; Raghunath, Radha; Tripathi, R.M.; Markandeya, S.G.; Puranik, V.D.; Ghosh, A.K.; Kushwaha, H.S.; Shreekumar, K.P.; Padmanabhan, P.V.A.; Murthy, P.S.S.; Venlataramani, N.

2005-02-01

A Nuclear Aerosol Test Facility (NATF) has been built and commissioned at Bhabha Atomic Research Centre to carry out simulation studies on the behaviour of aerosols released into the reactor containment under accident conditions. This report also discusses some new experimental techniques for estimation of density of metallic aggregates. The experimental studies have shown that the dynamic densities of aerosol aggregates are far lower than their material densities as expected by the well-known fractal theory of aggregates. In the context of codes, this has significant bearing in providing a mechanistic basis for the input density parameter used in estimating the aerosol evolution characteristics. The data generated under the quiescent and turbulent conditions and the information on aggregate densities are now being subjected to the validation of the aerosol behaviour codes. (author)

Medium energy heavy ion accelerator 14 UD Pelletron- a BARC-TIFR facility: a 5 year progress report 1989-1994

International Nuclear Information System (INIS)

Chatterjee, A.; Tandon, P.N.

1995-01-01

The medium energy heavy ion accelerator (MEHIA) facility based on 14 UD Pelletron set up under the collaborative project of Bhabha Atomic Research Centre (BARC) and Tata Institute of Fundamental Research (TIFR) at the TIFR campus at Bombay has been serving as a joint BARC-TIFR facility for heavy-ion accelerator based research. As this accelerator has just completed five years of its successful operations, it has been thought to be an appropriate time to bring out a report of the research work carried out with the accelerator facility over these last five years. To put the research work in proper perspective, the present report is formatted to provide a short write-up highlighting the work carried out in each area of activity along with a list of the publications which have resulted from these investigations. Some theoretical work related to the experimental activities with the pelletron accelerator has also been included in the list of publications. The research work in the area of nuclear physics, which forms the main thrust of the research activities with the accelerator, covers areas of high spin states, high energy photons, resonances in heavy ion reactions, heavy ion elastic and transfer reactions, heavy ion fusion-fission reactions and radiochemical studies in heavy ion reactions. The interdisciplinary areas of research include condensed matter physics and accelerator based atomic physics. In addition to the above topics the present report also describes the work related to the pelletron accelerator and associated experimental facilities, gas detector development work, data acquisition systems and spectrometer for heavy recoil ions under development. The present status of the superconducting Linac booster project is also briefly described. (author). refs., tabs

Development and validation of computer codes for analysis of PHWR containment behaviour

International Nuclear Information System (INIS)

Markandeya, S.G.; Haware, S.K.; Ghosh, A.K.; Venkat Raj, V.

1997-01-01

In order to ensure that the design intent of the containment of Indian Pressurised Heavy Water Reactors (IPHWRs) is met, both analytical and experimental studies are being pursued at BARC. As a part of analytical studies, computer codes for predicting the behaviour of containment under various accident scenarios are developed/adapted. These include codes for predicting 1) pressure, temperature transients in the containment following either Loss of Coolant Accident (LOCA) or Main Steam Line Break (MSLB), 2) hydrogen behaviour in respect of its distribution, combustion and the performance of proposed mitigation systems, and 3) behaviour of fission product aerosols in the piping circuits of the primary heat transport system and in the containment. All these codes have undergone thorough validation using data obtained from in-house test facilities or from international sources. Participation in the International Standard Problem (ISP) exercises has also helped in validation of the codes. The present paper briefly describes some of these codes and the various exercises performed for their validation. (author)

Search for the Pentaquark via the Decay $P^0_{\\bar{c}s} \\to \\phi \\pi \\rho$

Energy Technology Data Exchange (ETDEWEB)

Beck, S.Maytal [Tel Aviv U.

1998-01-01

This work reports results of the first search for the pentaquark, which is predicted to be a doublet of states: $P^0_{\\bar{c}s} = \\mid \\bar{c}suud$ > and $P^-_{\\bar{c}s}$ = $\\mid \\bar{c}sddu>$. The color hyperfine interaction between their constituent quarks results in a maximal binding potential of 150 MeV. Calculations done using other models predict that the pentaquark is either bound or is a near-threshold resonance. A bound pentaquark would have a mass below 2.907 GeV /$c^2$ and its lifetime would be like that of other charm particles, of the order of $10^{-13}$ s. Crude estimates of the pentaquark production cross section predict values of the order of 1 % of that of the $D_s$. Observation of the pentaquark is interesting for its unusual structure and would contribute to the understanding of QCD and the concept of confinement....

Automation and remote handling activities in BARC: an overview

International Nuclear Information System (INIS)

Badodkar, D.N.

2016-01-01

Division of Remote Handling and Robotics, BARC has been working on design and development of various application specific remote handling and automation systems for nuclear front-end and back-end fuel cycle technologies. Division is also engaged in preservice and in-service inspection of coolant channels for Pressurized Heavy Water Reactors in India. Design and development of Reactor Control Mechanisms for Nuclear Research and Power Reactors (PHWRs and Compact LWRs) is another important activity carried out in this division. Robotic systems for Indoor and Outdoor surveillance in and around nuclear installations have also been developed. A line scan camera based system has been developed for measuring individual PHWR fuel pellet lengths as well as stack length. An industrial robot is used for autonomous exchange of pellets to achieve desired stack length. The system can be extended for active fuel pellets also. An automation system has been conceptualized for remote handling and transfer of spent fuel bundles from storage pool directly to the chopper unit of reprocessing plant. In case of Advanced Heavy Water Reactor which uses mixed oxides of (Th-Pu) and (Th-"2"3"3U ) as fuel, automation system for front-end fuel cycle has been designed, which includes Powder processing and pressing; Pellet handling and inspection; Pin handling and inspection; and Cluster assembly and dis-assembly in shielded facilities. System demonstration through fullscale mock-up facility is nearing completion. Above talk is presented on behalf of all the officers and staff of DRHR. The talk is mainly focused on development of an automated fuel fabrication facility for mixed oxides of (Th- Pu)/(Th-"2"3"3U ) fuel pins. An overview of divisional ongoing activities in the field of remote handling and automation are also covered. (author)

Comparison of aerosol inhalation lung images using BARC and other nebulizers

International Nuclear Information System (INIS)

Isawa, Toyoharu; Teshima, Takeo; Anazawa, Yoshiki; Miki, Makoto

1994-01-01

Various factors determine the site of inhaled aerosol deposition in the lungs. They are the size of aerosol the composition of carrier gas of the aerosol, the airflow rate, physico-chemical properties of the carrier gas or the aerosol, the shape and structure of the airways, and the body position during inhalation. Aerosol inhalation lung images were obtained in the same subjects using 99m Tc-human serum albumin aerosol generated by 3 different aerosol generators each producing different-sized aerosol and 2 or 3 days apart from each study. The size of aerosol produced by an ultrasonic nebulizer (Mistogen) was 1.93 Micron in activity median aerodynamic diameter (AMAD) with its geometric standard deviation (σg) of 1.73, that by a jet nebulizer (Ultra Vent) was 1.04 micron in AMAD with its σg of 1.71, and that by our BARC nebulizer, a type of a jet nebulizer, was 0.84 micron in AMAD with its σg of 1.73. In addition Technegas was also applied to selected patients. The latter produced aerosol of less than 0.2 micron in size at the largest and the majority, say, 95% or more of the generated aerosol was less than 0.1 micron in size by electron Microscopy. Each subject inhaled aerosol in resting tidal breathing through a mouth-piece with a one way double J valve with the nose clipped in the sitting position. After inhaling approximately 2-3 mCi (74 to 111 MBq) in the thorax, four view lung images were taken: anterior, posterior, and right and left laterals. 300 K counts per view were collected. They were not only pictured on polaroid films as analogue data but also recorded and stored in a computer as digital data. In case of Technegas breathing it for the RV (residual volume) to the TLC (total lung capacity) level followed by breath-holding for 5 to 10 sec in duration was repeated 2 to 3 times as a breathing maneuver instead of tidal breathing. Otherwise deposition efficiency of Technegas is very little because of the small size of the Technegas. Representative 10

Research on refractory, reactive and rare metals in BARC

International Nuclear Information System (INIS)

Banerjee, Srikumar

2016-01-01

-metallics for specific applications. The presentation will essentially attempt to give an account of the development of refractory, reactive and rare metals in BARC over the period of nearly fifty years. (author)

Detection of radioactive material in public places: BARC's handheld tele radionuclide detector

International Nuclear Information System (INIS)

Bharade, S.K.; Sinha, Vineet; Vinod, M.; Ananthakrishnan, T.S.; Jindal, G.D.; Srivastava, Shikha; Sarade, Bhagyashree; Kamble, Ashok D.; Pithawa, C.K.; Subramanian, Venkat

2011-01-01

Electronics Division, BARC has developed a compact and portable system for detection of radioactive nuclides like 60 Co, 137 Cs etc. with high levels of radioactivity. These radioactive sources, because of their long life and relative ease of availability, have the potential of being used in radiological dispersion devices (dirty bombs) for panic creation in public places. The unit comprises of a compact CsI detector, photo diode and front-end electronics, micro-controller, a GPS module and Blue-tooth connectivity. The application software running on the mobile phone provides the interface as well as transmission of data to remote server. This is highly suitable for covert operations. The person, who carries this instrument, suitably camouflaged, also has a mobile phone in his pocket, which is connected to the system via blue tooth. On detection of activity above set limit, the system sends an alarm to the mobile phone. The mobile phone can be kept in vibration mode in order to avoid any undue attention. The graphical display on screen of mobile phone provides an indication of activity and the isotope identification. Simultaneously, the mobile phone sends information about the activity detected and source identification automatically along with the location of the instrument (longitude and latitude), provided by the GPS module in the instrument, to a remote server. The remote server provides radiation information on a map with position-coordinates. Based on this, necessary action can be initiated by the security personnel. (author)

Application of smart differential pressure transmitters (DPTS) for containment studies facility (CSF)

International Nuclear Information System (INIS)

Shanware, V.M.; Gole, N.V.; Sebastian, A.; Subramaniam, K.

2001-01-01

Containment Studies Facility (CSF) is being set up in BARC for studying various containment related thermal hydraulic and other processes during simulated conditions of pipe rupture. The set up consists of a model reactor containment vessel with a model primary heat transport system. Besides, provisions exist to introduce aerosols and hydrogen also in the containment model. The instrumentation includes measurement of the process temperatures, pressures, levels, flows, humidity, etc. Differential Pressure Transmitters (DPT) will be used for measurement of levels and flows in the CSF. The procured DPTs for this facility are smart. Conventional transmitters have a rangeability specification of 5 or 6. But the smart transmitters have rangeability varying between 40-100. Smart transmitters have facility to change its operating range online. This enables the provision of zooming in on the selected range and narrowing the range around the point of measurement. This facility can be exploited to realise the maximum possible accuracy at the smallest possible range around the point of measurement. This paper describes how the smart DPTs function, how the Highway Addressable Remote Transmitter (HART) protocol works and how we propose to use the on-line rangeability of these DPTs get the highest resolution in our measurements. (author)

Mutation induction, evaluation and utilization for development of high yielding varieties in Indian mustard and sunflower: an overview of BARC work

International Nuclear Information System (INIS)

Jambhulkar, S.J.; Shitre, A.S.

2009-01-01

Mutation breeding programme in Indian mustard and sunflower at BARC has resulted into the development of wide spectrum of mutations for seed coat colour, chlorophyll, plant height, maturity, flower morphology, seed weight and oil content. In Indian mustard, TM1 and TM50 are high yielding yellow seed coat mutants, which were exploited in hybridisation to develop bold, yellow seed coat and high yielding genotypes. Light green leaf and variegated leaf are novel mutation in mustard. Putative mutants for drought tolerance have been isolated. Variability for zero erucic acid and zero glucosinolates genotypes have been developed in B. napus and B. juncea. In sunflower, high yielding black seed coat mutant were isolated. Extreme dwarf measuring only 11 cm is novel. Three high yielding varieties namely TM2, TM4, and TPM1 in mustard and one i.e.TAS82 in sunflower have been released for cultivation in collaboration with state agricultural universities. (author)

The prognostic value of bleeding academic research consortium (BARC)-defined bleeding complications in ST-segment elevation myocardial infarction: a comparison with the TIMI (Thrombolysis In Myocardial Infarction), GUSTO (Global Utilization of Streptokinase and Tissue Plasminogen Activator for Occluded Coronary Arteries), and ISTH (International Society on Thrombosis and Haemostasis) bleeding classifications

NARCIS (Netherlands)

Kikkert, Wouter J.; van Geloven, Nan; van der Laan, Mariet H.; Vis, Marije M.; Baan, Jan; Koch, Karel T.; Peters, Ron J.; de Winter, Robbert J.; Piek, Jan J.; Tijssen, Jan G. P.; Henriques, José P. S.

2014-01-01

The aim of the present analysis was to compare 1-year mortality prediction of Bleeding Academic Research Consortium (BARC)-defined bleeding complications with existing bleeding definitions in patients with ST-segment elevation myocardial infarction (STEMI) and to investigate the prognostic value of

Pre-test analysis results of a PWR steel lined pre-stressed concrete containment model

International Nuclear Information System (INIS)

Basha, S.M.; Ghosh, Barnali; Patnaik, R.; Ramanujam, S.; Singh, R.K.; Kushwaha, H.S.; Venkat Raj, V.

2000-02-01

Pre-stressed concrete nuclear containment serves as the ultimate barrier against the release of radioactivity to the environment. This ultimate barrier must be checked for its ultimate load carrying capacity. BARC participated in a Round Robin analysis activity which is co-sponsored by Sandia National Laboratory, USA and Nuclear Power Engineering Corporation Japan for the pre-test prediction of a 1:4 size Pre-stressed Concrete Containment Vessel. In house finite element code ULCA was used to make the test predictions of displacements and strains at the standard output locations. The present report focuses on the important landmarks of the pre-test results, in sequential terms of first crack appearance, loss of pre-stress, first through thickness crack, rebar and liner yielding and finally liner tearing at the ultimate load. Global and local failure modes of the containment have been obtained from the analysis. Finally sensitivity of the numerical results with respect to different types of liners and different constitutive models in terms of bond strength between concrete and steel and tension-stiffening parameters are examined. The report highlights the important features which could be observed during the test and guidelines are given for improving the prediction in the post test computation after the test data is available. (author)

Effect of ThO2 concentration on thermo-physical properties of barium borosilicate glass

International Nuclear Information System (INIS)

Mishra, R.K.; Munshi, A.K.; Kaushik, C.P.; Raj, Kanwar; Shobha, M.; Srikhande, V.K.; Kothiyal, G.P.; Tyagi, A.K.

2006-01-01

An advanced heavy water reactor is being developed at Bhabha Atomic Research Centre (BARC) India with an aim of utilizing thorium for power generation. The high level radioactive liquid waste (HLW) generated from reprocessing of Th-based spent fuel is expected to contain Th as one of the main constituents other than fission products, corrosion products, actinides and added chemicals. Barium borosilicate (BBS) glass is being used for vitrification of the HLW generated at the reprocessing plant at BARC, Trombay, Mumbai

Development and deployment of BARC Vessel Inspection System (BARVIS) for TAPS-1 and 2

International Nuclear Information System (INIS)

Singh, Jit Pal; Ranjon, R.; Kulkarni, M.P.; Soni, N.L.; Patel, R.J.

2016-01-01

As per regulatory requirements, inspection of welds in Reactor Pressure Vessel (RPV) is necessary for further continuing operation of TAPS - 1 and 2. Upper shell longitudinal welds of RPV which were seen as inaccessible up till now have been inspected first time since operation of the reactors by deploying Weld Inspection Manipulator (WIM) in Unit-1 in August 2012. Subsequently Unit-2 and again Unit-1 upper shell welds were inspected with upgraded versions of WIM in Feb 2013 and March 2015 respectively. Inspection of upper shell welds paves the way for more challenging inspection of beltline region welds. These welds are accessible only from Inside Diameter (JD) surface through a narrow annular gap of 25 mm between RPV wall and thermal shield by managing obstructions due to core internals. BARC Vessel Inspection System (BARVIS) for inspection of beltline region welds from inner side of the RPV was designed, manufactured, tested and qualified for sending scanning probes in to the annular gap of 25mm as per RPV engineering drawings and also based on actual gap measured in Unit-2. Annular gap measurement was done in Units-1 before deployment of BARVIS during 25 th Refuelling Outage (RFO) in Unit-1. Contrary to the expectation, the annular gap was found less and inspection of beltline region with BARVIS in Unit-1 could not be done. Finally during RFO in January 2016 of Unit-2, BARVIS has been successfully deployed for beltline region welds inspection. BARVIS mainly consists of manipulator, its operating system and data acquisition system. Data acquisition system and data analysis are not covered in this report. (author)

Development of AUC-based process at BARC for production of free-flowing and sinterable UO2 powder

International Nuclear Information System (INIS)

Keni, V.S.; Ghosh, S.K.; Ganguly, C.; Majumdar, S.

1994-01-01

Ammonium uranium carbonate (AUC) process has been developed and industrially used in Germany for preparation of free-flowing and sinterable UO 2 powder for fabrication of UO 2 fuel pellets for light water reactors (LWR). Efforts are underway at Bhabha Atomic Research Centre (BARC) for developing AUC-based process which would yield free-flowing UO 2 powder suitable for direct pelletisation and sintering to very high density (> 96% T.D.) UO 2 fuel pellets for pressurised heavy water reactors (PHWRs) in India. The first phase of this work has been completed jointly by Chemical Engineering Division (ChED) and Radiometallurgy Division (RMD) in batches of 1.5 kg. It was possible to fabricate UO 2 pellets of density 93-95% T.D. on a reproducible basis. At ChED, process parameters have been optimised for fabrication of AUC with suitable physical properties in batches of 1.5 kg (U), starting with nuclear pure uranyl nitrate solution. At RMD calcination parameters of AUC was optimised in batches of 500 g for obtaining free-flowing UO 2 powder, suitable for direct pelletisation and sintering. The pelletisation and sintering have been carried out at Radiometallurgy Division in batches of 1-1.5 kg. The maximum achievable density of UO 2 pellets has been in the range of 95.5-96% T.D. (author). 11 refs

Technology transfer from nuclear research

International Nuclear Information System (INIS)

1989-01-01

A number of processes, components and instruments developed at the Bhabha Atomic Research Centre, (BARC), Bombay, find application in industry and are available for transfer to private or public sector undertakings for commercial exploitation. The Technology Transfer Group (TTG) constituted in January 1980 identifies such processes and prototypes which can be made available for transfer. This catalogue contains brief descriptions of such technologies and they are arranged under three groups, namely, Group A containing descriptions of technologies already transferred, Group B containing descriptions of technologies ready for transfer and Group C containing descriptions of technology transfer proposals being processed. The position in the above-mentioned groups is as on 1 March 1989. The BARC has also set up a Technology Corner where laboratory models and prototypes of instruments, equipment and components are displayed. These are described in the second part of the catalogue. (M.G.B.)

List of participants

Indian Academy of Sciences (India)

List of participants. Abbas Sohrab, BARC, Mumbai, India. Achary S N, BARC, Mumbai, India. Acharya Prashant G, JMS College, Ahmedabad, India. Aggarwal S K, BARC, Mumbai, India. Agrawal Ashish, BARC, Mumbai, India. Alam Md Sayem, AMU, Aligarh, India. Alamelu D, BARC, Mumbai, India. Aldona Rajewska, IAE ...

List of participants

Indian Academy of Sciences (India)

Babu P D, UGC-DAE CSR, Mumbai, India. Bahadur Jitendra, BARC, Mumbai, India. Bajaj Annu, GNDU, Amritsar, India. Balakrishnan Geetha, University of Warwick, UK. Banerjee Srikumar, BARC, Mumbai, India. Basak Tista, BARC, Mumbai, India. Basu S, BARC, Mumbai, India. Basu T K, BARC, Mumbai, India. Belushkin ...

High-Si content BARC for dual-BARC systems such as trilayer patterning

Science.gov (United States)

Kennedy, Joseph; Xie, Song-Yuan; Wu, Ze-Yu; Katsanes, Ron; Flanigan, Kyle; Lee, Kevin; Slezak, Mark; Liu, Zhi; Lin, Shang-Ho

2009-03-01

This work discusses the requirements and performance of Honeywell's middle layer material, UVAS, for tri-layer patterning. UVAS is a high Si content polymer synthesized directly from Si containing starting monomer components. The monomers are selected to produce a film that meets the requirements as a middle layer for tri-layer patterning (TLP) and gives us a level of flexibility to adjust the properties of the film to meet the customer's specific photoresist and patterning requirements. Results of simulations of the substrate reflectance versus numerical aperture, UVAS thickness, and under layer film are presented. ArF photoresist line profiles and process latitude versus UVAS bake at temperatures as low as 150ºC are presented and discussed. Immersion lithographic patterning of ArF photoresist line space and contact hole features will be presented. A sequence of SEM images detailing the plasma etch transfer of line space photoresist features through the middle and under layer films comprising the TLP film stack will be presented. Excellent etch selectivity between the UVAS and the organic under layer film exists as no edge erosion or faceting is observed as a result of the etch process. A detailed study of the impact of a PGMEA solvent photoresist rework process on the lithographic process window of a TLP film stack was performed with the results indicating that no degradation to the UVAS film occurs.

Two-layer anti-reflection strategies for implant applications

Science.gov (United States)

Guerrero, Douglas J.; Smith, Tamara; Kato, Masakazu; Kimura, Shigeo; Enomoto, Tomoyuki

2006-03-01

A two-layer bottom anti-reflective coating (BARC) concept in which a layer that develops slowly is coated on top of a bottom layer that develops more rapidly was demonstrated. Development rate control was achieved by selection of crosslinker amount and BARC curing conditions. A single-layer BARC was compared with the two-layer BARC concept. The single-layer BARC does not clear out of 200-nm deep vias. When the slower developing single-layer BARC was coated on top of the faster developing layer, the vias were cleared. Lithographic evaluation of the two-layer BARC concept shows the same resolution advantages as the single-layer system. Planarization properties of a two-layer BARC system are better than for a single-layer system, when comparing the same total nominal thicknesses.

Design and Performance of GMR Sensors for the Detection of Magnetic Microbeads in Biosensors

National Research Council Canada - National Science Library

Rife, J. C; Miller, M. M; Sheehan, P. E; Tamanaha, C. R; Tondra, M; Whitman, L. J

2003-01-01

We are developing a biosensor system, the Bead ARray Counter (BARC), based on the capture and detection of micron-sized, paramagnetic beads on a chip containing an array of giant magnetoresistive (GMR) sensors...

Recombinant lines for less-spininess in steroid-bearing Solanum viarum using induced mutants as parents

International Nuclear Information System (INIS)

Krishnan, R.; Nanda Kumar, D.; Subhas Chander, M.

1988-01-01

In the domestication of the wild, spinous and steroid-bearing Solanum viarum (syn. S. khasianum var. chatterjeeanum) induced mutations play a major role. The development of Glaxo and BARC mutants catalysed commercial cultivation of this species for its berries containing solasodine, used in steroid industries. The commercially more popular Glaxo mutant population consists predominantly of plants that are totally free of spines in aerial parts except lamina where few straight spines develop. The BARC mutant still possesses spines on aerial parts including the persistent calyx. However, the laminary spines of the BARC mutant are curved and vestigial. Comparative studies on morphology, growth behaviour and agronomic characters of the two mutants, their wild progenitor and their hybrid progenies showed that the three types differ only for spine character. In F 2 generation of a cross involving the Glaxo and BARC mutants, a double mutant recombinant was recovered. The recombinant is devoid of spines in aerial parts like its Glaxo mutant parent, but possesses laminary curved vestigial spines like the BARC parent. The spine characters of the recombinant are inherited double recessive. Three advanced lines of this recombinant type (IIHR 2n - 1,2 and 3) were tested in replicated trials 1985 and 1986. They showed parity in berry yield and solasodine content with the Glaxo mutant and three promising lines evolved elsewhere viz. 'RRL (Bhuhaneswar) Y-14', 'RRL (Jorhat)' and 'Pusa'. The results indicate gainful use of induced mutants in hybridization leading to development of superior less-spiny lines of steroid bearing Solanum viarum

Regulations of safe transport of radioactive material

International Nuclear Information System (INIS)

Patel, R.J.; Sumathi, E.

2017-01-01

BARC is a multi-disciplinary nuclear research organisation with facilities located at various parts of the country. The nuclear and radiological facilities in BARC include fuel fabrication facilities, nuclear research reactors, radiological laboratories, nuclear recycle facilities, waste management facilities and other associated facilities. RAdioactive Material (RAM) such as fresh nuclear fuel, irradiated fuel, radioactive sources, vitrified high level wastes, special nuclear material etc., are transported between these facilities either within the controlled premises or in public domain. In BARC the regulatory approval for the packages used for transport of RAM is issued by BARC Safety Council (BSC). Competent Authority for issuing the design approval for the BARC packages in public domain is Director, BARC. In this aspect BSC is assisted by Safety Review Committee-Transport of Radioactive Material (SRC-TRM) constituted by BSC entrusted with the mandate to ensure the packages are designed, manufactured and transported in accordance with the current regulations. This article summarizes the regulatory requirements for transport of RAM and experience in BARC facilities

Micro-controller based fiber optic data telemetry system for the ion source of low energy accelerator facility at BARC

International Nuclear Information System (INIS)

Padmakumar, Sapna; Ware, Shailaja V.; Subrahmanyam, N.B.V.; Bhatt, J.P.; Singh, S.K.; Gupta, S.K.; Singh, P.; Choudhury, R.K.

2009-01-01

The Low Energy Accelerator Facility (LEAF) is a 50 keV, high intensity, negative ion accelerator facility that has been set up indigenously at Nuclear Physics Division, BARC. This facility is capable of delivering a wide range of negative ion beams of both light and heavy ions across the periodic table using a SNICS II (Source of Negative Ion by Caesium Sputtering) source. A micro-controller based control and monitoring system has been developed exclusively for the ion source parameters of LEAF. The data control and monitoring system mainly targets acquiring the data from the field in the terms of parameters such as voltages and currents. There are processes which need to be monitored continuously in order to keep certain parameters under check. The microcontroller based fiber optic data telemetry system allows us to perform the aforesaid task. The voltages can be controlled and monitored by providing the inputs and receiving the feedback through a user friendly graphic user interface. With this system one can control the status as well as analog value of the high voltage power supplies like extractor, cathode, filament, focus line heater and oven. This system consists of Fiber optic transceiver, which is connected on serial port (RS 232C) of microcontroller as well as RS232 port of PC. The whole control system is reliable even in noisy environments including RF and worse EMI conditions. This compact modular design is implemented using low cost devices and allows easy and fast maintainability. In the paper, the details of the system are presented. (author)

Electron beam accelerator at BARC-BRIT complex - electron beam processing of materials and industrial utilization

International Nuclear Information System (INIS)

Khader, S.A.; Patkari, R.K.; Sharma, K.S.S.

2013-01-01

During the last decade, the 2MeV/20kW electron beam (EB) accelerator located at BARC-BRIT complex, Vashi has been successfully utilised for non-thermal applications to develop speciality products useful for the industry. Polymer materials are exposed to high energy electrons to induce crosslinking and degradation reactions in a number of industrial products without the use of external chemicals and additives. Various EB crosslinked products viz. PE O-rings, automotive components, automobile tyres, electrical insulations, etc have been found to be much superior in quality compared to those produced conventionally. A process has been developed to enhance colours in the polished diamonds and gem stones using EB irradiation at the facility which has attracted much attention in the Indian diamond industry as a value-addition process. Recycling of polymer waste processed under EB to produce microfine PTFE powder, to reuse in automobile industry etc. has shown good potential for the industrial use. The process feasibility both in terms of economics and technology have been amply demonstrated on a technological scale by installing special conveyors at our facility for irradiating various industrial products. Around 100 km cable insulations, 1.5 million PE O-rings and more than 40000 carats of polished diamonds have been processed in our facility over a period of time on commercial scale. Encouraged with the results, Indian private entrepreneurs have set up dedicated EB machines in some of the most significant industries producing wire and cables, electrical gadgets based on polymer composites, automobile tyres and diamonds. The products are unique in properties and are in some cases, became import substitutes. The industry is now fully geared up to adapt the technology by realising the advantages viz ease in adaptability, convenient, safe and environmental-friendly nature. Encouraged by the process demonstrations, while five EB accelerators were setup and are in operation

Management of Documents and Information in BSC Secretariat

International Nuclear Information System (INIS)

Sumathi, E.; Jayarajan, K.

2017-01-01

The regulatory and safety function of BARC facilities is being carried out by BARC Safety Framework with BARC Safety Council as an apex body. Presently, about one hundred safety committees and task forces are functional in the framework. BSC Secretariat (BSCS) provides technical and administrative support to the BARC Safety Framework for the regulatory activities in BARC. Important documents/records related to committee decisions and facilities are maintained in BSCS, through an established documentation and record keeping system. The compliance of regulatory recommendations is verified during regulatory inspections and subsequent submissions made by the facility authority. This supports the effective regulatory decision making of various committees. This article elaborates the maintenance of records and information at BSC

Report on R and D activities of Health Physics Division 1984 - 1985

International Nuclear Information System (INIS)

Chakraborty, P.P.; Iyer, M.R.; Somasundaram, S.

1986-01-01

A summary of the research and development programmes undertaken in Health Physics Division during the period 1984-1985 is contained in the report. The details of the various investigations are given in references listed under each abstract, most of which are published in the form of papers in symposia and journals or as BARC reports. Some of the investigations have been carried out in collaboration with other Divisions of BARC and outside organisations. A list of these leading to M.Sc./Ph.D Degrees submitted by members of the Division is given at the end. The Division has also a number of research contracts with IAEA. A summary of work carried out under these projects is included in a separate section. (author)

Refining of crude uranium by solvent extraction for production of nuclear pure uranium metal

International Nuclear Information System (INIS)

Gupta, S.K.; Manna, S.; Singha, M.; Hareendran, K.N.; Chowdhury, S.; Satpati, S.K.; Kumar, K.

2007-01-01

Uranium is the primary fuel material for any nuclear fission energy program. Natural uranium contains only 0.712% of 235 U as fissile constituent. This low concentration of fissile isotope in natural uranium calls for a very high level of purity, especially with respect to neutron poisons like B, Cd, Gd etc. before it can be used as nuclear fuel. Solvent extraction is a widely used technique by which crude uranium is purified for reactor use. Uranium metal plant (UMP), BARC, Trombay is engaged in refining of uranium concentrate for production of nuclear pure uranium metal for fabrication of fuel for research reactors. This paper reviews some of the fundamental aspects of this refining process with some special references to UMP, BARC. (author)

PREFACE: International Symposium on `Vacuum Science and Technology' (IVS 2007)

Science.gov (United States)

Mittal, K. C.; Gupta, S. K.

2008-03-01

equipments, accessories, products etc by different manufacturers and suppliers has been organized at the venue of the symposium hall for the benefit of the participants. The interest shown by the exhibitors reveals that the industry has come of age and the advances that have taken place over the years is quite significant. During the symposium, the Indian Vacuum Society felicitated two distinguished personalities who have contributed significantly for the development of vacuum science and technology in the country. The C AMBASANKARAN memorial and Smt SHAKUNTALABAI VYAWAHARE memorial Awards were also conferred on the two best contributed papers. A committee constituted by the Symposium Organizing Committee evaluated the relevance, scientific content, and clarity of presentation to decide the award winning papers. It is hoped that the discussion generated by the delegates at the symposium will help in a better understanding vacuum science and technology. K C Mittal Convener S K Gupta Co Convener International Advisory Committee Kakodkar, Anil DAE/India, Chairman Badve, Cdr A.V.(IN Retd.) Pfeiffer Vac India Banerjee, S. BARC/India Bhandari, R.K. BRNS/India Chander, Shekhar CEERI/India Chopra, K.L. IIT Delhi/India Day, Chris ITER Grover, R.B DAE,BARC/India Jakub, Szajman VSA/ Australia Jayaraj, R.N. NFC/India Kamath, H.S. BARC/India Kaw, P.K. IPR/India Kobayashi, M. VSJ/Japan Kumar, Lalit MTRDC, India Kumar, Vikram NPL., India Langley, Robert AVS, USA Larour, Jean Ecole/France Mendonsa, R.H. Lawrence and Mayo Myneni, Ganapatirao Jlab/USA Narsaiah, S.V. HHV Padamsee, Hasan Cornell/USA Pillay, R.G. TIFR Raj, Baldev IGCAR/India Raju, P.T. IVS/India Ramasami, T. DST/India Ray, A.K. BARC/India Reid, RJ IUVSTA/UK Roy, Amit IUAC/india Sahni, V.C. RRCAT, BARC/India Schamiloglu, E. UNM/USA Shankara, K.N. VSSC,ISRO/India Sinha, Bikash VEC,SINP/India Strubin, P. CERN/Switzerland Local Organizing Committee Ray, A.K. BARC (Chairman) Kailas, S. BARC, (Co Chairman) Chakravarty, D.P. BARC

List of Participants 183

Indian Academy of Sciences (India)

Narasimhan S L, BARC, Mumbai,. India. Nisha C K, IICT, Hyderabad, India. Pal O R, UICT, Mumbai, India. Pande S S, BARC, Mumbai, India. Paranjpe A S, BARC, Mumbai, India. Paranjpe S K, IAEA, Vienna, Austria. Parmar Rohini N, Saurashtra Univer- sity, Rajkot, India. Patil S R, MS University of Baroda,. Vadodara, India.

MIDDLE MIOCENE DEPOSITIONAL MODEL IN THE DRAVA DEPRESSION DESCRIBED BY GEOSTATISTICAL POROSITY AND THICKNESS MAPS (CASE STUDY: STARI GRADAC-BARCS NYUGAT FIELD

Directory of Open Access Journals (Sweden)

Tomislav Malvić

2006-12-01

Full Text Available Neogene depositional environments in the Drava depression can be classified in two groups. One group is of local alluvial fans, which were active during the period of Middle Miocene (Badenian extension through the entire Pannonian Basin. The second group is represented by continuous Pannonian and Pontian sedimentation starting with lacustrine environment of partly deep water and partly prodelta (turbidity fans and terminating at the delta plain sedimentation. The coarse-grained sediments of alluvial fans have the great hydrocarbon potential, because they often comprise reservoir rocks. Reservoir deposits are mostly overlain (as result of fan migration by pelitic seal deposits and sometimes including organic rich source facies. That Badenian sequences are often characterised by complete petroleum systems, what is confirmed by large number of oil and gas discoveries in such sediments in the Drava and other Croatian depressions. Alluvial environments are characterised by frequent changes of petrophysical properties, due to local character of depositional mechanism and material sources. In the presented paper, Stari Gradac-Barcs Nyugat field is selected as a case study for demonstrating the above mentioned heterogenic features of the Badenian sequences. Structural solutions are compared by maps of parameters related to depositional environment, i.e. porosity and thickness maps. Geostatistics were used for spatial extension of input dataset. The spatial variability of porosity values, i.e. reservoir quality, is interpreted by transition among different sub-environments (facies in the alluvial fan system.

Solar PV-based rooftop power plant

International Nuclear Information System (INIS)

Ashok Kumar, B.; Kumar, Chaitanya; Patel, C.B.; Pattanaik, B.R.; Panda, P.K.; Kaul, S.K.; Mishra, H.

2017-01-01

Technical Services Division (TSD) is responsible for providing reliable power supply to various operating reactors, laboratories and facilities of BARC. The power supply to BARC is derived from TATA Power at 110 KV and 22 KV at an average HT tariff of Rs.8.49 per unit at present. Peak power demand of BARC in summer season goes up to 23 MW. TSD has implemented several energy conservation measures to reduce the energy consumption and as well taken initiatives to install solar PV based rooftop power plants to reduce the cost of energy consumption in BARC

Design of a new bottom antireflective coating composition for KrF resist

Science.gov (United States)

Mizutani, Kazuyoshi; Momota, Makoto; Aoai, Toshiaki; Yagihara, Morio

1999-06-01

A study for a new organic bottom antireflective coating (BARC) composition is described. A structural design of a light-absorbing dye was most important because dye structure not only plays a role in eliminating reflection from a substrate but also shows influence on dry etch rate of BARC material to a considerable extent. For example, an anthracene moiety with large absorption at 248 nm had undesirable dry etch resistance. 3-Hydroxy-2-naphthoic acid moiety was found to be one of suitable dyes for KrF BARC compositions, and the polymer bearing the dye showed enough absorbance and good erodability in dry etch. The BARC polymer was eroded as one and a half times faster than a novolak resin, and a little faster than an anthracene incorporated polymer. The result was discussed from the concepts of Ohnishi parameter and the ring parameter for dry etch durability of resist materials. BARC polymer should be thermoset by hard bake to eliminate intermixing with resist compositions. The BARC polymer bearing hydroxy group which is useful for a crosslinking reaction was thermoset in the presence of melamine-formaldehyde crosslinker and an acid catalyst after baking over 200 degrees C.

Novel conformal organic antireflective coatings for advanced I-line lithography

Science.gov (United States)

Deshpande, Shreeram V.; Nowak, Kelly A.; Fowler, Shelly; Williams, Paul; Arjona, Mikko

2001-08-01

Flash memory chips are playing a critical role in semiconductor devices due to increased popularity of hand held electronic communication devices such as cell phones and PDAs (personal Digital Assistants). Flash memory offers two primary advantages in semiconductor devices. First, it offers flexibility of in-circuit programming capability to reduce the loss from programming errors and to significantly reduce commercialization time to market for new devices. Second, flash memory has a double density memory capability through stacked gate structures which increases the memory capability and thus saves significantly on chip real estate. However, due to stacked gate structures the requirements for manufacturing of flash memory devices are significantly different from traditional memory devices. Stacked gate structures also offer unique challenges to lithographic patterning materials such as Bottom Anti-Reflective Coating (BARC) compositions used to achieve CD control and to minimize standing wave effect in photolithography. To be applicable in flash memory manufacturing a BARC should form a conformal coating on high topography of stacked gate features as well as provide the normal anti-reflection properties for CD control. In this paper we report on a new highly conformal advanced i-line BARC for use in design and manufacture of flash memory devices. Conformal BARCs being significantly thinner in trenches than the planarizing BARCs offer the advantage of reducing BARC overetch and thus minimizing resist thickness loss.

Regulatory measures for traffic safety

International Nuclear Information System (INIS)

Veerapur, R.D.; Bharambe, S.D.; Patnaik, S.K.; Tandle, A.K.; Sonawane, K.A.; Kumar, Rajesh; Venkat Subramanian, K.

2017-01-01

Traffic safety is an issue related to occupational safety not restricted alone to the transportation but extends beyond. BARC has many facilities spread across large area in Mumbai and outside Mumbai. BARC deploys large number of buses, mini buses, jeeps and cars for commuting its employees to reach BARC and for commuting within BARC premises. Additionally, trucks, fire tenders, trailers etc. are also deployed for transportation of materials. No moving vehicle is ever free of the possibility of involvement in an accident. Vehicular accidents and the fatalities on road are the result of inter-play of a number of factors. The vehicle population has been steadily increasing with the pace picking up significantly in recent past. Increase in vehicle population in the face of limited road space used by a large variety of traffic has heightened the need and urgency for a well-thought-out road safety. Therefore, existence of regulatory authority to regulate traffic and vehicles to ensure safety of its employees and vehicles is very essential. BARC Traffic Safety Committee (BTSC), which is the regulating body for traffic safety is responsible for ensuring overall traffic safety. (author)

Comportamiento de las discapacidades en los adultos mayores. Consejo Popular Hermanos Barcón Behavior of the disabilities in the elderly. "Hermanos Barcon" Popular Council

Directory of Open Access Journals (Sweden)

Marvelia Díaz Calzada

2012-02-01

Full Text Available Se realizó una investigación descriptiva y transversal en los adultos mayores del Consejo Popular "Hermanos Barcón" durante el período de enero a junio de 2011, con el objetivo de determinar el comportamiento de las discapacidades. El universo lo constituyeron 2011 ancianos y la muestra 200. Se aplicó la encuesta de factores de riesgo de discapacidad. Los resultados se analizaron mediante el cálculo de tasas, frecuencias absolutas y porcentajes. Las discapacidades físicas están muy relacionadas con las secuelas de fracturas de cadera, mientras que las variables psicosociales que más se asocian con esta discapacidad son los niveles escolares bajos y la pérdida de rol social. Las discapacidades mentales prevalecieron en las edades avanzadas, el sexo femenino, la baja escolaridad y la desocupación.A descriptive and cross-sectional study was carried out with the elderly of "Hermanos Barcon" Popular Council, from January to June 2011 aimed at determining the behavior of their disabilities. The target group included 2011 old people and the sample 200. The survey for the disability risk factor was applied. Results were analyzed by means of rate calculation, absolute frequencies and percentages. Physical disabilities are close related to the sequelae of hip fractures, whereas low educational levels and lost of social role were the psychosocial variables most associated with this disability. Mental disabilities, female sex, low school degrees and unemployment prevailed in advanced ages.

Fulltext PDF

Indian Academy of Sciences (India)

Arora Sangeeta, Thapar University. Arumugham P, IIT Roorkee. Aswal D K, BARC, Mumbai. Attar Fakirmohammad, Fergusson College. Balabanski D, Horia Hulubei National Institute, Romania. Banerjee D, BARC, Mumbai. Bansal Preeti, Panjab University. Bansal Rajni, Panjab University. Bansal Rubina, Thapar University.

7 CFR 502.1 - General.

Science.gov (United States)

2010-01-01

..., grounds, equipment, and experimental plants and animals of BARC (36 FR 18440). The Secretary of... CONDUCT ON BELTSVILLE AGRICULTURE RESEARCH CENTER PROPERTY, BELTSVILLE, MARYLAND § 502.1 General. The... Research Center (BARC), Beltsville, MD, and to any persons entering in or on such property. The...

Iron in carbonate containing AFm phases

International Nuclear Information System (INIS)

Dilnesa, B.Z.; Lothenbach, B.; Le Saout, G.; Renaudin, G.; Mesbah, A.; Filinchuk, Y.; Wichser, A.; Wieland, E.

2011-01-01

One of the AFm phases in hydrated Portland cement is Ca 3 (Al x Fe 2 - x )O 6 .CaCO 3 .nH 2 O. It is based on hexagonal and platey structural elements and the interlayer structure incorporates CO 3 2- . The solid phases were experimentally synthesized and characterized by different techniques including X-ray techniques (XRD and EXAFS) and vibrational spectroscopy techniques (IR, Raman). Fe-monocarbonate (Fe-Mc) and Al-monocarbonate (Al-Mc) were found to be stable up to 50 o C, while Fe-hemicarbonate (Fe-Hc) was unstable with respect to Fe-Mc in the presence of calcite. Fe-Mc has a rhombohedral R3-barc symmetry which is different from the triclinic of the Al analogue. Both XRD and thermodynamic modelling of the liquid compositions indicated that Al-Mc and the Fe-Mc phases do not form solid solution. The solubility products were calculated experimentally at 20 o C and 50 o C. Under standards condition the solubility products and other thermodynamic parameters were estimated using temperature-solubility product extrapolation and found to be logK S0 (Fe-Mc) = -34.59 ± 0.50, logK S0 (Fe-Hc) = -30.83 ± 0.50 and logK S0 (Al-Mc) = -31.32 ± 0.50.

BARC highlights 1991

International Nuclear Information System (INIS)

1992-01-01

Some of the important research and development (R and D) activities carried out at the Centre during the last two or three years are described in brief. The descriptions are arranged under the headings : Physical Sciences, Chemical Sciences, Material and Materials Science, Radioisotopes, Reactors, Fuel Cycle, Radiological Safety and Protection, Electronics and Instrumentation, Engineering Services, and Life Sciences. The text is illustrated with a number of photographs - some of them coloured. (M.G.B.)

Molecular dynamics simulation of the rotational order-disorder phase transition in calcite

International Nuclear Information System (INIS)

Kawano, Jun; Miyake, Akira; Shimobayashi, Norimasa; Kitamura, Masao

2009-01-01

Molecular dynamics (MD) simulation of calcite was carried out with the interatomic potential model based on ab initio calculations to elucidate the phase relations for calcite polymorphs and the mechanism of the rotational order-disorder transition of calcite at high temperature at the atomic scale. From runs of MD calculations with increasing temperature within a pressure range of 1 atm and 2 GPa, the transition of calcite with R3-barc symmetry into a high-temperature phase with R3-barm symmetry was reproduced. In the high-temperature R3-barm phase, CO 3 groups vibrate with large amplitudes either around the original positions in the R3-barc structure or around other positions rotated ± 60 deg., and their positions change continuously with time. Moreover, contrary to the suggestion of previous investigators, the motion of CO 3 groups is not two-dimensional. At 1 atm, the transition between R3-barc and R3-barm is first order in character. Upon increasing temperature at high pressure, however, first a first-order isosymmetric phase transition between the R3-barc phases occurs, which corresponds to the start of ± 120 deg. flipping of CO 3 groups. Then, at higher temperatures, the transition of R3-barc to R3-barm phases happens, which can be considered second order. This set of two types of transitions at elevated pressure can be characterized by the appearance of an 'intermediate' R3-barc phase between the stable region of calcite and the high-temperature R3-barm phase, which may correspond to the CaCO 3 -IV phase.

Inflammable materials stores

International Nuclear Information System (INIS)

Nandagopan, V.

2017-01-01

A new Inflammable Materials Stores has been constructed by A and SED, BARC near Gamma Field for storage of inflammable materials falling into Petroleum Class ‘A’ ‘B’ and “C” mainly comprising of oils and lubricants, Chemicals like Acetone, Petroleum Ether etc. which are regularly procured by Central Stores Unit (CSU) for issue to the various divisions of BARC. The design of the shed done by A and SED, BARC was duly got approved from Petroleum and Explosive Safety Organization (PESO) which is a mandatory requirement before commencement of the construction. The design had taken into account various safety factors which is ideally required for an inflammable materials stores

Integrated Water Basin Management Including a Large Pit Lake and a Water Supply Reservoir: The Mero-Barcés Basin

Science.gov (United States)

Delgado, Jordi; Juncosa-Rivera, Ricardo; Hernández-Anguiano, Horacio; Muñoz-Ibáñez, Andrea

2016-04-01

use of lake water is acceptable from different points of view (water quality, legal constrains, etc.). Our results indicate that the joint use of the lake/reservoir system is feasible. Based on this and other complementary study, the basin water authorities has developed a project by which a 2.1 km uptake tunnel will be excavated in the next years to drain water from the lake towards the Barcés river and complement the water supply necessities of the Abegondo-Cecebre reservoir in case of hydric emergencies.

Heavy-quark fragmentation functions in the effective theory of heavy quarks

International Nuclear Information System (INIS)

Martynenko, A.P.; Saleev, V.A.

1996-01-01

The effective theory of heavy quarks is used to study b-bar-antiquark fragmentation in polarized Bc* mesons and b-quark fragmentation into P-wave (c-barb) states. The functions of heavy-quark fragmentation into longitudinally and transversely polarized S-wave (b-barc) states and into P-wave mesons containing b and c quarks are calculated. First-order corrections in 1/mb are taken into account exactly in these calculations. The results are shown to be consistent with the corresponding QCD calculations

Medical physics aspects of ophthalmic brachytherapy

International Nuclear Information System (INIS)

Sharma, S.D.; Shanta, A.; Palani Selvam, T.; Tripathi, U.B.; Bhatt, B.C.

2004-11-01

Intraocular melanoma is the most common primary malignancy of the eye. Radiation therapy using ophthalmic plaque has proved successful in the management of various ocular lesions. Although a few centres were using 90 Sr/ 90 Y plaques for shallow turtlours some years ago, eye plaque therapy was not a common practice in India. A revived interest in the use of eye plaque therapy and very high cost of imported sources has led to the development and production of 125 I seed sources by the Radiopharmaceuticals Division, BARC. This report presents a brief description on the clinical, dosimetry and radiation safety aspects of 90 Sr/ 90 Y and 106 Ru/ 106 Rh beta ray and 125 I gamma ray eye plaque applicators. This report has been divided in five Sections. Section I presents general introduction of ophthalmic brachytherapy including the structure of a human eye, types of ophthalmic plaques and characteristics of radioisotopes commonly used in such applications. A brief review of sources, applicators and dosimetry of 90 Sr/ 90 Y and 106 Ru/ 106 Rh beta and 125 I gamma ophthalmic plaques are given in Section II and Section III, respectively. Section IV contains the single seed dosimetry data of BARC OcuProsta 125 I seed as well as dosimetry data of typical eye plaques loaded with BARC OcuProsta 125 I seed. Quality assurance and radiation safety aspects of these eye applicators are described in Section V. A proforma of the application required to be filled in by the user institution for obtaining regulatory consent to start eye plaque therapy has also been appended to this report. (author)

Design, fabrication, installation and shielding integrity testing of source storage container for automatic source movement system used in TLD calibration facility

International Nuclear Information System (INIS)

Subramanian, V.; Baskar, S.; Annalakshmi, O.; Jose, M.T.; Jayshree, C.P.; Choudry, Shreelatha

2012-01-01

A state-of-art TLD laboratory has been commissioned in January 2000 at Radiological Safety Division of Indira Gandhi Centre for Atomic Research (IGCAR). The laboratory provides personnel monitoring service to 2000 occupational workers from Indira Gandhi Centre for Atomic Research and Bhabha Atomic Research Centre facilities. The laboratory has been accredited by the Radiation Safety Systems Division (RSSD), Bhabha Atomic Research Centre (BARC) since year 2002. The laboratory has exclusive facility for the calibration of the TLD cards. As apart of accreditation procedure and taking into account of geometry effect, the dose rate at the card position is determined by the accreditation authorities by using graphite chamber (secondary or national standard instrument) and often re estimated by a condenser R meter (M/s Victoreen, Germany) by our laboratory. As per the regulatory requirement, the exposure protocols should be automated. Towards this an automatic source movement system has been augmented in the calibration facility. By using the system, the source will be brought to the irradiation position by pneumatically and exposures will be terminated by counter, timer and triggering system. To accomplish this task a lead container has been designed, fabricated and mounted at the beneath of the calibration table for the storage of source. As per the automation process, a lead container for the source storage has been designed and installed beneath to the Calibration Table. The container was designed to hold a 3Ci 137 Cs source, but present activity of the source is 1.2Ci. Hence, the shielding integrity was tested with higher active source (1.7Ci 60 Co). The dose rate measured outside on the circumference of the container at the middle of the source is found to be the same as calculated using QAD CGGP calculations. The top plug is so designed to avoid inadvertent upward movement of the source. Though, the shielding was not adequate on top of the top plug, however it does

BARC progress report - 1998

Energy Technology Data Exchange (ETDEWEB)

Kalyane, V L [comp.; Library and Information Services Div., Bhabha Atomic Research Centre, Mumbai (India)

1999-04-01

This report is a compilation of the progress in various major activities and Research and Development programmes of the different Divisions of the Bhabha Atomic Research Centre, Mumbai. The list of publications and papers presented at the various conferences, symposia, workshops and papers published in journal by the staff members of the Divisions are also given. (author) figs., tabs.

BARC progress report - 1998

International Nuclear Information System (INIS)

Kalyane, V.L.

1999-04-01

This report is a compilation of the progress in various major activities and Research and Development programmes of the different Divisions of the Bhabha Atomic Research Centre, Mumbai. The list of publications and papers presented at the various conferences, symposia, workshops and papers published in journal by the staff members of the Divisions are also given. (author)

BARC annual report 1987

International Nuclear Information System (INIS)

1988-11-01

The report summarises the Research and Development (R and D) activities of the Bhabha Atomic Research Centre, Bombay, during 1987. These R and D activities are described in the chapters entitled: Physical Sciences, Chemical S ciences, Materials and Materials Sciences, Radioisotopes, Reactors, Fuel Cycle, Radiological Safety and Protection, Electronics and Instrumentation, Engineering Services, and Life Sciences. Activities in the fields of remote handling and robotics, technology transfer, and auxiliary activities like technical information, human resources and development etc. are dealt in the chapter entitled General. At the end of each chapter, a list of publications by the scientists in the corresp onding subject field is given. Some of the major highlights of the work during 1987 are: (1) DHRUVA reactor became fully operational at its rated capacity making neutrons available for isotope production and studies in neutron scattering and condensed matter, (2) R and D activities were extended to study h igh temperature superconductivity in both fundamental and applied aspects and (3) a laboratory for production of 32 P-biomolecules was set up at the Centre for Cellular and Molecular Biology at Hyderabad. (M.G.B.)

BARC progress report - 1997

Energy Technology Data Exchange (ETDEWEB)

Kalyane, V L [comp.; Library and Information Services Div., Bhabha Atomic Research Centre, Mumbai (India)

1998-07-01

This report is a compilation of the progress in various major activities and Research and Development programmes of the different Divisions of the Bhabha Atomic Research Centre, Mumbai. The list of publications and papers presented at the various conferences, symposia, workshops and papers published in journal by the staff members of the Divisions are also given. (author) figs., tabs.

BARC progress report - 1997

International Nuclear Information System (INIS)

Kalyane, V.L.

1998-07-01

This report is a compilation of the progress in various major activities and Research and Development programmes of the different Divisions of the Bhabha Atomic Research Centre, Mumbai. The list of publications and papers presented at the various conferences, symposia, workshops and papers published in journal by the staff members of the Divisions are also given. (author)

BARC progress report - 1996

International Nuclear Information System (INIS)

1997-01-01

This report summarises the various activities and research and development programmes of the different Divisions of the Bhabha Atomic Research Centre, Mumbai. The list of publications and paper presented at various conferences, symposia, workshops etc and papers published in various journals by the staff members of the different Divisions are also given. (author)

BARC progress report - 1996

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-12-31

This report summarises the various activities and research and development programmes of the different Divisions of the Bhabha Atomic Research Centre, Mumbai. The list of publications and paper presented at various conferences, symposia, workshops etc and papers published in various journals by the staff members of the different Divisions are also given. (author)

Regulatory process for material handling equipment

International Nuclear Information System (INIS)

Rajendran, S.; Agarwal, Kailash

2017-01-01

Atomic Energy (Factories) Rules (AEFR) 1996, Rule 35 states, 'Thorough inspection and load testing of a Crane shall be done by a Competent Person at least once every 12 months'. To adhere to this rule, BARC Safety Council constituted 'Material Handling Equipment Committee (MHEC)' under the aegis of Conventional Fire and Safety Review Committee (CFSRC) to carry out periodical inspection and certification of Material Handling Equipment (MHE), tools and tackles used in BARC Facilities at Trombay, Tarapur and Kalpakkam

Clinical utility of new bleeding criteria: a prospective study of evaluation for the Bleeding Academic Research Consortium definition of bleeding in patients undergoing percutaneous coronary intervention.

Science.gov (United States)

Choi, Jae-Hyuk; Seo, Jeong-Min; Lee, Dong Hyun; Park, Kyungil; Kim, Young-Dae

2015-04-01

The aim of this study was to evaluate the clinical utility of the new bleeding criteria, proposed by the Bleeding Academic Research Consortium (BARC), compared with the old criteria for determining the action of physicians in contact with bleeding events, after percutaneous coronary intervention (PCI). The BARC criteria were independently associated with an increased risk of 1-year mortality after PCI, and provided a predictive value, in regard to 1-year mortality. The standardized bleeding definitions will be expected to help the physician to correctly analyze the bleeding events, to select an optimal treatment, and to objectively compare the results of multiple trials and registries. All the patients undergoing PCI from June to September 2012 were prospectively enrolled. Patients who experienced a bleeding event were further classified, based on three different bleeding severity criteria: BARC, Thrombolysis In Myocardial Infarction (TIMI), and Global Use of Strategies To Open coronary arteries (GUSTO). The primary outcome was the occurrence of bleeding events requiring interruption of antiplatelet therapy (IAT) by physicians. A total of 376 consecutive patients were included in this study. Total bleeding events occurred in 46 patients (12.2%). BARC type ≥2 bleeding occurred in 30 patients (8.0%); however, TIMI major or minor bleeding, and GUSTO moderate or severe bleeding occurred in 6 (1.6%) and 11 patients (2.9%), respectively. Of the 46 patients, 28 (60.9% of patients) required IAT. On receiver-operating characteristic curve analysis, bleeding defined BARC type ≥2 effectively predicted IAT, with a sensitivity of 89.3%, and a specificity of 98.5% (pdefinition may be a more useful tool for the detection of bleeding with clinical relevance, for patients undergoing PCI. Copyright © 2014 Japanese College of Cardiology. Published by Elsevier Ltd. All rights reserved.

Radiation dosage

Energy Technology Data Exchange (ETDEWEB)

Finston, Roland [Health Physics, Stanford University, Stanford, CA (United States)

1986-07-01

Radiation dosage at Bikini Atoll is the result of current soil contamination, a relic of the nuclear weapons testing program of some 30 years ago. The principal contaminants today and some of their physical properties are listed: cesium-137, strontium-90, plutonium -239, 240 and americium-241. Cobalt-60 contributes less than 1 to the dose and is not considered significant. A resident of the atoll would accumulate radiation dose (rem) in two ways -- by exposure to radiation emanating from the ground and vegetation, and by exposure to radiation released in the spontaneous decay of radionuclides that have entered his body during the ingestion of locally grown foods. The latter process would account for some 90% of the dose; cesium-137 would be responsible for 0 90% of it. Since BARC's method of estimating dosage differs in some respects from that employed by the Lawrence Livermore National Laboratory (LLNL), (Ref.1, LLNL 1982) we are presenting our method in detail. The differences have two sources. First, the numbers used by BARC for the daily ingestion of radionuclides via the diet are higher than LLNL's. Second, BARC's calculation of dose from radionuclide intake utilizes the ICRP system. The net result is that BARC doses are consistently higher than LLNL doses, and in this respect are more conservative.

Radiation dosage

International Nuclear Information System (INIS)

Finston, Roland

1986-01-01

Radiation dosage at Bikini Atoll is the result of current soil contamination, a relic of the nuclear weapons testing program of some 30 years ago. The principal contaminants today and some of their physical properties are listed: cesium-137, strontium-90, plutonium -239, 240 and americium-241. Cobalt-60 contributes less than 1 to the dose and is not considered significant. A resident of the atoll would accumulate radiation dose (rem) in two ways -- by exposure to radiation emanating from the ground and vegetation, and by exposure to radiation released in the spontaneous decay of radionuclides that have entered his body during the ingestion of locally grown foods. The latter process would account for some 90% of the dose; cesium-137 would be responsible for 0 90% of it. Since BARC's method of estimating dosage differs in some respects from that employed by the Lawrence Livermore National Laboratory (LLNL), (Ref.1, LLNL 1982) we are presenting our method in detail. The differences have two sources. First, the numbers used by BARC for the daily ingestion of radionuclides via the diet are higher than LLNL's. Second, BARC's calculation of dose from radionuclide intake utilizes the ICRP system. The net result is that BARC doses are consistently higher than LLNL doses, and in this respect are more conservative

Preparation of denatured sup(99m)Tc labeled HSA aerosols of different median diameters for various imaging studies

Energy Technology Data Exchange (ETDEWEB)

Raghunath, B.; Kotrappa, P.; Soni, P.S.; Ganatra, R.D. (Bhabha Atomic Research Centre, Bombay (India))

1982-02-01

The preparation of denatured sup(99m)Tc-labelled human serum albumin (HSA) aerosols of different median diameters is described using the BARC (Bhabha Atomic Research Centre) dry aerosol generation and delivery system. The applications of these radioactive aerosols are demonstrated in aerosol scintigraphy of lungs, mucociliary movement studies and lymphoscintigraphy in rabbits. It is concluded that the BARC system gives a simplified, rapid and versatile procedure for generation of denatured volume tagged HSA aerosols for a variety of clinical applications.

Preparation of denatured sup(99m)Tc labeled HSA aerosols of different median diameters for various imaging studies

International Nuclear Information System (INIS)

Raghunath, B.; Kotrappa, P.; Soni, P.S.; Ganatra, R.D.

1982-01-01

The preparation of denatured sup(99m)Tc-labelled human serum albumin (HSA) aerosols of different median diameters is described using the BARC (Bhabha Atomic Research Centre) dry aerosol generation and delivery system. The applications of these radioactive aerosols are demonstrated in aerosol scintigraphy of lungs, mucociliary movement studies and lymphoscintigraphy in rabbits. It is concluded that the BARC system gives a simplified, rapid and versatile procedure for generation of denatured volume tagged HSA aerosols for a variety of clinical applications. (U.K.)

Radiation protection service for a nucleonic control system of continuous casting plant after events of accident

International Nuclear Information System (INIS)

Chakrabarti, Santanu; Massand, O.P.

1998-01-01

Extensive use of nucleonic control systems like level controllers was observed during radiation protection surveys in industries such as refineries, steel plants etc., located in the eastern region of India. There were two accidents at continuous casting plant in 1995 which affected the nucleonic control system installed in 1992. The authorities contacted Bhabha Atomic Research Centre (BARC) for radiation protection surveys for the involved nucleonic gauges. The present paper describes the radiation protection services rendered by BARC during such accidents. (author)

Nuclear research centres - Their evolution in the Indian context

International Nuclear Information System (INIS)

Kakodkar, A.; Grover, R.B.

2001-01-01

In a developing country, the role of the nuclear research centres (NRC) is quite large as it involves research, development, demonstration and deployment. The Bhabha Atomic Research Centre (BARC), the mother institution for all nuclear activities in India, has played this role for more than 40 years. With the successful deployment, the subsequent growth and management, both in the power and non-power sectors, is carried out by public sector enterprises. BARC continues to provide R and D support for improving performance and safety, technologies for repair and refurbishment, plant life management and evolutionary changes in the plant design. It has the responsibility of managing the backend of the fuel cycle. BARC has also been the nucleus for new research centres devoted to the development of fast reactors, accelerators and lasers. National NRCs, which provide exciting R and D opportunities with future orientation, provide assurance of availability of requisite skills and expertise while at the same time working for the futuristic objectives of the country. (author)

A web based on-line radiation early warning system for emergency preparedness and response centre

International Nuclear Information System (INIS)

Bhujbal, Vaibhav; Saindane, Shashank S.; Narasaiah, M.V.R.; Murali, S.

2018-01-01

The topography of the Bhabha Atomic Research Centre, Trombay site, where all major components of nuclear fuel cycle activities are located is very complex in nature. The assessment of the radiological impact, if any, due to atmospheric releases from these facilities within BARC site is being carried out by using a Local Area Network (LAN) based Radiation Early Warning System and meteorological parameters. The upgraded system is aimed at providing data during normal operation of the various facilities at site and for providing early warning to decision makers in case of any onset of an emergency. It is carried out by acquiring both on-line and off-line data on releases from the plants, the environmental radiation dose rate at selected locations and other related parameters. The monitors placed at these selected locations including strategic point around the BARC site can also help in detecting any attempt of unauthorized trafficking of the radioactive sources. This paper explains different aspects of the system operating at BARC

X-ray imaging for non-destructive testing of internal disorders in fruits

International Nuclear Information System (INIS)

Thomas, Paul

1998-01-01

A physiological disorder known as spongy tissue involving damage of the mesocarp (flesh) affects 20 to 30 percent of mango fruits, particularly Alphonso, the leading commercial variety of India. Large sized fruits and those more advanced in maturity or harvested when ripe show increased incidence of spongy tissue. The mango processing industry is also facing quality control problems and economic loss as weevil-infested fruits can contaminate the processed pulp as well as the processing machinery with insect, fecal and feed remnants. Studies undertaken in the Food Technology Division, Bhabha Atomic Research Centre (BARC), Mumbai with assistance from Radiation Standards Section, Radiological Unit, BARC Hospital and ECIL, Hyderabad, have shown that both spongy tissue affected and seed weevil infested mango fruits can be detected by x-ray transmittance. The resulting image can be used to detect affected fruits. An automated system for detecting and rejecting mangoes with spongy tissue or seed weevil infestation is under development in collaboration with the Electronic Systems Division, BARC. (author)

Progress report: 1996 Radiation Safety Systems Division

International Nuclear Information System (INIS)

Bhagwat, A.M.; Sharma, D.N.; Abani, M.C.; Mehta, S.K.

1997-01-01

The activities of Radiation Safety Systems Division include (i) development of specialised monitoring systems and radiation safety information network, (ii) radiation hazards control at the nuclear fuel cycle facilities, the radioisotope programmes at Bhabha Atomic Research Centre (BARC) and for the accelerators programme at BARC and Centre for Advanced Technology (CAT), Indore. The systems on which development and upgradation work was carried out during the year included aerial gamma spectrometer, automated environment monitor using railway network, radioisotope package monitor and air monitors for tritium and alpha active aerosols. Other R and D efforts at the division included assessment of risk for radiation exposures and evaluation of ICRP 60 recommendations in the Indian context, shielding evaluation and dosimetry for the new upcoming accelerator facilities and solid state nuclear track detector techniques for neutron measurements. The expertise of the divisional members was provided for 36 safety committees of BARC and Atomic Energy Regulatory Board (AERB). Twenty three publications were brought out during the year 1996. (author)

Current Status of Radiation Processing of Natural Polymers in India

International Nuclear Information System (INIS)

Ramnani, S.P.

2010-01-01

Radiation processing is being used on commercial basis in India since 1974 with the operation of ISOMED plant for radiation sterilization of medical products and Electron beam machine (ILU-6) in 1986. Since then many new products and processes have been investigated and some of them have culminated into useful applications. Many Indian industries produce and process natural polymers for local consumption and export. India exports about 120,000 tons of polysaccharides every year. Natural polysaccharides like guar gum, gum acacia, gum tora, agar, psylium husk etc are treated with gamma radiation mainly for controlling microbial contamination and sterilization. Radiation processing has also been used to reduce molecular weight of the polysaccharides in some applications. Recently, a few new applications have emerged where natural polysaccharides are used as additives and which play important role in controlling basic radiation chemistry reactions to produce useful products. Developed at BARC, radiation processed wound dressings, superabsorbent materials and low molecular weight chitosan are the products which have been used and could find potential applications in health care and agriculture sector. Radiation processed hydrogel wound dressings containing natural polysaccharides have already been commercialized. Some of the applications recently developed at BARC using natural polymers are briefly described below

Monsoonal and ENSO impacts on particle fluxes and the biological pump in the Indian Ocean

Digital Repository Service at National Institute of Oceanography (India)

Rixen, T.; Ramaswamy, V.; Gaye, B.; Herunadi, B.; Maier-Reimer, E.; Bange, H.W.; Ittekkot, V.

and CO 2 limit the growth of cyano- bacteria [Barce los e Ramos et al., 2007; Falkowski, 1997] or that a phosphate concentration of 0.35 µmol kg -1 repre- sents a threshold below which growth rates fall below graz- ing rates. The resulting net loss... CO 2 levels as shown by mesocosm experiments [Barce los e Ramos et al., 2007]. However, some evidence for such an effective organic car- bon export was already found not only in the Arabian Sea [Rixen and Ittekkot, 2005] but also...

A Seven-Year Major and Trace Element Study of Rain Water in the Barcés River Watershed, A Coruña, NW Spain

Science.gov (United States)

Delgado, Jordi; Cereijo-Arango, José Luis; Juncosa-Rivera, Ricardo

2016-04-01

Precipitation constitutes an important source of soluble materials to surface waters and, in areas where they are diluted precipitation (either dry or wet) it can be the most relevant solute source. Certain trace elements may have a limited natural availability in soils and rocks although they can be important with respect the operation of different biogeochemical cycles, for the computation of local/regional atmospheric pollutant loads or from the global mass budget. In the present study we report the results obtained in a long-lasting (December 2008-December 2015) monitoring survey of the chemical composition of bulk precipitation as monthly-integrated samples taken at the headwaters of the Barcés river watershed (A Coruña, Spain). This location was selected based on the necessity of quantification of the chemical composition and elemental loads associated with the different water types (stream water, ground water and precipitation) contributing to the flooding of the Meirama lake. Available data includes information on meteorological parameters (air temperature, relative humidity, atmospheric pressure, wind speed and direction, total and PAR radiation and precipitation) as well as a wide bundle of physico-chemical (pH, redox, electrical conductivity, alkalinity, Li, Na, K, Mg, Ca, Sr, Mn, Fe, NH4, Cs, Rb, Ba, Zn, Cu, Sb, Ni, Co, Cr, V, Cd, Ag, Pb, Se, Hg, Ti, Sn, U, Mo, F, Cl, Br, SO4, NO3, NO2, Al, As, PO4, SIO2, B, O2, DIC, DOC) and isotopic (18Ov-smow and 2Hv-smow) constituents. The average pH of local precipitation is 5.6 (n=65) which is consistent with the expected value for natural, unpolluted rain water. Most of the studied elements (eg. Na, Ca, K, Mg, SiO2, etc.) shows significant increases in their concentration in the dry period of the year. That points towards a more significant contribution of dry deposition in these periods compared with the wet ones. The average electrical conductivity is about 67 S/cm while the average chloride

Regulatory inspection of BARC facilities

International Nuclear Information System (INIS)

Rajdeep; Jayarajan, K.

2017-01-01

Nuclear and radiation facilities are sited, constructed, commissioned, operated and decommissioned, in conformity with the current safety standards and codes. Regulatory bodies follow different means to ensure compliance of the standards for the safety of the personnel, the public and the environment. Regulatory Inspection (RI) is one of the important measures employed by regulatory bodies to obtain the safety status of a facility or project and to verify the fulfilment of the conditions stipulated in the consent

BARC: A Novel Apoptosis Regulator

Science.gov (United States)

2005-06-01

References ...................................................................................... 11 A ppendices ...that acute inhibition of Bcl-2 by the functionally interacts with inositol 1,4,5-trisphosphate (IP 3) re- green tea compound epigallocatechin gallate

H N Ghosh, BARC, Mumbai

Indian Academy of Sciences (India)

admin

Relentless efforts are underway allover the world to develop a low cost efficient solar cell for the solution of global energy crisis. Dye sensitized solar cell (DSSC) appeared to be one of the good discovery for the solution of energy problem. We have been involved in studying ultrafast interfacial electron transfer dynamics in.

Axial-vector gluons and the fine structure of heavy quark--antiquark systems

International Nuclear Information System (INIS)

Feinberg, G.; Lynn, B.; Sucher, J.

1979-01-01

We point out that two models of the origin of spin-dependent forces in heavy quark systems make very different predictions about the relative size of these forces in c-barc and b-barb. The model in which these forces are relativistic corrections to vector or scalar gluon exchange predicts smaller spin-dependent effects in b-barb than in c-barc while a model in which these forces are due to exchange of axial-vector gluons predicts a similar size for spin-dependent splittings in the two systems

AMS using 14UD Pelletron at TIFR, Mumbai: present status and future prospects

International Nuclear Information System (INIS)

Surendran, P.; Gupta, A.K.; Nair, J.P.; Mahata, K.; Shrivastava, A.; Yadav, M.L.; Sparrow, H.; Thomas, R.G.; Bhagwat, P.V.; Kailas, S.; Kale, R.M.

2011-01-01

The AMS (Accelerator Mass Spectrometry) is a versatile tool employed in multidisciplinary programmes. The AMS programme at the BARC-TIFR 14UD Pelletron accelerator has been initiated with major emphasis on the determination of 36 Cl concentration in environment in general and water samples in particular. Preliminary measurements related to detection of 129 I have been carried out in recent past. The system used for AMS measurement is based on a 14 MV Tandem Accelerator. In this paper, the status and future prospects of AMS programme at BARC-TIFR Pelletron Accelerator Facility are presented

Effector-Triggered Immunity Determines Host Genotype-Specific Incompatibility in Legume-Rhizobium Symbiosis.

Science.gov (United States)

Yasuda, Michiko; Miwa, Hiroki; Masuda, Sachiko; Takebayashi, Yumiko; Sakakibara, Hitoshi; Okazaki, Shin

2016-08-01

Symbiosis between legumes and rhizobia leads to the formation of N2-fixing root nodules. In soybean, several host genes, referred to as Rj genes, control nodulation. Soybean cultivars carrying the Rj4 gene restrict nodulation by specific rhizobia such as Bradyrhizobium elkanii We previously reported that the restriction of nodulation was caused by B. elkanii possessing a functional type III secretion system (T3SS), which is known for its delivery of virulence factors by pathogenic bacteria. In the present study, we investigated the molecular basis for the T3SS-dependent nodulation restriction in Rj4 soybean. Inoculation tests revealed that soybean cultivar BARC-2 (Rj4/Rj4) restricted nodulation by B. elkanii USDA61, whereas its nearly isogenic line BARC-3 (rj4/rj4) formed nitrogen-fixing nodules with the same strain. Root-hair curling and infection threads were not observed in the roots of BARC-2 inoculated with USDA61, indicating that Rj4 blocked B. elkanii infection in the early stages. Accumulation of H2O2 and salicylic acid (SA) was observed in the roots of BARC-2 inoculated with USDA61. Transcriptome analyses revealed that inoculation of USDA61, but not its T3SS mutant in BARC-2, induced defense-related genes, including those coding for hypersensitive-induced responsive protein, which act in effector-triggered immunity (ETI) in Arabidopsis. These findings suggest that B. elkanii T3SS triggers the SA-mediated ETI-type response in Rj4 soybean, which consequently blocks symbiotic interactions. This study revealed a common molecular mechanism underlying both plant-pathogen and plant-symbiont interactions, and suggests that establishment of a root nodule symbiosis requires the evasion or suppression of plant immune responses triggered by rhizobial effectors. © The Author 2016. Published by Oxford University Press on behalf of Japanese Society of Plant Physiologists. All rights reserved. For permissions, please email: journals.permissions@oup.com.

Waste container and method for containing waste

International Nuclear Information System (INIS)

Ono, Akira; Matsushita, Mitsuhiro; Doi, Makoto; Nakatani, Seiichi.

1990-01-01

In a waste container, water-proof membranes and rare earth element layers are formed on the inner surface of a steel plate concrete container in which steel plates are embedded. Further, rear earth element detectors are disposed each from the inner side of the steel plate concrete container by way of a pressure pipe to the outer side of the container. As a method for actually containing wastes, when a plurality of vessels in which wastes are fixed are collectively enhoused to the waste container, cussioning materials are attached to the inner surface of the container and wastes fixing containers are stacked successively in a plurality of rows in a bag made of elastic materials. Subsequently, fixing materials are filled and tightly sealed in the waste container. When the waste container thus constituted is buried underground, even if it should be deformed to cause intrusion of rain water to the inside of the container, the rare earth elements in the container dissolved in the rain water can be detected by the detectors, the containers are exchanged before the rain water intruding to the inner side is leached to the surrounding ground, to previously prevent the leakage of radioactive nuclides. (K.M.)

Design and development of weld inspection manipulator for reactor pressure vessel of TAPS-1

International Nuclear Information System (INIS)

Chatterjee, H.; Singh, J.P.; Ranjon, R.; Kulkarni, M.P.; Patel, R.J.

2013-01-01

The reactor pressure vessel (RPV) of TAPS-1 BWR contains six longitudinal and four circumferential welds. Periodical in-service inspection of these weld joints has been a regulatory issue pending for long. In the 22 nd refuelling outage in July 2012 the inspection of L1-1, L1-2 longitudinal welds as well as their junctions with C1 circumferential weld were proposed to be done using ultrasonic technique. Approaching these welds from OD side of the RPV is a difficult and tedious task. Therefore it was decided to examine these welds from ID side of the RPV by filling the cavity with water and approaching the RPV from top. No technology was locally available to take the probes at a depth of 10-12 m under water. NPCIL approached RTD, BARC to develop an underwater manipulator to accomplish this task. RTD took up this work as a challenge and came out with the design of manipulator. The weld inspection manipulator (WIM) was fabricated on a war foot basis, tested and successfully implemented in the reactor for the first time in TAPS history. The entire activity was completed in three months time. This article gives the details of design, manufacturing, performance testing, qualification trials and implementation of WIM in the reactor. Ultrasonic testing techniques were developed by QAD, BARC which are not covered in this article. (author)

High-etch-rate bottom-antireflective coating and gap-fill materials using dextrin derivatives in via first dual-Damascene lithography process

Science.gov (United States)

Takei, Satoshi; Sakaida, Yasushi; Shinjo, Tetsuya; Hashimoto, Keisuke; Nakajima, Yasuyuki

2008-03-01

The present paper describes a novel class of bottom antireflective coating (BARC) and gap fill materials using dextrin derivatives. The general trend of interconnect fabrication for such a high performance LSI is to apply cupper (Cu)/ low-dielectric-constant (low-k) interconnect to reduce RC delay. A via-first dual damascene process is one of the most promising processes to fabricate Cu/ low-k interconnect due to its wide miss-alignment margin. The sacrificial materials containing dextrin derivatives under resist for lithography were developed in via-first dual damascene process. The dextrin derivatives in this study was obtained by the esterification of the hydroxyl groups of dextrin resulting in improved solubility in the resist solvents such as propylene glycol monomethylether, propylene glycol monomethylether acetate, and ethyl lactate due to avoid the issue of defects that were caused by incompatability. The etch rate of our developed BARC and gap fill materials using dextrin derivatives was more than two times faster than one of the ArF resists evaluated in a CF4 gas condition using reactive ion etching. The improved etch performance was also verified by comparison with poly(hydroxystyrene), acrylate-type materials and latest low-k materials as a reference. In addition to superior etch performance, these materials showed good resist profiles and via filling performance without voids in via holes.

Quantum effects and colour transparency in charmonium photoproduction on nuclei

International Nuclear Information System (INIS)

Kopeliovich, B.Z.; Zakharov, B.G.

1991-01-01

A rigorous quantum-mechanical treatment of colour transparency effects in diffractive photoproduction of c-barc-pairs on nuclei was developed. The evolution of the c-barc wave function during propagating through a nucleus is rather a considerable distortion of its form, than a trivial attenuation. One of the manifestations of the quantum effects is a nuclear antishadowing of Ψ' yield, i.e. transparency above one. On the contrary, a considerable nuclear shadowing is predicted for the photoproduction of J/Ψ, which has a much smaller absorption cross section than Ψ'. 26 refs.; 5 figs.; 1 tab

Secondary Containers and Service Containers for Pesticides

Science.gov (United States)

Secondary containers and service containers are used by pesticide applicators in the process of applying a pesticide. EPA does not require secondary containers or service containers to be labeled or to meet particular construction standards. Learn more.

Container crane for sea freight containers

NARCIS (Netherlands)

Luttekes, E.; Rijsenbrij, J.C.

2001-01-01

The invention relates to a container crane for loading and unloading seaborne containers. The container crane comprises a bridge girder (7), a jib (8), at least two crabs (11, 12) which can travel along the said bridge girder and/or jib and are provided with hoist means for lifting and lowering the

FAUST/CONTAIN; FAUST/CONTAIN

Energy Technology Data Exchange (ETDEWEB)

Cherdron, W.; Minges, J.; Sauter, H.; Schuetz, W.

1995-08-01

The FAUNA facility has been restructured after completion of the sodium fire experiments. It is now serving LWR research, cf. report II on program no. 32.21.02 concerning steam explosions. The CONTAIN code system for computing the thermodynamic, aerosol and radiological phenomena in a containment under severe accident conditions is being developed with a new to fission product release and transport. (orig.)

Effectiveness of containment sprays in containment management

International Nuclear Information System (INIS)

Nourbakhsh, H.P.; Perez, S.E.; Lehner, J.R.

1993-05-01

A limited study has been performed assessing the effectiveness of containment sprays-to mitigate particular challenges which may occur during a severe accident. Certain aspects of three specific topics related to using sprays under severe accident conditions were investigated. The first was the effectiveness of sprays connected to an alternate water supple and pumping source because the actual containment spray pumps are inoperable. This situation could occur during a station blackout. The second topic concerned the adverse as well as beneficial effects of using containment sprays during severe accident scenario where the containment atmosphere contains substantial quantities of hydrogen along with steam. The third topic was the feasibility of using containment sprays to moderate the consequences of DCH

APR1400 Containment Simulation with CONTAIN code

Energy Technology Data Exchange (ETDEWEB)

Hwang, Moon Kyu; Chung, Bub Dong [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2010-05-15

The more realistic containment pressure variation predicted by the CONTAIN code through the coupled analysis during a large break loss of coolant accident in the nuclear power plant is expected to provide more accurate prediction for the plant behavior than a standalone MARS-KS calculation. The input deck has been generated based on the already available ARP- 1400 input for CONTEMPT code. Similarly to the CONTEMPT input deck, a simple two-cell model was adopted to model the containment behavior, one cell for the containment inner volume and another cell for the environment condition. The developed input for the CONTAIN code is to be eventually applied for the coupled code calculation of MARS-KS/CONTAIN

APR1400 Containment Simulation with CONTAIN code

International Nuclear Information System (INIS)

Hwang, Moon Kyu; Chung, Bub Dong

2010-01-01

The more realistic containment pressure variation predicted by the CONTAIN code through the coupled analysis during a large break loss of coolant accident in the nuclear power plant is expected to provide more accurate prediction for the plant behavior than a standalone MARS-KS calculation. The input deck has been generated based on the already available ARP- 1400 input for CONTEMPT code. Similarly to the CONTEMPT input deck, a simple two-cell model was adopted to model the containment behavior, one cell for the containment inner volume and another cell for the environment condition. The developed input for the CONTAIN code is to be eventually applied for the coupled code calculation of MARS-KS/CONTAIN

Prenatal Experiences of Containment in the Light of Bion's Model of Container/Contained

Science.gov (United States)

Maiello, Suzanne

2012-01-01

This paper explores the idea of possible proto-experiences of the prenatal child in the context of Bion's model of container/contained. The physical configuration of the embryo/foetus contained in the maternal uterus represents the starting point for an enquiry into the unborn child's possible experiences of its state of being contained in a…

Continuous containment monitoring with containment pressure fluctuation

International Nuclear Information System (INIS)

Dick, J.E.

1996-01-01

The monitoring of the integrity of containments particularly but not exclusively for nuclear plants is dealt with in this invention. While this application is primarily concerned with containment monitoring in the context of the single unit design, it is expected that the concepts presented will be universally applicable to any containment design, including containments for non-nuclear applications such as biological laboratories. The nuclear industry has long been interested in a means of monitoring containment integrity on a continuous basis, that is, while the reactor is operating normally. 12 refs., 2 figs

Resonator controller for the super-conducting LINAC

International Nuclear Information System (INIS)

Joshi, Gopal; Sujo, C.I.; Karande, Jitendra

2001-01-01

A resonator controller has been developed at Electronics Division, BARC, to stabilize the amplitude and phase of RF fields in the super-conducting resonators of BARC-TIFR linac. Due to reduced losses these resonators have intrinsic bandwidth of the order of one hertz at 150MHz whereas the vibration induced center frequency changes are of the order of a few hertz. In the control strategy followed the resonator is made the frequency selective part of an oscillator. The phase lock is achieved by dynamically adding a phase shift in the oscillator. In this paper we present the control strategy, implementation details and performance obtained with this controller. (author)

Indian programme on molten salt cooled nuclear reactors

International Nuclear Information System (INIS)

DuIera, I.V.; Vijayan, P.K.; Sinha, R.K.

2013-01-01

Bhabha Atomic Research Centre (BARC) is developing a 600 MWth pebble bed high temperature reactor, cooled by natural circulation of molten fluoride salts and is capable of supplying process heat at 1000 ℃ to facilitate hydrogen production by splitting water. BARC has also initiated studies for a reactor concept in which salts of molten fluoride fuel and coolant in fluid form, flows through the reactor core of graphite moderator, resulting in nuclear fission within the molten salt. For thorium fuel cycle, this concept is very attractive, since the fuel can be re-processed on-line, enabling it to be an efficient neutron breeder. (author)

Containment

International Nuclear Information System (INIS)

Anon.

1987-01-01

The primary mission of the Containment Group is to ensure that underground nuclear tests are satisfactorily contained. The main goal is the development of sound technical bases for containment-related methodology. Major areas of activity include siting, geologic description, emplacement hole stemming, and phenomenological predictions. Performance results of sanded gypsum concrete plugs on the Jefferson, Panamint, Cornucopia, Labquark, and Bodie events are given. Activities are also described in the following areas: computational capabilities site description, predictive modeling, and cavity-pressure measurement. Containment publications are listed. 8 references

CONTAIN code analyses of direct containment heating experiments

International Nuclear Information System (INIS)

Williams, D.C.; Griffith, R.O.; Tadios, E.L.; Washington, K.E.

1995-01-01

In some nuclear reactor core-melt accidents, a potential exists for molten core-debris to be dispersed into the containment under high pressure. Resulting energy transfer to the containment atmosphere can pressurize the containment. This process, known as direct containment heating (DCH), has been the subject of extensive experimental and analytical programs sponsored by the U.S. Nuclear Regulatory Commission (NRC). The DCH modeling has been an important focus for the development of the CONTAIN code. Results of a detailed independent peer review of the CONTAIN code were published recently. This paper summarizes work performed in support of the peer review in which the CONTAIN code was applied to analyze DCH experiments. Goals of this work were comparison of calculated and experimental results, CONTAIN DCH model assessment, and development of guidance for code users, including development of a standardized input prescription for DCH analysis

Direct containment heating models in the CONTAIN code

International Nuclear Information System (INIS)

Washington, K.E.; Williams, D.C.

1995-08-01

The potential exists in a nuclear reactor core melt severe accident for molten core debris to be dispersed under high pressure into the containment building. If this occurs, the set of phenomena that result in the transfer of energy to the containment atmosphere and its surroundings is referred to as direct containment heating (DCH). Because of the potential for DCH to lead to early containment failure, the U.S. Nuclear Regulatory Commission (USNRC) has sponsored an extensive research program consisting of experimental, analytical, and risk integration components. An important element of the analytical research has been the development and assessment of direct containment heating models in the CONTAIN code. This report documents the DCH models in the CONTAIN code. DCH models in CONTAIN for representing debris transport, trapping, chemical reactions, and heat transfer from debris to the containment atmosphere and surroundings are described. The descriptions include the governing equations and input instructions in CONTAIN unique to performing DCH calculations. Modifications made to the combustion models in CONTAIN for representing the combustion of DCH-produced and pre-existing hydrogen under DCH conditions are also described. Input table options for representing the discharge of debris from the RPV and the entrainment phase of the DCH process are also described. A sample calculation is presented to demonstrate the functionality of the models. The results show that reasonable behavior is obtained when the models are used to predict the sixth Zion geometry integral effects test at 1/10th scale

Direct containment heating models in the CONTAIN code

Energy Technology Data Exchange (ETDEWEB)

Washington, K.E.; Williams, D.C.

1995-08-01

The potential exists in a nuclear reactor core melt severe accident for molten core debris to be dispersed under high pressure into the containment building. If this occurs, the set of phenomena that result in the transfer of energy to the containment atmosphere and its surroundings is referred to as direct containment heating (DCH). Because of the potential for DCH to lead to early containment failure, the U.S. Nuclear Regulatory Commission (USNRC) has sponsored an extensive research program consisting of experimental, analytical, and risk integration components. An important element of the analytical research has been the development and assessment of direct containment heating models in the CONTAIN code. This report documents the DCH models in the CONTAIN code. DCH models in CONTAIN for representing debris transport, trapping, chemical reactions, and heat transfer from debris to the containment atmosphere and surroundings are described. The descriptions include the governing equations and input instructions in CONTAIN unique to performing DCH calculations. Modifications made to the combustion models in CONTAIN for representing the combustion of DCH-produced and pre-existing hydrogen under DCH conditions are also described. Input table options for representing the discharge of debris from the RPV and the entrainment phase of the DCH process are also described. A sample calculation is presented to demonstrate the functionality of the models. The results show that reasonable behavior is obtained when the models are used to predict the sixth Zion geometry integral effects test at 1/10th scale.

Food preservation technologies developed at BARC

International Nuclear Information System (INIS)

Jain, M.P.

2013-01-01

Food irradiation is important as it is being used to disinfest food grains, pulses, wheat flour, rice, semolina, raisins etc; quarantining and shelf life increasing of fruits like mangoes; microbial decontamination of spices; sprout inhibition of tubers and bulbs; shelf life increasing and pathogen control of meat and fish. Category-IV type irradiators based on gamma rays exposure of food are currently being employed for this purpose. Cobalt-60 isotope is produced in the nuclear reactors. Isotope gives gamma rays as its nucleus is unstable. The gamma rays pass through the food items and inhibit sprouting of tubers and bulbs, kill bacteria, virus and the larvae of insects

Commissioning of calorimeter in radiochemical laboratory for non-destructive assay of special nuclear materials

International Nuclear Information System (INIS)

Patra, S.; Mhatre, A.M.; Agarwal, C.; Chaudhury, S.; Pujari, P.K.

2017-01-01

Accounting of special nuclear materials (SNM) in every stages of nuclear fuel cycle is a necessity where one needs the quantitative estimation of SNM in variety of samples like sealed containers or finished products without altering its physical and chemical form. Non-destructive assay (NDA) techniques are capable of assaying such samples by the way of measuring passive/active neutrons/gamma rays or by the measurement of decay heat. Radiochemistry Division has been actively involved in the development and deployment of various NDA methodologies for meeting the demand of nuclear material accounting as and when required. Recently a radiometric calorimeter, developed by Reactor Control Division, E and I Group, BARC, has been installed in Lab C-33, Radiochemistry Division

A standard fission neutron irradiation facility

International Nuclear Information System (INIS)

Sahasrabudhe, S.G.; Chakraborty, P.P.; Iyer, M.R.; Kirthi, K.N.; Soman, S.D.

1979-01-01

A fission neutron irradiation facility (FISNIF) has been set up at the thermal column of the CIRUS reactor at BARC. The spectrum and the flux have been measured using threshold detectors. The paper describes the setting up of the facility, measurement and application. A concentric cylinder containing UO 2 powder sealed inside surrounds the irradiation point of a pneumatic sample transfer system located in the thermal column of the reactor. Samples are loaded in a standard aluminium capsule with cadmium lining and transported pneumatically. A sample transfer time of 1 s can be achieved in the facility. Typical applications of the facility for studying activation of iron and sodium in fission neutrons are also discussed. (Auth.)

Design and development of control instrumentation for the superconducting Linear Accelerator

International Nuclear Information System (INIS)

Joshi, Gopal; Kapatral, R.S.; Jha, K.; Rathod, N.C.; Sujo, C.I.; Ananthakrishnan, T.S.; Narsaiah, A.; Ghodgaonkar, M.D.; Kataria, S.K.; Singh, S.K.

2001-01-01

Electronics Division, BARC is developing the required control instrumentation for the Linear Accelerator (LINAC) coming up at TIFR. This consists of RF systems, CAMAC instruments and the Control and Information System. The control system consists of several identical Local Control Stations (LCS) connected over a LAN to a Main Control Station (MCS). Each LCS consists of a PC, CAMAC crates with functional Modules and RF systems. The MCS will contain two PCs running identical software. Each LCS will cater to two LINAC module each consisting of one cryostat and four resonators. This paper discusses different systems developed and under development in the Electronics Division which play an important role in the control of the LINAC. (author)

Determination of impurities in beryl by neutron activation analysis

International Nuclear Information System (INIS)

Swain, K.K.; Dalvi, Aditi A.; Ajith, Nicy

2015-01-01

Beryl is a chemically complex and highly compositionally variable gem-forming mineral found in a variety of locations worldwide. Pure beryl is colorless, but the presence of impurities imparts colors such as green, blue, yellow, red, and white. It is one of the most important gem minerals and the gems are named by their color. The impurities in beryl can be determined using various analytical techniques. Neutron activation analysis (NAA) is a sensitive technique for multielement analysis of geological samples. Four beryl samples, collected from Nayakund Mehandi Block, Parseoni, Maharashtra, were received from Geological Survey of India (GSI), Pune. Powdered samples (50-100 mg) along with comparators (IAEA Soil-7) were packed in aluminum foils, sealed in an aluminum container and irradiated for 7 days in tray rod facility of Dhruva reactor, BARC, Mumbai. After irradiation, samples were brought to laboratory. Samples were opened, transferred into polyethylene packets and weighed. Gamma activity measurements were carried out using 45% HPGe detector coupled to 8 k multi channel analyzer. For the determination of manganese, which produces relatively shorter lived activation product ( 56 Mn: T 1/2 = 2.56 h), samples were sealed in polyethylene pouches and irradiated in graphite reflector position of Critical facility reactor, BARC, Mumbai. Relative method of NAA was used for concentration calculations. IAEA reference material (RM), SL -1 (lake sediment) was analyzed for quality control. Percentage errors on the measured concentrations of the elements are within ± 8% with respect to the recommended/information values

Under sodium ultrasonic imaging system for PFBR

International Nuclear Information System (INIS)

Patankar, V.H.; Lalwani, S.K.; Agashe, A.A.

2014-01-01

Under Sodium UltraSonic Scanner (USUSS) has been developed to detect the growth and protrusion of fuel sub-assemblies of PFBR, submerged in liquid sodium by using the ultrasonic imaging technique during reactor shut-down when liquid sodium is at 180 ℃. The imaging is carried out prior to every Fuel handling operation. Electronics Division, BARC has designed and developed an 8-Channel Ultrasonic Imaging System (UIS) which consists of 4 downward viewing and 4 side viewing ultrasonic transducers alongwith pulser-receiver, signal processing electronics hardware and software. An automated mechanical scanner developed by IGCAR houses sodium immersible transducers to image the fuel sub assemblies. The system has been successfully tested with dummy protruding and grown FSAs, submerged under liquid sodium. Such ultrasonic imaging systems are not available to India from international market. The USUSS developed indigenously has all the features available in similar systems developed by other countries. After every imaging campaign, the mechanical scanner containing ultrasonic transducers is stored in the Argon filled storage-pit. Before every campaign of USUSS, it is necessary to check the healthiness of the sodium immersible and contaminated ultrasonic transducers, as the under-sodium scanner is decontaminated once in five years. For this purpose, a novel Non Contact Ultrasonic Inspection System (NCUIS) has been designed and developed by Electronics Division, BARC to check the functionality of the high-temperature and contaminated transducers of USUSS, using air-coupled ultrasonic technique. (author)

PREFACE: 5th DAE-BRNS Workshop on Hadron Physics (Hadron 2011)

Science.gov (United States)

Jyoti Roy, Bidyut; Chatterjee, A.; Kailas, S.

2012-07-01

the authors for giving us the manuscripts in good time. The workshop was financially supported by BRNS, DAE, GoI. We also received partial funding support from the India-FAIR coordination centre, Kolkata, for the organization of the India-PANDA discussion meeting. We acknowledge the financial support received from BRNS and DST (Department of Science and Technology). The assistance from various departments of BARC and the Homi Bhabha Centre for Science Education (HBCSE), TIFR is gratefully acknowledged. We also thank the members of the advisory committee and organizing committee and colleagues from NPD and Physics Group, BARC for their contributions. May 2012, Mumbai Bidyut Jyoti Roy A Chatterjee S Kailas Bhabha Atomic Research Centre Hadron 2011 photograph The PDF also contains a list of the workshop's committees and sponsors, photographs from the workshop and the programme of events.

Performance monitoring of zircaloy-4 square fuel channels at TAPS-1 and 2

International Nuclear Information System (INIS)

Akhtar, J.; Ramu, A.; Anilkumar, K.R.; Sharma, B.L.; Bhattacharjee, S.; Ramamurty, U.; Srivastava, S.P.; Prasad, P.N.; Anantharaman, K.

2006-01-01

Tarapur Atomic Power Station is a twin unit Boiling Water Reactors. The initial rated capacity of each unit was 210 MWe. Subsequently due to Secondary Steam Generator tube leak problem, the units were de-rated to 160 MWe in the year 1984-85. The station has completed 36 years of successful commercial operation. TAPS reactor fuel channels are made of Zircaloy-4, material. These are used along with 6x6 array nuclear fuel assemblies. The fuel channels need to be discharged once it reaches an optimum exposure limit and based on the surveillance programme, which monitors the channels performance. NFC has indigenously developed fuel channels for TAPS and these are at various stages of exposure in both the reactor cores. The performance review of these channels was carried out by the experts from TAPS-Site, NPCIL-ED and RED, BARC. The two major factors, which affect fuel channels performance, are (a) Bulge and (b) Bow. The phenomenon of longitudinal bow occurs due to the neutron flux gradient across the channels faces. Studies made on this subject by General Electric (GE) indicated that this channel deflection occurs at a slow rate. Therefore, fuel channels surveillance programme is essential to check the irradiated fuel channels performance in order to replace the fuel channels once it reaches the optimum exposure limit. To estimate the useful life of irradiated fuel channels, channel deflection/bulge measurement inspection system and methodology was developed jointly by TAPS and Centre for Design and manufacture (CDM), BARC. This system was successfully deployed at TAPS. This paper briefly describes the developmental efforts made by Nuclear Fuel Complex (NFC), Hyderabad, NPCIL-Fuel Group, Engg.Directorate, RED/BARC, CDM/BARC. (author)

Status report of pelletron accelerator and ECR based heavy ion accelerator programme

International Nuclear Information System (INIS)

Gupta, A.K.

2015-01-01

The BARC-TIFR Pelletron Accelerator is completing twenty seven years of round-the-clock operation, serving diverse users from institutions within and outside DAE. Over the years, various developmental activities and application oriented programs have been initiated at Pelletron Accelerator Facility, resulting into enhanced utilization of the accelerator. We have also been pursuing an ECR based heavy ion accelerator programme under XII th Plan, consisting of an 18 GHz superconducting ECR (Electron Cyclotron Resonance) ion source and a room temperature RFQ (Radio Frequency Quadrupole) followed by low and high beta superconducting niobium resonator cavities. This talk will provide the current status of Pelletron Accelerator and the progress made towards the ECR based heavy ion accelerator program at BARC. (author)

Recommended numerical nuclear physics data for cutting-edge nuclear technology applications

International Nuclear Information System (INIS)

Ganesan, S.; Srivenkatesan, R.; Anek Kumar; Murthy, C.S.R.C.; Dhekne, P.S.

2005-01-01

This paper introduces some aspects of online nuclear data services at Mumbai as part of today's technology of sharing knowledge of the recommended numerical nuclear physics data for nuclear applications. The physics foundation for cutting-edge technology applications is significantly strengthened by such knowledge generation and sharing techniques. A BARC server is presently mirroring the nuclear data services of the IAEA, Vienna. The users can get all the nuclear data information much faster from the BARC nuclear data mirror website that is now fully operational. The nuclear community is encouraged to develop the habit of accessing the website for recommended values of nuclear data for use in research and applications. The URL is: www-nds.indcentre.org.in (author)

Bhabha Atomic Research Centre: annual report 1986-87

International Nuclear Information System (INIS)

1987-01-01

The Research and Development (R and D) work and achievements of the Bhabha Atomic Research Centre, Bombay, during the financial year 1986-1987 are reported. The R and D activities of BARC cover the entire nuclear fuel cycle, production and use of radioisotopes, radiation protection and also basic research in several disciplines. The report is presented in the chapters entitled: Physical Sciences, Chemical Sciences, Materials and Materials Science, Life Sciences, Radioisotopes, Reactors, Fuel Cycle, Health and Safety, Electronics and Instrumentation, Engineering and General Services. At the end of each chapter are listed the journal articles published, the paper presented at conferences, symposia etc. and technical reports issued by the scientists of BARC in the subject field indicated by the title of the chapter. The R and D work of the outstation units of BARC, namely, Nuclear Research Laboratory at Srinagar, High Altitute Research Laboratory at Gulmarg, Variable Energy Cyclotron Centre at Calcutta and Gauribidanur Seismic Array near Bangalore are also described in the report. The report concludes with a brief account of: (1) transfer of technologies developed at the Centre, (2) activities related to human resource development for nuclear programmes of the country, and (3) progress of design and construction work of Centre for Advanced Technology at Indore. (M.G.B.)

Atomic energy

International Nuclear Information System (INIS)

Ramanna, R.

1978-01-01

Development of nuclear science in India, particularly the research and development work at the Bhabha Atomic Research Centre (BARC), Bombay, is described. Among the wide range of materials developed for specific functions under rigorous conditions are nuclear pure grade uranium, zirconium and beryllium, and conventional materials like aluminium, carbon steel and stainless steels. Radioisotopes are produced and used for tracer studies in various fields. Various types of nuclear gauges and nuclear instruments are produced. Radiations have been used to develop new high yielding groundnut mutants with large kernals. The sterile male technique for pest control and radiosterilization technique to process potatoes, onions and marine foods for storage are ready for exploitation. Processes and equipment have been developed for production of electrolytic hydrogen, electrothermal phosphorus and desalinated water. Indigenously manufactured components and materials are now being used for the nuclear energy programme. Indian nuclear power programme strategy is to build heavy water reactors and to utilise their byproduct plutonium and depleted uranium to feed fast breeder reactors which will produce more fissile material than burnt. Finally a special mention has been made of the manpower development programme of the BARC. BARC has established a training school in 1957 giving advanced training in physics, chemistry and various branches of engineering and metallurgy

Monte Carlo simulation of calibration of shadow shield scanning bed whole body monitor using different size BOMAB phantoms

International Nuclear Information System (INIS)

Bhati, S.; Patni, H.K.; Singh, I.S.; Garg, S.P.

2005-01-01

A shadow shield scanning bed whole body monitor incorporating a (102 mm dia x 76 mm thick) NaI(Tl) detector, is employed for assessment of high-energy photon emitters at BARC. The monitor is calibrated using a Reference BOMAB phantom representative of an average Indian radiation worker. However to account for the size variation in the physique of workers, it is required to calibrate the system with different size BOMAB phantoms which is both difficult and expensive. Therefore, a theoretical approach based on Monte Carlo techniques has been employed to calibrate the system with BOMAB phantoms of different sizes for several radionuclides of interest. A computer program developed for this purpose, simulates the scanning geometry of the whole body monitor and computes detection efficiencies for the BARC Reference phantom (63 kg/168 cm), ICRP Reference phantom (70 kg/170 cm) and several of its scaled versions covering a wide range of body builds. The detection efficiencies computed for different photon energies for BARC Reference phantom were found to be in very good agreement with experimental data, thus validating the Monte Carlo scheme used in the computer code. The results from this study could be used for assessment of internal contamination due to high-energy photon emitters for radiation workers of different physiques. (author)

Reactor container

International Nuclear Information System (INIS)

Ichiki, Tadaharu; Saba, Kazuhisa.

1979-01-01

Purpose: To improve the earthquake resistance as well as reduce the size of a container for a nuclear reactor with no adverse effects on the decrease of impact shock to the container and shortening of construction step. Constitution: Reinforcing profile steel materials are welded longitudinally and transversely to the inner surface of a container, and inner steel plates are secured to the above profile steel materials while keeping a gap between the materials and the container. Reactor shielding wall planted to the base concrete of the container is mounted to the pressure vessel, and main steam pipeways secured by the transverse beams and led to the outside of container is connected. This can improve the rigidity earthquake strength and the safetiness against the increase in the inside pressure upon failures of the container. (Yoshino, Y.)

7 CFR 906.340 - Container, pack, and container marking regulations.

Science.gov (United States)

2010-01-01

... 7 Agriculture 8 2010-01-01 2010-01-01 false Container, pack, and container marking regulations... AGRICULTURE ORANGES AND GRAPEFRUIT GROWN IN LOWER RIO GRANDE VALLEY IN TEXAS Container and Pack Requirements § 906.340 Container, pack, and container marking regulations. (a) No handler shall handle any variety of...

Reactor container

International Nuclear Information System (INIS)

Naruse, Yoshihiro.

1990-01-01

The thickness of steel shell plates in a reactor container embedded in sand cussions is monitored to recognize the corrosion of the steel shell plates. That is, the reactor pressure vessel is contained in a reactor container shell and the sand cussions are disposed on the lower outside of the reactor container shell to elastically support the shell. A pit is disposed at a position opposing to the sand cussions for measuring the thickness of the reactor container shell plates. The pit is usually closed by a closing member. In the reactor container thus constituted, the closing member can be removed upon periodical inspection to measure the thickness of the shell plates. Accordingly, the corrosion of the steel shell plates can be recognized by the change of the plate thickness. (I.S.)

A container

DEFF Research Database (Denmark)

2012-01-01

A container assembly for the containment of fluids or solids under a pressure different from the ambient pressure comprising a container (2) comprising an opening and an annular sealing, a lid (3) comprising a central portion (5) and engagement means (7) for engaging the annular flange, and sealing...... means (10) wherein the engagement means (7) is adapted, via the sealing means, to seal the opening when the pressure of the container assembly differs from the ambient pressure in such a way that the central portion (5) flexes in the axial direction which leads to a radial tightening of the engagement...... means (7) to the container, wherein the container further comprises locking means (12) that can be positioned so that the central portion is hindered from flexing in at least one direction....

Empty Container Logistics

Directory of Open Access Journals (Sweden)

Jakov Karmelić

2012-05-01

Full Text Available Within the whole world container traffic, the largest share of containers is in the status of repositioning. Container repositioning results from the need for harmonization between the point of empty container accumulation and the point of demand, and waiting time for the availability of the first next transport of cargo. This status of containers on the container market is the consequence of imbalances in the worldwide trade distribution on most important shipping routes. The need for fast and effective reallocation of empty containers causes high costs and often represents an obstacle affecting the efficiency of port container terminals and inland carriers.In accordance with the above issue, this paper is mainly focused on the analysis of the data concerning global container capacities and the roots of container equipment imbalances, with the aim of determining the importance of empty container management and the need for empty container micro-logistic planning at the spread port area.

Rare earths: harvesting basic research for technology

International Nuclear Information System (INIS)

Jagatap, B.N.

2014-01-01

In recent years, rare earths are increasingly becoming a versatile platform for basic research that presents enormous technological potentials. A variety of nano-sized inorganic matrices varying from oxides, phosphates, gallates and aluminates, tungstates, stannates, vanadates to fluorides doped with different lanthanide ions have been synthesized and their optical properties have been investigated in the Chemistry Group, BARC. Another interesting application is laser cooling of solids using rare earth doped glasses with potential applications in remote cooling of electronic devices. Combining the luminescence properties of rare earths with photonic crystals is yet another potent area with wide ranging applications. In this presentation we provide an overview of these developments with examples from the R and D programs of the Chemistry Group, BARC

Progress report of Technical Physics Division: April 1980 - March 1982

International Nuclear Information System (INIS)

Chaudhry, Ramesh; Vijendran, P.

1983-01-01

Activities, with an individual summary of each, of the Technical Physics Division (TPD) of the Bhabha Atomic Research Centre (BARC), Bombay are reported for the period April 1980 - March 1982. The major thrust of the TPD's work has been in: (i) design and fabrication of instruments, devices and equipment and (ii) development of techniques in the frontline research and technology areas like vacuum science, surface analysis, cryogenics and crystal growing. The Division also provided custombuilt electronics equipment, vacuum systems and glass components and devices to the various Divisions of BARC and other units of the DAE. Training and manpower development activities and technology transfer activities are also reported. Lists of seminars, colloquia, publications during the period of the report are given. (M.G.B.)

A container for containing and protecting a radioactive substance

International Nuclear Information System (INIS)

1974-01-01

The invention relates to a container adapted to contain and protect a radio-active substance. That container comprises a heat sensitive device for automatically (and, preferably, sealingly) enclosing and protecting the radio-active substance, should room temperature reach a predetermined level. Thus, the radio-active substance cannot escape in case of fire. Preferably, a bolt is also provided, capable of being actuated at a temperature slightly above the temperature actuating the protective device so as to maintain the radioactive substance protected. This can be applied to containers containing a radio-active substance such as polonium 210 [fr

Nuclear reactor container

International Nuclear Information System (INIS)

Ishiyama, Takenori.

1989-01-01

This invention concerns a nuclear reactor container in which heat is removed from a container by external water injection. Heat is removed from the container by immersing the lower portion of the container into water and scattering spary water from above. Thus, the container can be cooled by the spray water falling down along the outer wall of the container to condensate and cool vapors filled in the container upon occurrence of accidents. Further, since the inside of the container can be cooled also during usual operation, it can also serve as a dry well cooler. Accordingly, heat is removed from the reactor container upon occurrence of accidents by the automatic operation of a spray device corresponding to the change of the internal temperature and the pressure in the reactor container. Further, since all of these devices are disposed out of container, maintenance is also facilitated. (I.S.)

Storage Space Allocation of Inbound Container in Railway Container Terminal

Directory of Open Access Journals (Sweden)

Li Wang

2014-01-01

Full Text Available Efficient storage strategy of railway container terminals is important in balancing resource utilization, reducing waiting time, and improving handling efficiency. In this paper, we consider the formulation and solution algorithm for storage space allocation problem of inbound containers in railway container terminal. The problem is formulated as two-stage optimization models, whose objectives are balancing the workload of inbound containers and reducing the overlapping amounts. An algorithm implement process based on rolling horizon approach is designed to solve the proposed models. Computational experiments on an actual railway container terminal show that the proposed approach is effective to solve space allocation problem of inbound container and is significant for the operation and organization of railway container terminals.

Fibre-concrete container

International Nuclear Information System (INIS)

2000-01-01

In this leaflet the fibre-concrete container for radioactive wastes is described. The fibre container is made of fibre-concrete that contains cement, aggregate, sand, filter, flame-silica, super-plastificator, water and scattered metal fibres. The fibre-concrete container has a dice shape with outer dimension 1.7 x 1.7 x 1.7 m. It is mounted of a container body, a container cover and two caps. Total weight of container is 4,240 kg, maximum weight of loaded container do not must exceed 15,000 kg. The physical and mechanical properties of the fibre-concrete container are described in detail. The fibre-concrete container manufactured for storing of low and intermediate radioactive wastes. A fibre-concrete container utilization to store of radioactive wastes solves these problems: increase of stability of stored packages of radioactive waste; watertightness within 300 years at least; static stability of bearing space; better utilization of bearing spaces; insulation of radioactive waste in a case of seismic and geological event; increase of fire resistance; and transport of radioactive waste

Containment Loads Analysis for CANDU6 Reactor using CONTAIN 2.0

International Nuclear Information System (INIS)

Kim, Tae H.; Yang, Chae Y.

2013-01-01

The containment plays an important role to limit the release of radioactive materials to the environment during design basis accidents (DBAs). Therefore, the containment has to maintain its integrity under DBA conditions. Generally, a containment functional DBA evaluation includes calculations of the key containment loads, i. e., pressure and temperature effects associated with a postulated large rupture of the primary or secondary coolant system piping. In this paper, the behavior of containment pressure and temperature was evaluated for loss of coolant accidents (LOCAs) of the Wolsong unit 1 in order to assess the applicability of CONTAIN 2.0 code for the containment loads analysis of the CANDU6 reactor. The containment pressure and temperature of the Wolsong unit 1 were evaluated using the CONTAIN 2.0 code and the results were compared with the CONTEMPT4 code. The peak pressure and temperature calculated by CONTAIN 2.0 agreed well with those of CONTEMPT4 calculation. The overall result of this analysis shows that the CONTAIN 2.0 code can apply to the containment loads analysis for the CANDU6 reactor

Group 4. Containment

International Nuclear Information System (INIS)

McCauley, V.S.; Keiser, J.R.

1992-01-01

This paper summarizes the findings of the Containment Working Group which met at the Workshop on Radioactive, Hazardous, and/or Mixed Waste Sludge Management. The Containment Working Group (CWG) examined the problems associated with providing adequate containment of waste forms from both short- and long-term storage. By its nature, containment encompasses a wide variety of waste forms, storage conditions, container types, containment schemes, and handling activities. A containment system can be anything from a 55-gal drum to a 100-ft-long underground vault. Because of the diverse nature of containment systems, the CWG chose to focus its limited time on broad issues that are applicable to the design of any containment system, rather than attempting to address problems specific to a particular containment system or waste-form type. Four major issues were identified by the CWG. They relate to: (1) service conditions and required system performance; (2) ultimate disposition; (3) cost and schedule; and (4) acceptance criteria, including quality assurance/quality control (QA/QC) concerns. All of the issues raised by the group are similar in that they all help to define containment system requirements

Primary standardization of cesium-137 for international intercomparison

International Nuclear Information System (INIS)

Srivastava, P.K.

1977-01-01

Primary standards of cesium-137 are of great importance for precise radiation measurements because, due to its simple decay-scheme and long half-life, it is widely used for the calibration of radiation detectors. Also 137 Cs is used for the measurement of fission-yield and uranium burn-up in reactor engineering studies. In view of these, an international intercomparison was organised on a limited scale to correlate the standards established at the Bhabha Atomic Research Centre (BARC), Bombay(India) and Physikalisch-Technische Bundesanstalt (PTB), West Germany. The ''efficiency tracing technique'' was developed at BARC for the primary standardization of 137 Cs for this intercomparison. Two tracers, namely 82 Br and 60 Co, were employed to trace the beta efficiency of the 4 πβ-γ coincidence counting system. It is shown that this technique offers high accuracy and inherent reliability. The ''tracing-technique'' for 137 Cs standardization is briefly described. The gravimetric method of dilution and preparation of mixed sources of 137 Cs - 82 Br and 137 Cs - 60 Co are given. The various counting parameters and settings are included. Data reduction and the estimation of systematic and statistical errors are discussed. The results of the intercomparison, which are also included, show that the agreement between the measurments of BARC and PTB is within 0.5%. (author)

Reactor container

International Nuclear Information System (INIS)

Fukazawa, Masanori.

1991-01-01

A system for controlling combustible gases, it has been constituted at present such that the combustible gases are controlled by exhausting them to the wet well of a reactor container. In this system, however, there has been a problem, in a reactor container having plenums in addition to the wet well and the dry well, that the combustible gases in such plenums can not be controlled. In view of the above, in the present invention, suction ports or exhaust ports of the combustible gas control system are disposed to the wet well, the dry well and the plenums to control the combustible gases in the reactor container. Since this can control the combustible gases in the entire reactor container, the integrity of the reactor container can be ensured. (T.M.)

Container transport direct call – logistic solution to container transport via Estonia

Directory of Open Access Journals (Sweden)

A. Tolli

2007-12-01

Full Text Available Container transport in the world grows up to 12 % every year. Chinese container transport contributes majority of container flows in international container transport. Many world seaports compete for Chinese container flows and make eff orts to get investments and direct calls from China to their ports. Estonia has a possibility to decrease its large dependence and risks due to the transit of oil and oil products and coal with the help of container flows from China. In addition to a favorable geographical location Estonia has several other important arguments, like suffi cient land in the harbours for developing a container terminal to launch extensive container transport transit from China. Port of St. Petersburg, container transport port closest to Estonia by the Baltic Sea, is overloaded. Estonia can compete for container flows directed to Moscow, Nizhniy Novgorod, Kazan and Kaluga. Construction of an international high-tech container terminal in Port of Tallinn serves as one important precondition for directing Russian transit container flows through Estonia. Such a container terminal could service also larger vessels and container flows from China. Container lines and container terminals operating as alliances are jointly able to substantially increase container flows through countries.

Empty Container Logistics

OpenAIRE

Jakov Karmelić; Čedomir Dundović; Ines Kolanović

2012-01-01

Within the whole world container traffic, the largest share of containers is in the status of repositioning. Container repositioning results from the need for harmonization between the point of empty container accumulation and the point of demand, and waiting time for the availability of the first next transport of cargo. This status of containers on the container market is the consequence of imbalances in the worldwide trade distribution on most important shipping routes. The need for fast a...

Containment loads due to direct containment heating and associated hydrogen behavior: Analysis and calculations with the CONTAIN code

International Nuclear Information System (INIS)

Williams, D.C.; Bergeron, K.D.; Carroll, D.E.; Gasser, R.D.; Tills, J.L.; Washington, K.E.

1987-05-01

One of the most important unresolved issues governing risk in many nuclear power plants involves the phenomenon called direct containment heating (DCH), in which it is postulated that molten corium ejected under high pressure from the reactor vessel is dispersed into the containment atmosphere, thereby causing sufficient heating and pressurization to threaten containment integrity. Models for the calculation of potential DCH loads have been developed and incorporated into the CONTAIN code for severe accident analysis. Using CONTAIN, DCH scenarios in PWR plants having three different representative containment types have been analyzed: Surry (subatmospheric large dry containment), Sequoyah (ice condenser containment), and Bellefonte (atmospheric large dry containment). A large number of parameter variation and phenomenological uncertainty studies were performed. Response of DCH loads to these variations was found to be quite complex; often the results differ substantially from what has been previously assumed concerning DCH. Containment compartmentalization offers the potential of greatly mitigating DCH loads relative to what might be calculated using single-cell representations of containments, but the actual degree of mitigation to be expected is sensitive to many uncertainties. Dominant uncertainties include hydrogen combustion phenomena in the extreme environments produced by DCH scenarios, and factors which affect the rate of transport of DCH energy to the upper containment. In addition, DCH loads can be aggravated by rapid blowdown of the primary system, co-dispersal of moderate quantities of water with the debris, and quenching of de-entrained debris in water; these factors act by increasing steam flows which, in turn, accelerates energy transport. It may be noted that containment-threatening loads were calculated for a substantial portion of the scenarios treated for some of the plants considered

Reactor containment

International Nuclear Information System (INIS)

Kawabe, Ryuhei; Yamaki, Rika.

1990-01-01

A water vessel is disposed and the gas phase portion of the water vessel is connected to a reactor container by a pipeline having a valve disposed at the midway thereof. A pipe in communication with external air is extended upwardly from the liquid phase portion to a considerable height so as to resist against the back pressure by a waterhead in the pipeline. Accordingly, when the pressure in the container is reduced to a negative level, air passes through the pipeline and uprises through the liquid phase portion in the water vessel in the form of bubbles and then flows into the reactor container. When the pressure inside of the reactor goes higher, since the liquid surface in the water vessel is forced down, water is pushed up into the pipeline. Since the waterhead pressure of a column of water in the pipeline and the pressure of the reactor container are well-balanced, gases in the reactor container are not leaked to the outside. Further, in a case if a great positive pressure is formed in the reactor container, the inner pressure overcomes the waterhead of the column of water, so that the gases containing radioactive aerosol uprise in the pipeline. Since water and the gases flow being in contact with each other, this can provide the effect of removing aerosol. (T.M.)

Shielding container

International Nuclear Information System (INIS)

Darling, K.A.M.

1981-01-01

A shielding container incorporates a dense shield, for example of depleted uranium, cast around a tubular member of curvilinear configuration for accommodating a radiation source capsule. A lining for the tubular member, in the form of a close-coiled flexible guide, provides easy replaceability to counter wear while the container is in service. Container life is extended, and maintenance costs are reduced. (author)

Shielded container

International Nuclear Information System (INIS)

Fries, B.A.

1978-01-01

A shielded container for transportation of radioactive materials is disclosed in which leakage from the container is minimized due to constructional features including, inter alia, forming the container of a series of telescoping members having sliding fits between adjacent side walls and having at least two of the members including machine sealed lids and at least two of the elements including hand-tightenable caps

Human resource development strategies adopted by the Department of Atomic Energy, India

International Nuclear Information System (INIS)

Grover, R.B.

2007-01-01

In view of the knowledge intensive nature of the nuclear technology and the state of hi-tech industrial infrastructure in India, Bhabha Atomic Research Centre (BARC) has been designed to have a composite character. It is a large institution and has been pursuing activities starting from basic research to technology development. At BARC, we have also put in place a very effective human resource development programme and this programme is run by faculty drawn from within the organization. As a result, BARC has attributes of an institute, a research laboratory and also an industrial organization. The composite character is confined not only to BARC but also extends to the Department of Atomic Energy (DAE) as a whole. Simultaneous with research centres, we have been setting up industrial units. The fountainhead of success of the atomic energy programme in India is the fact that both the research centres, which generate knowledge and the industrial units, which generate wealth from the knowledge, are under one umbrella and that is the DAE working under the policy framework laid by the Atomic Energy Commission. The two sets of institutions maintain an organic linkage permitting seamless interaction and facilitating technology transfer without any cumbersome formalities. The common policy framework followed by all the institutions enables the department to follow an integrated approach towards human resource development and this further strengthens the linkages between the institutions. This has enabled the country to be self-reliant in all aspects of nuclear fuel cycle, starting with prospecting and mining of uranium and ending with the back-end of the fuel cycle, which involves reprocessing of the spent fuel and nuclear waste management. Most of the R and D work, which led to realization of this capability, was done or initiated at BARC at Trombay. Some of the activities have now been taken over by other research centers: IGCAR at Kalpakkam for fast reactors, Centre for

Progress report [of] Technical Physics and Prototype Engineering Division, April 1982 - March 1984

International Nuclear Information System (INIS)

Ramamurthi, S.S.; Chaudhry, Ramesh

1985-01-01

The work done by the Technical Physics and Prototype Engineering Division of the Bhabha Atomic Research Centre (BARC) at Bombay during the period from April 1982 to March 1984 is described in the form of summaries. The main thrust of the work of the Division is towards designing, developing, fabricating and if needed, producing on a large scale various instruments, equipment and components required for the programmes of the BARC and the Department of Atomic Energy. The summaries describing the work are grouped under the headings:(1) vacuum, (2) surface analysis, (3) mass spectrometry, (4) electronics, (5) cryogenics, (6) crystals and detectors, (7) glass technology and devices, and (8) optoelectronics. A list of publications of the staff-members of the Division during the report period is given. (M.G.B.)

A new data acquisition system for pelletron-LINAC experiments

International Nuclear Information System (INIS)

Ramachandran, K.; Chatterjee, A.; Singh, Sudheer; Jha, K.; Joy, Saju; Behere, A.; Goadgoankar, M.D.

2007-01-01

The LINAC booster facility coupled with Pelletron accelerator at Mumbai and the plans to have large detector arrays such as Indian National Gamma Array, Charged Particle Array, Neutron Array, BaF 2 etc. pose new challenges to have a Data Acquisition system (DAQ) with a throughput an order of magnitude higher than the present CAMAC system. The major limitation of CAMAC readout is the 1μs/word readout time. A new FERA (Fast Encoding and Readout) data acquisition system developed at BARC for the augmentation of the throughput of CAMAC is a readout bus for the CAMAC ADCs. With this FERA DAQ, it is possible to readout CAMAC ADC's at 150 ns/word. This talk will present the new DAQ system used at BARC-TIFR Pelletron Accelerator facility. (author)

Parametric thermal analysis of 75 MHz heavy ion RFQ

International Nuclear Information System (INIS)

Mishra, N.K.; Mehrotra, N.; Verma, V.; Gupta, A.K.; Bhagwat, P.V.

2015-01-01

An ECR based Heavy Ion Accelerator comprising of a superconducting Electron Cyclotron Resonance (ECR) Ion Source, normal conducting RFQ (Radio Frequency Quadrupole) and superconducting Niobium resonators is being developed at BARC under XII plan. A state-of-the-art 18 GHz superconducting ECR ion source (PK-ISIS) jointly configured with Pantechnik, France is operational at Van-de-Graaff, BARC. The electromagnetic design of the improved version of 75 MHz heavy ion RFQ has been reported earlier. The previous thermal study of 51 cm RFQ model showed large temperature variation axially along the vane tip. A new coolant flow scheme has been worked out to optimize the axial temperature gradient. In this paper the thermal analysis including parametric study of coolant flow rates and inlet temperature variation will be presented. (author)

Generation of aerosols: BARC nebulizer and others

International Nuclear Information System (INIS)

Soni, P.S.; Raghunath, B.

1994-01-01

The concern with atmospheric pollution in recent times has focused attention on aerosols, their distribution pattern after inhalation and the kinetics of their deposition and exclusion from bronchial passages. The technique of radioaerosols for lung imaging is of recent origin. The procedure was proposed as a means of estimating regional ventilation and localizing areas of airway narrowing. The technique is an alternative in the face of non-availability of radioactive gases, especially in developing countries where the cost is the major factor due to economic reasons. Now, it is beyond doubt that radioaerosol lung studies are a potentially valuable tool in the evaluation of respiratory function in health and disease, especially to detect chronic obstructive pulmonary diseases. Also, the administration of a drug by aerosol inhalation provides a convenient method for the treatment of conditions affecting the respiratory system. This write-up will brief us about radioaerosol, its generation and characterisation

Generation of aerosols: BARC nebulizer and others

Energy Technology Data Exchange (ETDEWEB)

Soni, P S; Raghunath, B

1994-07-01

The concern with atmospheric pollution in recent times has focused attention on aerosols, their distribution pattern after inhalation and the kinetics of their deposition and exclusion from bronchial passages. The technique of radioaerosols for lung imaging is of recent origin. The procedure was proposed as a means of estimating regional ventilation and localizing areas of airway narrowing. The technique is an alternative in the face of non-availability of radioactive gases, especially in developing countries where the cost is the major factor due to economic reasons. Now, it is beyond doubt that radioaerosol lung studies are a potentially valuable tool in the evaluation of respiratory function in health and disease, especially to detect chronic obstructive pulmonary diseases. Also, the administration of a drug by aerosol inhalation provides a convenient method for the treatment of conditions affecting the respiratory system. This write-up will brief us about radioaerosol, its generation and characterisation.

BARC's efforts towards maintenance of water quality

International Nuclear Information System (INIS)

Kamath, P.R.

1978-01-01

Some of the studies pursued at the Environmental Survey Laboratories (ESLs) established at the site of nuclear installations in India are discussed. Each site has its special features and these ESLs monitor radioactive pollution in the environment including Man. The major objective of the surveillance programme at nuclear sites is the maintenance of water quality. Environmental investigations carried out to collect data on individual organisms, recipient water characteristics, thermal pollution and its effect on fish are described. (K.M.)

49 CFR 173.189 - Batteries containing sodium or cells containing sodium.

Science.gov (United States)

2010-10-01

... 49 Transportation 2 2010-10-01 2010-10-01 false Batteries containing sodium or cells containing sodium. 173.189 Section 173.189 Transportation Other Regulations Relating to Transportation PIPELINE AND... Than Class 1 and Class 7 § 173.189 Batteries containing sodium or cells containing sodium. (a...

Sadhana | Indian Academy of Sciences

Indian Academy of Sciences (India)

Numerical simulation with finite element and artificial neural network of ball ... The methodology evolved in this work can be extended to predict material properties ... Reactor Safety Division, Bhabha Atomic Research Centre (BARC), Trombay, ...

Passive containment system

International Nuclear Information System (INIS)

Kleimola, F.W.

1977-01-01

Disclosed is a containment system that provides complete protection entirely by passive means for the loss of coolant accident in a nuclear power plant and wherein all stored energy released in the coolant blowdown is contained and absorbed while the nuclear fuel is prevented from over-heating by a high containment back-pressure and a reactor vessel refill system. The primary containment vessel is restored to a high sub-atmospheric pressure within a few minutes after accident initiation and the decay heat is safely transferred to the environment while radiolytic hydrogen is contained by passive means. 20 claims, 14 figures

High security container

International Nuclear Information System (INIS)

Moreau, P.J.-M.; Monsterleet, G.A.

1979-01-01

This invention concerns containments, vessels or tanks for containing and protecting products or installations of various kinds, to be called by the general denomination 'containers'. Such products can be, inter alia, liquids such as natural gas, ammonia, vinyle chloride and hydrocarbons. Far from just forming simple means of storage, the containers used for this must now be capable of withstanding fire, sabotage for instance rocket fire, even impacts from aircraft, earthquakes and other aggressions of the same kind. The particular object of this invention is to create a container withstanding all these various agressions. It must also be considered that this container can not only be used for storing products or materials but also for enclosing particularly dangerous or delicate installations, such as nuclear or chemical reactors [fr

Product development of Indian cargo scanner

International Nuclear Information System (INIS)

2017-01-01

A cargo scanner is required for nonintrusive screening of suspected cargo containers in trade, using high energy X-ray, to detect any mis-declarations, contraband goods concealment or hidden ammunition or explosives. The cargo scanners help authorities to process large number of suspected cargo with a high level of confidence with other additional benefit of faster clearance, minimised intrusive inspection and generating secured digital record of the process. BARC is in process of developing Indian Cargo Scanner with indigenous X-ray source. Proof of concept and conformance of the results to the international standards has been demonstrated in laboratory. Full scale equipment named as Portal scanner shall be demonstrated at Gamma field Trombay in year 2017. Subsequently the technology transfer may be done to a suitable Indian vendor

Bhabha Atomic Research Centre annual report : 1989

International Nuclear Information System (INIS)

1991-01-01

The main thrust of the various research and development (R and D) activities of the Bhabha Atomic Research Centre (BARC), Bombay, is towards the implementation of India's nuclear power programme. To that end, its R and D activities cover the entire nuclear fuel cycle, reactor technology; applications of radioisotopes and radiations in agriculture, medicine and industries; and radiation protection in nuclear installations. The report presents in summarised form the R and D activities carried out during 1989 in the chapters entitled: Physical Sciences, Chemical Sciences, Materials and Materials Sciences, Radioisotopes, Reactors, Fuel Cycle, Radiological Safety and Protection, Electronics and Instrumentation, Engineering Services, Life Sciences and General. At the end of each chapter, a list of publications by the staff scientists in the corresponding subject field is given. The list includes published journal articles and technical reports, and papers presented at conferences, symposia etc. The report also covers the R and D activities of the outstation units of BARC, namely, Nuclear Research Laboratory, Srinagar; High Altitude Research Laboratory, Gulmarg; and Variable Energy Cyclotron Centre, Calcutta. BARC is also engaged in basic an applied research in frontier areas of science such as plasma and fusion physics, accelerators and lasers, high temperature superconductivity, condensed matter physics, high pressure physics, high resolution spectroscopy, chemical reaction dynamics and laser induced chemistry, electronics and robotics: radiation biology, and genetic engineering. Report is illustrated with a number of figures, graphs, and coloured pictures. (M.G.B.) figs., refs

Sulfur-Containing Agrochemicals.

Science.gov (United States)

Devendar, Ponnam; Yang, Guang-Fu

2017-10-09

Modern agricultural chemistry has to support farmers by providing innovative agrochemicals. In this context, the introduction of sulfur atoms into an active ingredient is still an important tool in modulating the properties of new crop-protection compounds. More than 30% of today's agrochemicals contain at least one sulfur atom, mainly in fungicides, herbicides and insecticides. A number of recently developed sulfur-containing agrochemical candidates represent a novel class of chemical compounds with new modes of action, so we intend to highlight the emerging interest in commercially active sulfur-containing compounds. This chapter gives a comprehensive overview of selected leading sulfur-containing pesticidal chemical families namely: sulfonylureas, sulfonamides, sulfur-containing heterocyclics, thioureas, sulfides, sulfones, sulfoxides and sulfoximines. Also, the most suitable large-scale synthetic methods of the recently launched or provisionally approved sulfur-containing agrochemicals from respective chemical families have been highlighted.

The accidental astronomer

Indian Academy of Sciences (India)

Lawrence

Research Centre (BARC), Tata Institute of Fundamental Research ... to make my Ph.D. a stressful, lengthy process, but I persisted and ... An American graduate student, as- ... prospects of getting a job in Bhubaneswar or its vicinity, as as-.

Development of neutron detectors and neutron radiography at ...

Indian Academy of Sciences (India)

BARC, Department of Atomic Energy units and some universities and research institutes in India and .... by Solid State Physics Division for various applications, using the 400 kW swim- ming pool type reactor, Apsara as the neutron source.

Containment performance improvement program

International Nuclear Information System (INIS)

Beckner, W.; Mitchell, J.; Soffer, L.; Chow, E.; Lane, J.; Ridgely, J.

1990-01-01

The Containment Performance Improvement (CPI) program has been one of the main elements in the US Nuclear Regulatory Commission's (NRC's) integrated approach to closure of severe accident issues for US nuclear power plants. During the course of the program, results from various probabilistic risk assessment (PRA) studies and from severe accident research programs for the five US containment types have been examined to identify significant containment challenges and to evaluate potential improvements. The five containment types considered are: the boiling water reactor (BMR) Mark I containment, the BWR Mark II containment, the BWR Mark III containment, the pressurized water reactor (PWR) ice condenser containment, and the PWR dry containments (including both subatmospheric and large subtypes). The focus of the CPI program has been containment performance and accident mitigation, however, insights are also being obtained in the areas of accident prevention and accident management

Traceable calibration of hospital 192Ir HDR sources

International Nuclear Information System (INIS)

Govinda Rajan, K.N.; Sharma, S.D.; Palaniselvam, T.; Vandana, S.; Bhatt, B.C.; Vinatha, S.; Patki, V.S.; Pendse, A.M.; Kannan, V.

2004-01-01

A HDR 1000 PLUS well type ionization chamber, procured from Standard Imaging, USA, and maintained by medical Physics and Safety Section (MPSS), Bhabha Atomic Research Centre (BARC), India, as a reference well chamber 1 (RWCH1), was traceably calibrated against the primary standard established by Radiological Standards Laboratory (RSL), BARC for 192 Ir HDR source, in terms of air kerma strength (AKS). An indigenously developed well-type ionization chamber, reference well chamber 2 (RWCH2) and electrometer system, fabricated by CD High Tech (CDHT) Instruments Private Ltd., Bangalore, India, was in turn calibrated against RWCH1. The CDHT system (i.e. RWCH2 and CDHT electrometer system) was taken to several hospitals, in different regions of the country, to check the calibration status of 192 Ir HDR sources. The result of this calibration audit work is reported here. (author)

Bhabha Atomic Research Centre : annual report 1990

International Nuclear Information System (INIS)

1992-01-01

Research and development (R and D) activities of the Bhabha Atomic Research Centre (BARC) carried out during 1990 are reported. The main thrust of the R and D activities of BARC is on : (1)providing support to the nuclear power programme, (2)designing, building and utilising research reactors, (3)working in related frontline technologies, and also (4)basic research in frontier areas of science. These activities are described in brief under the chapters entitled : (1)Physical Sciences (2)Chemical Sciences (3)Materials and Material Science (4)Radioisotopes (5)Reactions (6)Fuel Cycle (7)Radiological Safety and Protection (8)Electronics and Instrumentation (9)Engineering Services (10)Life Sciences and (11)General. At the end of each chapter a list of papers and reports published in the subject field indicated by the title of the chapter is given. (N.B.). figs., tabs

Feasibility studies to assess the use of 236Pu as a radiochemical yield monitor in bioassay samples

International Nuclear Information System (INIS)

Sawant, P.D.; Kalsi, P.C.

2007-01-01

Various plutonium compounds are handled in nuclear facilities of BARC. Hence, there is a possibility of occupational workers getting exposed to Pu. In vitro bioassay monitoring in which Pu is separated by chemical procedures from excreta samples and estimated by alpha-spectrometry, is the method of choice for the evaluation of internal dose to the occupational workers handling Pu. However, this method requires a suitable Pu tracer for reducing the uncertainties due to chemical yield in the separation, electro-deposition and counting efficiency. 242 Pu is commonly used as a tracer but due to its non-availability, efforts were made earlier to indigenously synthesis 236 Pu by proton irradiation of 237 Np in BARC-TIFR pelletron facility. The present study, reports the feasibility of using 236 Pu as a radiochemical yield monitor (tracer) in bioassay samples. (author)

Pre-criticality testing of radiation monitors associated with protective and regulatory channels of PHWRs and related work

International Nuclear Information System (INIS)

Tripathi, S.M.; Rao, Suresh; Mahant, A.K.; Sathian, V.; Ghodke, Shobha; Satam, R.A.; Singh, Yashoda; Phadnis, U.V.; Shaha, V.V.

2006-01-01

The paper describes the various experiments that are regularly carried out for each PHWR since RAPS-2. The work involves performance evaluation of start-up counters and ion chambers used in Protective and Regulatory channels and start-up counters used both in-core and out of core. In addition, Radiation Safety Systems Division (RSSD) also carries out calibration of Delayed Neutron Monitors (DNM) and Self Powered Neutron Detectors (SPND). Except SPND, all other detectors are tested not only at BARC but also at reactor sites prior to initial flushing of heavy water, using the actual circuitry and control instruments at site. The performance evaluation of SPNDs is carried out at A-1 location of APSARA reactor core. Apart from these, RSSD also carries out calibration of zonal classification monitors and health physics related radiation monitors at BARC. (author)

Reactor container

International Nuclear Information System (INIS)

Kojima, Yoshihiro; Hosomi, Kenji; Otonari, Jun-ichiro.

1997-01-01

In the present invention, a catalyst for oxidizing hydrogen to be disposed in a reactor container upon rupture of pipelines of a reactor primary coolant system is prevented from deposition of water droplets formed from a reactor container spray to suppress elevation of hydrogen concentration in the reactor container. Namely, a catalytic combustion gas concentration control system comprises a catalyst for oxidizing hydrogen and a support thereof. In addition, there is also disposed a water droplet deposition-preventing means for preventing deposition of water droplets in a reactor pressure vessel on the catalyst. Then, the effect of the catalyst upon catalytic oxidation reaction of hydrogen can be kept high. The local elevation of hydrogen concentration can be prevented even upon occurrence of such a phenomenon that various kinds of mobile forces in the container such as dry well cooling system are lost. (I.S.)

Nuclear reactor container

International Nuclear Information System (INIS)

Yamaki, Rika; Kawabe, Ryuhei.

1989-01-01

A venturi scrubber is connected to a nuclear reactor container. Gases containing radioactive aerosols in the container are introduced into the venturi scrubber in the form of a high speed stream under the pressure of the container. The radioactive aerosols are captured by inertia collision due to the velocity difference between the high speed gas stream and water droplets. In the case of the present invention, since the high pressure of the reactor container generated upon accident is utilized, compressor, etc. is no more required, thereby enabling to reduce the size of the aerosol removing device. Further, since no external power is used, the radioactive aerosols can be removed with no starting failure upon accidents. (T.M.)

Sharps container

Science.gov (United States)

Lee, Angelene M. (Inventor)

1992-01-01

This invention relates to a system for use in disposing of potentially hazardous items and more particularly a Sharps receptacle for used hypodermic needles and the like. A Sharps container is constructed from lightweight alodined nonmagnetic metal material with a cup member having an elongated tapered shape and length greater than its transverse dimensions. A magnet in the cup member provides for metal retention in the container. A nonmagnetic lid member has an opening and spring biased closure flap member. The flap member is constructed from stainless steel. A Velcro patch on the container permits selective attachment at desired locations.

Integrated severe accident containment analysis with the CONTAIN computer code

International Nuclear Information System (INIS)

Bergeron, K.D.; Williams, D.C.; Rexroth, P.E.; Tills, J.L.

1985-12-01

Analysis of physical and radiological conditions iunside the containment building during a severe (core-melt) nuclear reactor accident requires quantitative evaluation of numerous highly disparate yet coupled phenomenologies. These include two-phase thermodynamics and thermal-hydraulics, aerosol physics, fission product phenomena, core-concrete interactions, the formation and combustion of flammable gases, and performance of engineered safety features. In the past, this complexity has meant that a complete containment analysis would require application of suites of separate computer codes each of which would treat only a narrower subset of these phenomena, e.g., a thermal-hydraulics code, an aerosol code, a core-concrete interaction code, etc. In this paper, we describe the development and some recent applications of the CONTAIN code, which offers an integrated treatment of the dominant containment phenomena and the interactions among them. We describe the results of a series of containment phenomenology studies, based upon realistic accident sequence analyses in actual plants. These calculations highlight various phenomenological effects that have potentially important implications for source term and/or containment loading issues, and which are difficult or impossible to treat using a less integrated code suite

Journal of Genetics | Indian Academy of Sciences

Indian Academy of Sciences (India)

Partial sequence analysis and expression patterns of some of these random cDNA ... Department of Microbiology and Cell Biology, Indian Institute of Science, ... BC V6T124, Canada; USDA Vegetable Lab, Building 010A, ARS/PSI/BARC- ...

Fulltext PDF

Indian Academy of Sciences (India)

Foreword. Drs M Ramanadham, V C Rakhecha, R Mukhopadhyay, S Basu and V K Aswal. I also thank BRNS for the financial support. V C Sahni. Director, Physics Group, BARC, Mumbai and. Director, Centre for Advanced Technology, Indore. 2.

Reactor container structure

International Nuclear Information System (INIS)

Sato, Yoshimi; Fukuda, Yoshio.

1993-01-01

A main container of an FBR type reactor using liquid sodium as coolants is attached to a roof slug. The main container contains, as coolants, lower temperature sodium, and high temperature sodium above a reactor core and a partitioning plate. The main container has a structure comprising only longitudinal welded joints in parallel with axial direction in the vicinity of the liquid surface of high temperature sodium where a temperature gradient is steep and great thermal stresses are caused without disposing lateral welded joints in perpendicular to axial direction. Only the longitudinal welded joints having a great fatigue strength are thus disposed in the vicinity of the liquid surface of the high temperature sodium where axial thermal stresses are caused. This can improve reliability of strength at the welded portions of the main container against repeating thermal stresses caused in vicinity of the liquid surface of the main container from a view point of welding method. (I.N.)

High integrity container evaluation for solid waste disposal burial containers

International Nuclear Information System (INIS)

Josephson, W.S.

1996-01-01

In order to provide radioactive waste disposal practices with the greatest measure of public protection, Solid Waste Disposal (SWD) adopted the Nuclear Regulatory Commission (NRC) requirement to stabilize high specific activity radioactive waste prior to disposal. Under NRC guidelines, stability may be provided by several mechanisms, one of which is by placing the waste in a high integrity container (HIC). During the implementation process, SWD found that commercially-available HICs could not accommodate the varied nature of weapons complex waste, and in response developed a number of disposal containers to function as HICs. This document summarizes the evaluation of various containers that can be used for the disposal of Category 3 waste in the Low Level Burial Grounds. These containers include the VECTRA reinforced concrete HIC, reinforced concrete culvert, and the reinforced concrete vault. This evaluation provides justification for the use of these containers and identifies the conditions for use of each

Development of human resources for Indian nuclear power ...

Indian Academy of Sciences (India)

issues arising out of radiation and nuclear safety, physical protection of nuclear ..... The course work is offered at all campuses of BARC Training School and ..... exposes the students to R&D environment, but also motivates them to take up a ...

Possible heavy tetraquarks qQq-barQ-bar, qqQ-barQ-bar and qQQ-barQ-bar

International Nuclear Information System (INIS)

Cui Ying; Chen Xiaolin; Deng Weizhen; Zhu Shilin

2007-01-01

Assuming X(3872) is a qcq-barc-bar tetraquark and using its mass as input, the authors perform a schematic study of the masses of possible heavy tetraquarks using the color-magnetic interaction with the flavor symmetry breaking corrections. (authors)

A single crystal neutron diffraction study on mixed crystal (K)0.25 ...

Indian Academy of Sciences (India)

2018-02-02

Feb 2, 2018 ... Author for correspondence (rajul@barc.gov.in). MS received 16 ... very long time, no general theoretical model accounting for all the unique ..... depending on the π-orbital contribution to the P–O bond [18]. Ideal geometry for ...

Design studies of a high-current radiofrequency quadrupole for ...

Indian Academy of Sciences (India)

signed for the low-energy high-intensity proton accelerator (LEHIPA) project at BARC,. India. The beam ... In this generalized method, the focussing factor (B) and vane voltage ..... r0 and also power dissipation vary along the length of the RFQ.

Elastic scattering and fusion cross-sections in Li + Al reaction

Indian Academy of Sciences (India)

1Department of Physics, Faculty of Science, The M.S. University of Baroda,. Vadodara 390 .... ization and to check the left–right beam wandering if any. ..... The authors would like to thank FOTIA staff at BARC for their cooperation during the.

Alternative containers for low-level wastes containing large amounts of tritium

International Nuclear Information System (INIS)

Gause, E.P.; Lee, B.S.; MacKenzie, D.R.; Wiswall, R. Jr.

1984-11-01

High-activity tritiated waste generated in the United States is mainly composed of tritium gas and tritium-contaminated organic solvents sorbed onto Speedi-Dri which are packaged in small glass bulbs. Low-activity waste consists of solidified and adsorbed liquids. In this report, current packages for high-activity gaseous and low-activity adsorbed liquid wastes are emphasized with regard to containment potential. Containers for low-level radioactive waste containing large amounts of tritium need to be developed. An integrity may be threatened by: physical degradation due to soil corrosion, gas pressure build-up (due to radiolysis and/or biodegradation), rapid permeation of tritium through the container, and corrosion from container contents. Literature available on these points is summarized in this report. 136 references, 20 figures, 40 tables

PIC-container for containment and disposal of low and intermediate level radioactive wastes

International Nuclear Information System (INIS)

Araki, Kunio; Shinji, Yoshimasa; Maki, Yasuro; Ishizaki, Kanjiro; Minegishi, Keiichi; Sudoh, Giichi.

1981-03-01

Steel fiber reinforced polymer-impregnated concrete (SFPIC) has been investigated for low and intermediate level radioactive waste containers. The present study has been carried out by the following stages. A) Preliminary evaluation: 60 L size container for cold and hot tests. B) Evaluation of size effect: 200 L size container for cold tests. The 60 L and 200 L containers were designed as pressure-container (without equalizer) for 500 kg/cm 2 and 700 kg/cm 2 . Polymerization of impregnated methylmethacrylate monomer for stage-A and B were performed by 60 Co-γ ray radiation and thermal catalytic polymerization, respectively. Under the loading of 500 kg/cm 2 and 700 kg/cm 2 -outside hydraulic pressure, these containers were kept in their good condition. The observed maximum strains were about 1380 x 10 -6 and 3950 x 10 -6 at the outside central position of container body for circumferential direction of the 60 L and 200 L container, respectively. An accelerated leaching test was performed by charging the concentrate of the liquid radioactive waste from JMTR in JAERI into the container. Although they were immersed in deionized water for 400 days, nuclides were not leached from the container. From results of various tests, it was evaluated that the SFPIC-container was suitable for containment and disposal of low and intermediate level radioactive wastes. There was not any great difference between the two size containers for the physical and chemical properties except in their preparation process. (author)

Status of the CONTAIN computer code for LWR containment analysis

International Nuclear Information System (INIS)

Bergeron, K.D.; Murata, K.K.; Rexroth, P.E.; Clauser, M.J.; Senglaub, M.E.; Sciacca, F.W.; Trebilcock, W.

1983-01-01

The current status of the CONTAIN code for LWR safety analysis is reviewed. Three example calculations are discussed as illustrations of the code's capabilities: (1) a demonstration of the spray model in a realistic PWR problem, and a comparison with CONTEMPT results; (2) a comparison of CONTAIN results for a major aerosol experiment against experimental results and predictions of the HAARM aerosol code; and (3) an LWR sample problem, involving a TMLB' sequence for the Zion reactor containment

Status of the CONTAIN computer code for LWR containment analysis

International Nuclear Information System (INIS)

Bergeron, K.D.; Murata, K.K.; Rexroth, P.E.; Clauser, M.J.; Senglaub, M.E.; Sciacca, F.W.; Trebilcock, W.

1982-01-01

The current status of the CONTAIN code for LWR safety analysis is reviewed. Three example calculations are discussed as illustrations of the code's capabilities: (1) a demonstration of the spray model in a realistic PWR problem, and a comparison with CONTEMPT results; (2) a comparison of CONTAIN results for a major aerosol experiment against experimental results and predictions of the HAARM aerosol code; and (3) an LWR sample problem, involving a TMLB' sequence for the Zion reactor containment

Facilities Enhancement for IPY at Barrow

Science.gov (United States)

Sheehan, G.; Brown, J.; Coakley, B.; Zak, B.

2007-12-01

In connection with the International Polar Year, research facilities at Barrow have been markedly enhanced. On June 1st, Sen. Ted Stevens cut the ribbon at the Grand Opening of the Barrow Arctic Research Center (BARC). The BARC currently covers 18,000 sq. ft, with future phases anticipated, including 8 research labs, a necropsy lab for animal studies, freezers for biological samples, a state-of-the-art-data system, a planned Internet II connection, meeting spaces, and offices. There is a platform on the roof of the facility for instrumentation, and a communications tower to provide WIFI connections to remote instrumentation located on the adjacent Barrow Environmental Observatory (BEO). The BEO, which consists of 11 square miles of tundra and coastline set aside for environmental and ecological research, has also seen recent enhancements. A power line and a hard- surfaced trail now provide easy access to the interior of the BEO. Users of the BEO (and others) also have access to many different data sets continuously collected at the NOAA Global Monitoring Division Barrow Station and the DOE ARM (Atmospheric Radiation Measurement) Climate Research Facility (see http://www.esrl.noaa.gov/gmd/obop/brw.html and http://www.arm.gov/sites/nsa.stm respectively) also adjacent to the BEO. The National Weather Service Barrow Station also provides data of interest. Researchers submitting proposals to the National Science Foundation can include a request for the use of BARC and BEO facilities in their proposals. ARM facilities, recently augmented, can also be made available, but through arrangements made directly with ARM (BDZak@sandia.gov; 505-845-8631 or MDIvey@sandia.gov; 505-284-9092). BARC, BEO and ARM facilities are available to other agency and international users as well. For more information, see http://www.arcticscience.org, or contact Glenn Sheehan (907-852-4881, basc@arcticscience.org). The BEO consists of land owned by Ukpeagvik Inupiat Corporation, which is owned by

Cavity ring-down technique for measurement of reflectivity of high ...

Indian Academy of Sciences (India)

Laser & Plasma Technology Division, Bhabha Atomic Research Centre, Mumbai 400 085,. India. *Corresponding author. E-mail: gsridhar@barc.gov.in. Abstract. A simple, accurate and reliable method for measuring the reflectivity of laser- ... Keywords. Cavity ring-down method; reflectivity measurement; optical resonator.

Numerical simulation with finite element and artificial neural network ...

Indian Academy of Sciences (India)

Reactor Safety Division, Bhabha Atomic Research Centre (BARC), Trombay, ... their evaluated property is verified with experimental tensile specimen results. An ... tensile strength, strength coefficient, true stress–true strain curves and strain ... Haggag & Nansted (1989) also described a simple technique for estimating the ...

7 CFR 502.9 - Soliciting, vending, debt collection, and distribution of handbills.

Science.gov (United States)

2010-01-01

...) AGRICULTURAL RESEARCH SERVICE, DEPARTMENT OF AGRICULTURE CONDUCT ON BELTSVILLE AGRICULTURE RESEARCH CENTER... display or distribution of commercial advertising, or the collecting of private debts, in or on BARC..., health, and other purposes sponsored or approved by the Agricultural Research Service, concessions, or...

RESONANCEIJU-IY

Indian Academy of Sciences (India)

Development of superconductor based magnets, liquid crystals, linear accelerators for medical and other applications, low temperature physics, memory alloys, biotechnology, development of new radiopharmaceuticals etc. are some of the fields in which BARC scientists work. Computers are essential for any scientific work ...

Apparatus for the storage of transport- and storage-containers containing radioactive fuel elements

International Nuclear Information System (INIS)

Vox, A.

1983-01-01

The invention concerns an apparatus for the storage of transport and storage containers containing radioactive fuel elements. For each transport or storage container there is a separate silo-type container of steel, concrete, prestressed concrete or suchlike breakproof and fireproof material, to be placed in the open, that can be opened for removal and placing of the transport or storage container respectively. (orig.) [de

Nuclear reactor containment device

International Nuclear Information System (INIS)

Ichiki, Tadaharu.

1980-01-01

Purpose: To reduce the volume of a containment shell and decrease the size of a containment equipment for BWR type reactors by connecting the containment shell and a suppression pool with slanted vent tubes to thereby shorten the vent tubes. Constitution: A pressure vessel containing a reactor core is installed at the center of a building and a containment vessel for the nuclear reactor that contains the pressure vessel forms a cabin. To a building situated below the containment shell, is provided a suppression chamber in which cooling water is charged to form a suppression pool. The suppression pool is communicated with vent tubes that pass through the partition wall of the containment vessel. The vent tubes are slanted and their lower openings are immersed in coolants. Therefore, if accident is resulted and fluid at high temperature and high pressure is jetted from the pressure vessel, the jetting fluid is injected and condensated in the cooling water. (Moriyama, K.)

The impact of BWR MK I primary containment failure dynamics on secondary containment integrity

International Nuclear Information System (INIS)

Greene, S.R.

1987-01-01

During the past four years, the ORNL BWRSAT Program has developed a series of increasingly sophisticated BWR secondary containment models. These models have been applied in a variety of studies to evaluate the severe accident mitigation capability of BWR secondary containments. This paper describes the results of a recent ORNL study of the impact of BWR MK I primary containment failure dynamics on secondary containment integrity. A 26-cell MELCOR Browns Ferry secondary containment model is described and the predicted thermodynamic response of the secondary containment to a variety of postulated primary containment failure modes is presented. The effects of primary containment failure location, timing, and ultimate hole size on secondary containment response is investigated, and the potential impact of hydrogen deflagrations on secondary containment integrity is explored

Radiological containment handbook

International Nuclear Information System (INIS)

1982-10-01

The purpose of this NUREG is to be used as a reference text. It is meant to be used by the working personnel as a guide for using temporary radiological containments. The installing group and health physics group may vary among organizations but responsibilities and duties will not change. It covers installation and inspection containments; working and operating guidelines; operating requirement; emergency procedures; and removal of containments

FAUST/CONTAIN

International Nuclear Information System (INIS)

Cherdron, W.; Minges, J.; Sauter, H.; Schuetz, W.

1995-01-01

The FAUNA facility has been restructured after completion of the sodium fire experiments. It is now serving LWR research, cf. report II on program no. 32.21.02 concerning steam explosions. The CONTAIN code system for computing the thermodynamic, aerosol and radiological phenomena in a containment under severe accident conditions is being developed with a new to fission product release and transport. (orig.)

Radiation technology in agriculture

International Nuclear Information System (INIS)

D'Souza, S.F.

2013-01-01

The Department of Atomic Energy through its research, development and deployment activities in nuclear science and technology, has been contributing towards enhancing the production of agricultural commodities and their preservation. Radiations and radioisotopes are used in agricultural research to induce genetic variability in crop plants to develop improved varieties, to manage insect pests, monitor fate and persistence of pesticides, to study fertilizer use efficiency and plant micronutrient uptake and also to preserve agricultural produce. Use of radiation and radioisotopes in agriculture which is often referred to as nuclear agriculture is one of the important fields of peaceful applications of atomic energy for societal benefit and BARC has contributed significantly in this area. 41 new crop varieties developed at BARC have been released and Gazette notified by the MoA, GOI for commercial cultivation and are popular among the farming community and grown through out the country

Development of triple axis neutron spectrometer (Paper No. 24)

International Nuclear Information System (INIS)

Pal, B.C.; Wadhwa, N.R.; Goveas, S.H.

1987-02-01

The triple axis neutron spectrometers are the basic instruments intended for use with neutron beams from reactors. Various types of spectrometers, each devoted to different kinds of measurement can be designed and manufactured, once a prototype having all the attributes of a versatile instrument is designed and developed. With the view to achieving self reliance in this field, Central Workshops of Bhabha Atomic Research Centre (BARC), Bombay designed and developed a prototype of triple axis spectrometer meeting the specifications prepared by Nuclear Physics Division of BARC . This spectrometer, with a moving wedge system was successfully manufactured and installed at 'DHRUVA'. Another version of this spectrometer, called the 'Polarised Neutron Spectrometer' was also built and exported to South Korea and installed at Korea Advanced Energy Research Institute, Seoul. This paper deals with basic concept, development of design, engineering of mechanical assemblies, the manufacturing approach and problems encountered during manufacture. (author). 3 figs

Performance analysis of indigenous spectroscopy system based on Lanthanum Bromide (LaBr3(Ce)) scintillation detector

International Nuclear Information System (INIS)

Kulkarni, C.P.; Punnal, Mahesh; Vinod, M.; Padmini, S.; Bhatnagar, P.V.; Behere, Anita; Kulkarni, D.B.; Paranjape, D.B.

2018-01-01

This paper presents detailed performance analysis of LaBr 3 (Ce) based compact spectroscopy system indigenously developed in Electronics Division BARC. The system incorporates state of the art low power electronic components along-with advanced spectroscopy software. Performance parameters and spectral response are experimentally determined and the results are presented in comparison with a standard HPGe system under similar test conditions. These experiments are conducted in Radiation Standards Section, RSSD in BARC using calibration sources for acquiring gamma spectrums in various combinations of source-to-detector (S-D) distances and acquisition times. The acquired data is used for deriving energy calibration and computing FWHM, dead time, count-rate (cps) and efficiency to evaluate system performance; particularly with smaller acquisition times as necessitated by field applications. Self activity of the detector is also determined experimentally and presented along-with comments on its effect on low count-rate applications

Research and development activities of the Seismology Section for the period January 1982-December 1983

International Nuclear Information System (INIS)

Roy, Falguni

1984-01-01

The research and development activities of the Seismology Section of the Bhabha Atomic Research Centre (BARC) at Bombay are reported for the period January 1982-December 1983 in the form of summaries. The Section's activities are mainly directed towards detection of underground nuclear explosions. During the report period 64 signals out of about 12000 seismograms which were examined were identified as the signals due to underground nuclear explosions. The instrumentation work for Kolar rockburst research was almost completed under the collaboration programme of BARC with Bharat Gold Mines Ltd. Analytical methods have been developed for interpreting the frequency-magnitude relation of earthquake. These methods will be useful in the seismic estimation of risk in case only restricted data involving events of low magnitude are available. A list of publications of the staff-members of the Section during the report period is given. (M.G.B.)

Water Chemistry Section: progress report (1981-82)

International Nuclear Information System (INIS)

Dharwadkar, S.R.; Ramshesh, V.

1983-01-01

The activities of the Water Chemistry Section of the Bhabha Atomic Research Centre (BARC), Bombay, during the years 1981 and 1982 are reported in the form of individual summaries. The research activities of the Section cover the following areas: (1) chemistry and thermodynamics of nuclear materials, (2) crystal structure of organo-metallic complexes using X-ray diffraction, (3) thermophysical and phase transition studies, (4) solid state chemistry and thermochemical studies, (5) water and steam chemistry of heavy water plants and phwr type reactors, and (6) uranium isotope exchange studies. A survey is also given of: (i) the Section's participation in advisory and consultancy services in nuclear and thermal power stations, (ii) training activities, and (iii) assistance in chemical analysis by various techniques to other units of BARC and outside agencies. A list of publications and lectures by the staff during the report period is included. (M.G.B.)

Development of a high power electron beam welding gun with replaceable high voltage feed-through insulators

Energy Technology Data Exchange (ETDEWEB)

Saha, T.K; Mascarenhas, M.; Kandaswamy, E., E-mail: tanmay@barc.gov.in [Power Beam Equipment Design Section, Bhabha Atomic Research Centre, Mumbai (India)

2014-07-01

Ceramic to metal sealed feed-through insulators are commonly used in electron beam welding gun. The above feed-through insulators are susceptible to failure, as the brazing joints in them are not always very strong. Failure in one of these feed-through could render the complete gun unusable. This problem has already been faced in BARC, which led to the development of the electron gun with replaceable feed through insulators. A 24 kW Electron Beam Welding (EBW) gun with indigenous designed replaceable insulators is fabricated in BARC. Emphasis during the design of the gun had been to reduce the use of imported components to zero. This paper describes the design and fabrication of this gun and reports various simulations and tests performed. Beam trajectory of the gun is numerically computed and presented. Weld passes were carried out on stainless steel plates show satisfactory penetrations. (author)

Operating experience of upgraded radio frequency source at 76 MHz coupled to heavy ion RFQ

International Nuclear Information System (INIS)

Pande, Manjiri; Shiju, A.; Patel, N.R.; Shrotriya, S.D.; Bhagwat, P.V.

2015-01-01

A heavy ion radio frequency quadrupole (RFQ) accelerator has been developed at BARC (BARC). A RF source which was designed and developed at 76 MHz earlier, has been upgraded and coupled to heavy ion RFQ successfully. The DC bias supplies of this source have been replaced with new supplies having high efficiency and well filteration against RF interference (RFI). The driver of main power amplifier has been replaced with indigenously designed and developed unit. The earlier introduced microcontroller based interlock experienced RF noise issues. So, this circuit has been modified with the new circuit. With these modifications, the performance of the RF source was improved. Additionally, a separate low power RF source of around 100 + Watt was designed, developed and integrated with RFQ for its RF conditioning. This paper describes the details of up gradation of technologies implemented and coupling experience of this RF source with heavy ion RFQ. (author)

Reactor container cooling device

Energy Technology Data Exchange (ETDEWEB)

Ando, Koji; Kinoshita, Shoichiro

1995-11-10

The device of the present invention efficiently lowers pressure and temperature in a reactor container upon occurrence of a severe accident in a BWR-type reactor and can cool the inside of the container for a long period of time. That is, (1) pipelines on the side of an exhaustion tower of a filter portion in a filter bent device of the reactor container are in communication with pipelines on the side of a steam inlet of a static container cooling device by way of horizontal pipelines, (2) a back flow check valve is disposed to horizontal pipelines, (3) a steam discharge valve for a pressure vessel is disposed closer to the reactor container than the joint portion between the pipelines on the side of the steam inlet and the horizontal pipelines. Upon occurrence of a severe accident, when the pressure vessel should be ruptured and steams containing aerosol in the reactor core should be filled in the reactor container, the inlet valve of the static container cooling device is closed. Steams are flown into the filter bent device of the reactor container, where the aerosols can be removed. (I.S.).

The probability of containment failure by direct containment heating in Zion

International Nuclear Information System (INIS)

Pilch, M.M.; Yan, H.; Theofanous, T.G.

1994-12-01

This report is the first step in the resolution of the Direct Containment Heating (DCH) issue for the Zion Nuclear Power Plant using the Risk Oriented Accident Analysis Methodology (ROAAM). This report includes the definition of a probabilistic framework that decomposes the DCH problem into three probability density functions that reflect the most uncertain initial conditions (UO 2 mass, zirconium oxidation fraction, and steel mass). Uncertainties in the initial conditions are significant, but our quantification approach is based on establishing reasonable bounds that are not unnecessarily conservative. To this end, we also make use of the ROAAM ideas of enveloping scenarios and ''splintering.'' Two causal relations (CRs) are used in this framework: CR1 is a model that calculates the peak pressure in the containment as a function of the initial conditions, and CR2 is a model that returns the frequency of containment failure as a function of pressure within the containment. Uncertainty in CR1 is accounted for by the use of two independently developed phenomenological models, the Convection Limited Containment Heating (CLCH) model and the Two-Cell Equilibrium (TCE) model, and by probabilistically distributing the key parameter in both, which is the ratio of the melt entrainment time to the system blowdown time constant. The two phenomenological models have been compared with an extensive database including recent integral simulations at two different physical scales. The containment load distributions do not intersect the containment strength (fragility) curve in any significant way, resulting in containment failure probabilities less than 10 -3 for all scenarios considered. Sensitivity analyses did not show any areas of large sensitivity

Containment structure optimization

International Nuclear Information System (INIS)

Putman, S.; Walser, A.

1979-01-01

The major design features investigated are: dome shape, the prestress level provided to counteract accident pressure, the effect of diameter variation, and the design pressure used to size the containment. The optimum dome shape and optimum prestress level are used to investigate the effect of variations in diameter and design pressure on containment cost. The containment internal diameter is fixed at 150 feet for investigation of dome shape, prestress level and design prestress. A hemispherical dome containment with a prestress level of 1.25 P/sub a/ is recommended regardless of design pressure selected. A design pressure of 60 psi is recommended. No significant cost penalty is associated with diameter variation in the range of 145 to 155 feet

Lightweight flywheel containment

Science.gov (United States)

Smith, James R.

2004-06-29

A lightweight flywheel containment composed of a combination of layers of various material which absorb the energy of a flywheel structural failure. The various layers of material act as a vacuum barrier, momentum spreader, energy absorber, and reaction plate. The flywheel containment structure has been experimentally demonstrated to contain carbon fiber fragments with a velocity of 1,000 m/s and has an aerial density of less than 6.5 g/square centimeters. The flywheel containment, may for example, be composed of an inner high toughness structural layer, and energy absorbing layer, and an outer support layer. Optionally, a layer of impedance matching material may be utilized intermediate the flywheel rotor and the inner high toughness layer.

CONTAIN calculations; CONTAIN-Rechnungen

Energy Technology Data Exchange (ETDEWEB)

Scholtyssek, W.

1995-08-01

In the first phase of a benchmark comparison, the CONTAIN code was used to calculate an assumed EPR accident `medium-sized leak in the cold leg`, especially for the first two days after initiation of the accident. The results for global characteristics compare well with those of FIPLOC, MELCOR and WAVCO calculations, if the same materials data are used as input. However, significant differences show up for local quantities such as flows through leakages. (orig.)

Experimental and theoretical studies in Molten Salt Natural Circulation Loop (MSNCL)

International Nuclear Information System (INIS)

Srivastava, A.K.; Borgohain, A.; Jana, S.S.; Bagul, R.K.; Singh, R.R.; Maheshwari, N.K.; Belokar, D.G.; Vijayan, P.K.

2014-12-01

High Temperature Reactors (HTR) and solar thermal power plants use molten salt as a coolant, as it has low melting point and high boiling point, enabling us to operate the system at low pressure. Molten fluoride salt and molten nitrate salt are proposed as a candidate coolant for High Temperature Reactors (HTR) and solar power plant respectively. BARC is developing a 600 MWth pebble bed high temperature reactor, cooled by natural circulation of fluoride salt and capable of supplying process heat at 1000°C to facilitate hydrogen production by splitting water. Beside this, BARC is also developing a 2MWe solar power tower system using molten nitrate salt. With these requirements, a Molten Salt Natural Circulation Loop (MSNCL) has been designed, fabricated, installed and commissioned in Hall-7, BARC for thermal hydraulic, instrumentation development and material compatibility related studies. Steady state natural circulation experiments with molten nitrate salt (mixture of NaNO 3 and KNO 3 in 60:40 ratio) have been carried out in the loop at different power level. Various transients viz. startup of natural circulation, step power change, loss of heat sink and heater trip has also been studied in the loop. A well known steady state correlation given by Vijayan et. al. has been compared with experimental data. In-house developed code LeBENC has also been validated against all steady state and transient experimental results. The detailed description of MSNCL, steady state and transient experimental results and validation of in-house developed code LeBENC have been described in this report. (author)

Bhabha Atomic Research Centre: annual report 1988

International Nuclear Information System (INIS)

1989-12-01

The research and development (R and D) work carried out in the Bhabha Atomic Research Centre (BARC), Bombay during 1988 is summarised and presented in the sections entitled Physical Sciences, Chemical Sciences, Materials and Materials Science, Radioisotopes, Reactors, Fuel cycle, Radiological Safety and Protection, Electronics and Instrumentation, Engineering Services, Life Sciences and General. At the end of each section a list of publications is also given. The R and D work of the outstation units of BARC, namely, Nuclear Research Laboratory, Srinagar; High Altitute Research Laboratory, Gulmarg and Variable Energy Cyclotron Centre, Calcutta are also described in this report. Some of the highlights of the work during the year are: (1) Medium Energy Heavy Ion Accelerator (MEHIA) facility set up jointly by BARC and the Tata Institute of Fundamental Research (TIFR) at TIFR premises became fully operational in September 1988. A number of new compositions of high temperature supconducting materials were synthesized. The highest transition temperature achieved was 125 K. Research work to improve the quality of sintered uranium oxide pellets achieved the purpose. Nuclear fuels were fabricated by using sol-gel process. R and D work for 235 MWe and 500 MWe PHWR type reactors is continuing. Conceptual design of the fuel handling system for the prototype fast breeder reactor was finalised. 233 U+Al alloy fuel for Kamini reactor was fabricated. Progress has been made in industrial applications of enzymes. Various applications of radioisotopes are being continued. Certain technologies and processes developed in the Centre were transferred to commercial agencies for large scale exploitation. (M.G.B.)

Environmental gamma radiation levels around various DAE research centres

International Nuclear Information System (INIS)

Takale, R.A.; Swarnakar, M.; Shetty, P.G.; Sahu, S.K.; Pandit, G.G.

2014-01-01

This paper presents the gamma radiation levels of four research centres viz. Bhabha Atomic Research Centre (BARC), Trombay; Indira Gandhi Centre for Atomic Research (IGCAR), Kalpakkam; Variable Energy Cyclotron Centre (VECC), Kolkata; Raja Ramanna Centre for Advanced Technology (RRCAT), Indore; and an industry Board of Radiation and Isotope Technology (BRIT), Vashi. BARC is India's premier nuclear research facility and is a multi-disciplinary research centre with extensive infrastructure for advanced research and development (R and D). IGCAR, Kalpakkam is engaged in scientific research and advanced engineering programme towards the development of Fast Breeder Reactor technology. VECC Kolkata is dedicated to carry out frontier R and D in the fields of Accelerator Science and Technology, Nuclear Science (Theoretical and Experimental), and Material Science etc. RRCAT, Indore has rapidly grown into a premier institute for R and D in lasers, accelerators and their applications. BRIT, Vashi unit is involved in production, development, and supply of radioisotope based products and provision of isotope applications, radiation processing, radio analytical services etc. With an objective to keep a watch on the prevailing environmental background gamma radiation level around all the DAE installations, routine monitoring programme are being carried out using the Thermo Luminescent Dosimeters (TLDs). TLDs provide the simple, inexpensive and precise measurement of small, integrated, external gamma radiation dose rate. The general practice of this programme is to observe the outdoor gamma radiation levels. This paper summarizes the methodology and gamma radiation levels of four research centres viz. BARC, IGCAR, VECC, RRCAT and an industry BRIT, Vashi

Identification of unknown sample using NAA, EDXRF, XRD techniques

International Nuclear Information System (INIS)

Dalvi, Aditi A.; Swain, K.K.; Chavan, Trupti; Remya Devi, P.S.; Wagh, D.N.; Verma, R.

2015-01-01

Analytical Chemistry Division (ACD), Bhabha Atomic Research Centre (BARC) receives samples from law enforcement agencies such as Directorate of Revenue Intelligence, Customs for analysis. Five unknown grey powdered samples were received for identification and were suspected to be Iridium (Ir). Identification of unknown sample is always a challenging task and suitable analytical techniques have to be judiciously utilized for arriving at the conclusion. Qualitative analysis was carried out using Jordan Valley, EX-3600 M Energy dispersive X-ray fluorescence (EDXRF) spectrometer at ACD, BARC. A SLP series LEO Si (Li) detector (active area: 30 mm 2 ; thickness: 3.5 mm; resolution: 140 eV at 5.9 keV of Mn K X-ray) was used during the measurement and only characteristic X-rays of Ir (Lα: 9.17 keV and Lβ: 10.70 keV) was seen in the X-ray spectrum. X-ray diffraction (XRD) measurement results indicated that the Ir was in the form of metal. To confirm the XRD data, neutron activation analysis (NAA) was carried out by irradiating samples and elemental standards (as comparator) in graphite reflector position of Advanced Heavy Water Reactor Critical Facility (AHWR CF) reactor, BARC, Mumbai. After suitable decay period, gamma activity measurements were carried out using 45% HPGe detector coupled to 8 k multi channel analyzer. Characteristic gamma line at 328.4 keV of the activation product 194 Ir was used for quantification of iridium and relative method of NAA was used for concentration calculations. NAA results confirmed that all the samples were Iridium metal. (author)

Radioactive material transporting container

International Nuclear Information System (INIS)

Watabe, Yukio.

1990-01-01

As a supporting member of a sealing container for containing spent fuels, etc., a straight pipe or a cylinder has been used. However, upon dropping test, the supporting member is buckled toward the central axis of a transporting container and a shock absorber is crushed in the axial direction to prevent its pushing force to the outer side, which may possibly hinder normal shock moderating function. Then, at least more than one-half of the supporting member is protruded radially to the outer side of the sealing container beyond the fixed portion with the sealed container, so that the member has a portion extended in the radial outside of the transporting container with an angle greater than the angle formed between a line connecting the outer circumference at the bottom of an outer cylinder with the gravitational center of the transporting container and the central axis of the transporting container. As a result, buckling of the supporting member toward the central axis of the transporting container upon dropping test can be prevented and the deformation of the shock absorber is neither not prevented to exhibit normal shock absorbing effect. This can improve the reliability and reduce the amount of shock absorbers. (N.H.)

Deflagration in stainless steel storage containers containing plutonium dioxide

International Nuclear Information System (INIS)

Kleinschmidt, P.D.

1996-02-01

Detonation of hydrogen and oxygen in stainless steel storage containers produces maximum pressures of 68.5 psia and 426.7 psia. The cylinders contain 3,000 g of PuO 2 with 0.05 wt% and 0.5 wt% water respectively. The hydrogen and oxygen are produced by the alpha decomposition of the water. Work was performed for the Savannah River Site

The probability of containment failure by direct containment heating in zion

International Nuclear Information System (INIS)

Pilch, M.M.; Yan, H.; Theofanous, T.G.

1994-01-01

This report is the first step in the resolution of the Direct Containment Heating (DCH) issue for the Zion Nuclear Power Plant using the Risk Oriented Accident Analysis Methodology (ROAAM). This report includes the definition of a probabilistic framework that decomposes the DCH problem into three probability density functions that reflect the most uncertain initial conditions (UO 2 mass, zirconium oxidation fraction, and steel mass). Uncertainties in the initial conditions are significant, but the quantification approach is based on establishing reasonable bounds that are not unnecessarily conservative. To this end, the authors also make use of the ROAAM ideas of enveloping scenarios and open-quotes splinteringclose quotes. Two casual relations (CRs) are used in this framework: CR1 is a model that calculates the peak pressure in the containment as a function of the initial conditions, and CR2 is a model that returns the frequency of containment failure as a function of pressure within the containment. Uncertainty in CR1 is accounted for by the use of two independently developed phenomenological models, the Convection Limited Containment Heating (CLCH) model and the Two-Cell Equilibrium (TCE) model, and by probabilistically distributing the key parameter in both, which is the ratio of the melt entrainment time to the system blowdown time constant. The two phenomenological models have been compared with an extensive data base including recent integral simulations at two different physical scales (1/10th scale in the Surtsey facility at Sandia National Laboratories and 1/40th scale in the COREXIT facility at Argonne National Laboratory). The loads predicted by these models were significantly lower than those from previous parametric calculations. The containment load distributions do not intersect the containment strength curve in any significant way, resulting in containment failure probabilities less than 10 -3 for all scenarios considered

Definition of containment failure

International Nuclear Information System (INIS)

Cybulskis, P.

1982-01-01

Core meltdown accidents of the types considered in probabilistic risk assessments (PRA's) have been predicted to lead to pressures that will challenge the integrity of containment structures. Review of a number of PRA's indicates considerable variation in the predicted probability of containment failure as a function of pressure. Since the results of PRA's are sensitive to the prediction of the occurrence and the timing of containment failure, better understanding of realistic containment capabilities and a more consistent approach to the definition of containment failure pressures are required. Additionally, since the size and location of the failure can also significantly influence the prediction of reactor accident risk, further understanding of likely failure modes is required. The thresholds and modes of containment failure may not be independent

Accelerator development in India for ADS programme

Indian Academy of Sciences (India)

Nuclear Physics Division, Bhabha Atomic Research Centre, Mumbai 400 085, India. *Physics ... At BARC, development of a Low Energy High Intensity Proton Accelerator. (LEHIPA) ... incinerate the MA (minor actinides) and LLFP (long-lived fission products) ra- diotoxic .... figure 3 to satisfy the required boundary conditions.

Containment safety margins

International Nuclear Information System (INIS)

Von Riesemann, W.A.

1980-01-01

Objective of the Containment Safety Margins program is the development and verification of methodologies which are capable of reliably predicting the ultimate load-carrying capability of light water reactor containment structures under accident and severe environments. The program was initiated in June 1980 at Sandia and this paper addresses the first phase of the program which is essentially a planning effort. Brief comments are made about the second phase, which will involve testing of containment models

75 FR 62323 - Pesticide Management and Disposal; Standards for Pesticide Containers and Containment; Change to...

Science.gov (United States)

2010-10-08

... Pesticide Management and Disposal; Standards for Pesticide Containers and Containment; Change to Labeling... the pesticide container and containment regulations to provide an 8-month extension of the labeling... titled ``Pesticide Management and Disposal; Standards for Pesticide Containers and Containment'' (71 FR...

Simplified containment event tree analysis for the Sequoyah Ice Condenser containment

International Nuclear Information System (INIS)

Galyean, W.J.; Schroeder, J.A.; Pafford, D.J.

1990-12-01

An evaluation of a Pressurized Water Reactor (PER) ice condenser containment was performed. In this evaluation, simplified containment event trees (SCETs) were developed that utilized the vast storehouse of information generated by the NRC's Draft NUREG-1150 effort. Specifically, the computer programs and data files produced by the NUREG-1150 analysis of Sequoyah were used to electronically generate SCETs, as opposed to the NUREG-1150 accident progression event trees (APETs). This simplification was performed to allow graphic depiction of the SCETs in typical event tree format, which facilitates their understanding and use. SCETs were developed for five of the seven plant damage state groups (PDSGs) identified by the NUREG-1150 analyses, which includes: both short- and long-term station blackout sequences (SBOs), transients, loss-of-coolant accidents (LOCAs), and anticipated transient without scram (ATWS). Steam generator tube rupture (SGTR) and event-V PDSGs were not analyzed because of their containment bypass nature. After being benchmarked with the APETs, in terms of containment failure mode and risk, the SCETs were used to evaluate a number of potential containment modifications. The modifications were examined for their potential to mitigate or prevent containment failure from hydrogen burns or direct impingement on the containment by the core, (both factors identified as significant contributors to risk in the NUREG-1150 Sequoyah analysis). However, because of the relatively low baseline risk postulated for Sequoyah (i.e., 12 person-rems per reactor year), none of the potential modifications appear to be cost effective. 15 refs., 10 figs. , 17 tabs

75 FR 33705 - Pesticide Management and Disposal; Standards for Pesticide Containers and Containment; Change to...

Science.gov (United States)

2010-06-15

... Pesticide Management and Disposal; Standards for Pesticide Containers and Containment; Change to Labeling... the pesticide container and containment regulations to provide a 4-month extension of the 40 CFR 156... pesticide labels to comply with the label requirements in the container and containment regulations. DATES...

75 FR 26268 - Agency Information Collection Activities: Permit To Transfer Containers to a Container Station

Science.gov (United States)

2010-05-11

... Activities: Permit To Transfer Containers to a Container Station AGENCY: U.S. Customs and Border Protection... information collection requirement concerning the: Permit to Transfer Containers to a Container Station. This... information collection: Title: Permit to Transfer Containers to a Container Station. OMB Number: 1651-0049...

Container inspection in the port container terminal by using 14 MeV neutrons

Energy Technology Data Exchange (ETDEWEB)

Valkovic, Vladivoj [Institute Ruder Boskovic, Zagreb (Croatia); Kvinticka 62, Zagreb (Croatia); Sudac, Davorin; Nad, Karlo; Obhodas, Jasmina [Ruder Boskovic Institute, Bijenicka c.54, Zagreb (Croatia)

2015-07-01

A proposal for an autonomous and flexible ship container inspection system is presented. This could be accomplished by the incorporation of inspection system on the container transportation devices (straddle carriers, yard gentry cranes automated guided vehicles, trailers). This configuration is terminal specific and it will be decided by container terminal operator. In such a way no part of port operational area will be used for inspection. The inspection scenario will include container transfer from ship to transportation device with inspection unit mounted on it, inspection during container movement to the container location. A neutron generator without associated alpha particle detection will be used. This will allow the use of higher neutron intensity (5x10{sup 9} - 10{sup 10} n/s in 4π). The inspected container will be stationary in the 'inspection position' on the transportation device while the 'inspection unit' will move along its side. Following analytical methods will be used simultaneously: neutron radiography, X-ray radiography, neutron activation analysis, (n,γ) and (n,n'γ) reactions, neutron absorption, and scattering, X-ray backscattering, Neutron techniques will take the advantage of using 'smart collimators' for neutrons and gammas, both emitted and detected. The inspected voxel will be defined by intersections/union of neutron generator and detectors solid angles. The container inspection protocol will be based on identification of discrepancies between its cargo manifest and its elemental 'fingerprint' and radiography profiles. In addition, the information on container weight will be obtained during the container transport and foreseen screening from the measurement of density of material in the container. (authors)

The probability of containment failure by direct containment heating in surry

International Nuclear Information System (INIS)

Pilch, M.M.; Allen, M.D.; Bergeron, K.D.; Tadios, E.L.; Stamps, D.W.; Spencer, B.W.; Quick, K.S.; Knudson, D.L.

1995-05-01

In a light-water reactor core melt accident, if the reactor pressure vessel (RPV) fails while the reactor coolant system (RCS) at high pressure, the expulsion of molten core debris may pressurize the reactor containment building (RCB) beyond its failure pressure. A failure in the bottom head of the RPV, followed by melt expulsion and blowdown of the RCS, will entrain molten core debris in the high-velocity steam blowdown gas. This chain of events is called a high-pressure melt ejection (HPME). Four mechanisms may cause a rapid increase in pressure and temperature in the reactor containment: (1) blowdown of the RCS, (2) efficient debris-to-gas heat transfer, (3) exothermic metal-steam and metal-oxygen reactions, and (4) hydrogen combustion. These processes, which lead to increased loads on the containment building, are collectively referred to as direct containment heating (DCH). It is necessary to understand factors that enhance or mitigate DCH because the pressure load imposed on the RCB may lead to early failure of the containment

CONTAIN independent peer review

International Nuclear Information System (INIS)

Boyack, B.E.; Corradini, M.L.; Khatib-Rahbar, M.; Loyalka, S.K.; Smith, P.N.

1995-01-01

The CONTAIN code was developed by Sandia National Laboratories under the sponsorship of the US Nuclear Regulatory Commission (NRC) to provide integrated analyses of containment phenomena. It is used to predict nuclear reactor containment loads, radiological source terms, and associated physical phenomena for a range of accident conditions encompassing both design-basis and severe accidents. The code's targeted applications include support for containment-related experimental programs, light water and advanced light water reactor plant analysis, and analytical support for resolution of specific technical issues such as direct containment heating. The NRC decided that a broad technical review of the code should be performed by technical experts to determine its overall technical adequacy. For this purpose, a six-member CONTAIN Peer Review Committee was organized and a peer review as conducted. While the review was in progress, the NRC issued a draft ''Revised Severe Accident Code Strategy'' that incorporated revised design objectives and targeted applications for the CONTAIN code. The committee continued its effort to develop findings relative to the original NRC statement of design objectives and targeted applications. However, the revised CONTAIN design objectives and targeted applications. However, the revised CONTAIN design objectives and targeted applications were considered by the Committee in assigning priorities to the Committee's recommendations. The Committee determined some improvements are warranted and provided recommendations in five code-related areas: (1) documentation, (2) user guidance, (3) modeling capability, (4) code assessment, and (5) technical assessment

CONTAIN independent peer review

Energy Technology Data Exchange (ETDEWEB)

Boyack, B.E. [Los Alamos National Lab., NM (United States); Corradini, M.L. [Univ. of Wisconsin, Madison, WI (United States). Nuclear Engineering Dept.; Denning, R.S. [Battelle Memorial Inst., Columbus, OH (United States); Khatib-Rahbar, M. [Energy Research Inc., Rockville, MD (United States); Loyalka, S.K. [Univ. of Missouri, Columbia, MO (United States); Smith, P.N. [AEA Technology, Dorchester (United Kingdom). Winfrith Technology Center

1995-01-01

The CONTAIN code was developed by Sandia National Laboratories under the sponsorship of the US Nuclear Regulatory Commission (NRC) to provide integrated analyses of containment phenomena. It is used to predict nuclear reactor containment loads, radiological source terms, and associated physical phenomena for a range of accident conditions encompassing both design-basis and severe accidents. The code`s targeted applications include support for containment-related experimental programs, light water and advanced light water reactor plant analysis, and analytical support for resolution of specific technical issues such as direct containment heating. The NRC decided that a broad technical review of the code should be performed by technical experts to determine its overall technical adequacy. For this purpose, a six-member CONTAIN Peer Review Committee was organized and a peer review as conducted. While the review was in progress, the NRC issued a draft ``Revised Severe Accident Code Strategy`` that incorporated revised design objectives and targeted applications for the CONTAIN code. The committee continued its effort to develop findings relative to the original NRC statement of design objectives and targeted applications. However, the revised CONTAIN design objectives and targeted applications. However, the revised CONTAIN design objectives and targeted applications were considered by the Committee in assigning priorities to the Committee`s recommendations. The Committee determined some improvements are warranted and provided recommendations in five code-related areas: (1) documentation, (2) user guidance, (3) modeling capability, (4) code assessment, and (5) technical assessment.

Container Materials, Fabrication And Robustness

International Nuclear Information System (INIS)

Dunn, K.; Louthan, M.; Rawls, G.; Sindelar, R.; Zapp, P.; Mcclard, J.

2009-01-01

The multi-barrier 3013 container used to package plutonium-bearing materials is robust and thereby highly resistant to identified degradation modes that might cause failure. The only viable degradation mechanisms identified by a panel of technical experts were pressurization within and corrosion of the containers. Evaluations of the container materials and the fabrication processes and resulting residual stresses suggest that the multi-layered containers will mitigate the potential for degradation of the outer container and prevent the release of the container contents to the environment. Additionally, the ongoing surveillance programs and laboratory studies should detect any incipient degradation of containers in the 3013 storage inventory before an outer container is compromised.

Regular expression containment

DEFF Research Database (Denmark)

Henglein, Fritz; Nielsen, Lasse

2011-01-01

We present a new sound and complete axiomatization of regular expression containment. It consists of the conventional axiomatiza- tion of concatenation, alternation, empty set and (the singleton set containing) the empty string as an idempotent semiring, the fixed- point rule E* = 1 + E × E......* for Kleene-star, and a general coin- duction rule as the only additional rule. Our axiomatization gives rise to a natural computational inter- pretation of regular expressions as simple types that represent parse trees, and of containment proofs as coercions. This gives the axiom- atization a Curry......-Howard-style constructive interpretation: Con- tainment proofs do not only certify a language-theoretic contain- ment, but, under our computational interpretation, constructively transform a membership proof of a string in one regular expres- sion into a membership proof of the same string in another regular expression. We...

The function of single containment and double containment of PWR nuclear power plant

International Nuclear Information System (INIS)

Chen Weijing.

1985-01-01

The function and structures of single containment and double containment of PWR nuclear power plant were described briefiy. The dissimilarites of diffent type of containments, which effects the impact of environment are discused. The impact of environment, effected by 'source term', containment gas leak rate and diffusion pattern of the released gas, under different operating condition is analysed. Especially, the impact of environment under LOCA accident is fully analysed

Improvements in containers

International Nuclear Information System (INIS)

Guy, R.

1977-01-01

An improved container is described for transporting radioactive materials, such as irradiated Magnox fuel elements. It has a lid fixed to the container body and at the corners of the lid has shock absorbers that project from the corners and have part-spheroidal shape. The centre of curvature of the surface of the spheroid is positioned within the lid, so that impact loads on a shock absorber tend to hold it to the container rather than dislodge it. The shock absorbers may be Al-Si alloy castings. (U.K.)

Testing low cost anaerobic digestion (AD) systems

Science.gov (United States)

To evaluate the potential for low technology and low cost digesters for small dairies, BARC and researchers from the University of Maryland installed six modified Taiwanese-model field-scale (FS) digesters near the original dairy manure digester. The FS units receive the same post-separated liquid ...

Pramana – Journal of Physics | Indian Academy of Sciences

Indian Academy of Sciences (India)

... development laboratory are located at APSARA reactor. All the instruments including the detectors and electronics have been developed within BARC. A new powder diffractometer (PD-3) is being developed by UGC-DAE-CSR. The national facility is utilized in collaboration with various universities and other institutions.

Fulltext PDF

Indian Academy of Sciences (India)

We also thank Vijai Kumar of Knowledge Management Group,. BARC, and Miloslav Znojil, Nuclear Physics Institute, Czech Republic for the help extended towards registration and many other aspects of the conference. We thank Rohini Godbole, Chief Editor, Pramana – Journal of Physics for the encouragement received ...

Aerosol in the containment

International Nuclear Information System (INIS)

Lanza, S.; Mariotti, P.

1986-01-01

The US program LACE (LWR Aerosol Containment Experiments), in which Italy participates together with several European countries, Canada and Japan, aims at evaluating by means of a large scale experimental activity at HEDL the retention in the pipings and primary container of the radioactive aerosol released following severe accidents in light water reactors. At the same time these experiences will make available data through which the codes used to analyse the behaviour of the aerosol in the containment and to verify whether by means of the codes of thermohydraulic computation it is possible to evaluate with sufficient accuracy variable influencing the aerosol behaviour, can be validated. This report shows and compares the results obtained by the participants in the LACE program with the aerosol containment codes NAVA 5 and CONTAIN for the pre-test computations of the test LA 1, in which an accident called containment by pass is simulated

The Medical Cyclotron Facility in RMC, Parel, BARC

International Nuclear Information System (INIS)

Gopalakrishna, Arjun; Banerjee, Sharmila

2017-01-01

The Medical Cyclotron Facility in Radiation Medicine Centre (RMC) is the first one of its kind, installed in 2002. "1"8F based radiotracers are produced in this facility on a routine basis for Positron Emission Tomography (PET), of in-house patients, as well as for supply to other nuclear medicine centers in Mumbai as well as Pune. The facility consists of the following sub parts - Cyclotron and support equipment; Radiochemistry synthesis laboratory; Quality control (QC) laboratory

PET/CT Facility at Radiation Medicine Centre, BARC

International Nuclear Information System (INIS)

Baghel, Nawab Singh; Banerjee, Sharmila

2017-01-01

Positron Emission Tomography (PET) integrated with Computed Tomography in a single unit (PET/CT) has become an established and valued imaging modality in the clinical arena. Integrated PET/CT has been shown to be more accurate for lesion localisation and characterisation than either PET or CT alone. Image fusion brings together two image datasets with the intention of registering them as closely as possible. Generally, the two image datasets would have been produced on different types of medical imaging devices. Various problems can evolve when using two geographically remote imaging devices. To overcome this, in recent times there has been a move towards the integration of the two medical imaging devices into one physical unit. The use of one imaging unit to produce two different image datasets is known as hybrid imaging

An overview of BARC-TIFR pelletron linac facility

International Nuclear Information System (INIS)

Gupta, A.K.

2014-01-01

The 14UD Pelletron Accelerator at Mumbai has recently completed twenty five years of successful operation. The accelerator is primarily used for basic research in the fields of nuclear, atomic, condensed matter and material science. The superconducting Linac booster provides additional acceleration to the ions from Pelletron injector up to A∼60 region with E∼5 MeV/A. Further, an alternate injector system to the Superconducting LINAC booster is planned as an augmentation programme, comprising of a superconducting ECR ion source, room temperature RFQ and superconducting low-beta cavity resonators. This talk will provide an overview of the recent developmental activities carried out at the Pelletron Accelerator Facility, resulting in enhanced overall performance and uptime of the accelerator. The application oriented programs initiated at Pelletron Accelerator and the current status of the alternate injector system at the Pelletron-Linac facility will also be discussed. (author)

An overview of BARC-TIFR Pelletron-Linac Facility

International Nuclear Information System (INIS)

Gupta, A. K.

2015-01-01

The 14UD Pelletron Accelerator at Mumbai has recently completed twenty five years of successful operation. The accelerator is primarily used for basic research in the fields of nuclear, atomic, condensed matter and material science. The superconducting Linac booster provides additional acceleration to the ions from Pelletron injector up to A~60 region with E~5 MeV/A. Further, an alternate injector system to the Superconducting LINAC booster is planned as an augmentation programme, comprising of a superconducting ECR ion source, room temperature RFQ and superconducting low-beta cavity resonators. This talk will provide an overview of the recent developmental activities carried out at the Pelletron Accelerator Facility, resulting in enhanced overall performance and uptime of the accelerator. The application oriented programs initiated at Pelletron Accelerator and the current status of the alternate injector system at the Pelletron-Linac facility will also be discussed. (author)

High voltage performance of BARC-TIFR Pelletron Accelerator

Energy Technology Data Exchange (ETDEWEB)

Surendran, P.; Ansari, Q.N.; Nair, J.P., E-mail: surendra@tifr.res.in [Nuclear Physics Division, Bhabha Atomic Research Centre, Mumbai (India); and others

2014-07-01

The 14 UD Pelletron Accelerator at TIFR, Mumbai is operational since its inception in 1988. It was decided to impart enough time for high voltage conditioning to achieve higher operational voltage. Prior to this, comprehensive works such as replacing all the sputter ion pumps and Titanium sublimation pumps across the accelerator tube with new or refurbished ones and replacement of Alumina balls in the SF{sub 6} drier with fresh balls were carried out. High voltage conditioning of each module was done. Further conditioning of two modules at a time in overlapping mode improved the terminal voltage. As a result of this rigorous conditioning Terminal voltage of 12.6 MV was achieved and beam has been delivered to users at 12 MV terminal. Details of this effort will be presented in this paper. (author)

High voltage performance of BARC-TIFR Pelletron Accelerator

International Nuclear Information System (INIS)

Surendran, P.; Ansari, Q.N.; Nair, J.P.

2014-01-01

The 14 UD Pelletron Accelerator at TIFR, Mumbai is operational since its inception in 1988. It was decided to impart enough time for high voltage conditioning to achieve higher operational voltage. Prior to this, comprehensive works such as replacing all the sputter ion pumps and Titanium sublimation pumps across the accelerator tube with new or refurbished ones and replacement of Alumina balls in the SF_6 drier with fresh balls were carried out. High voltage conditioning of each module was done. Further conditioning of two modules at a time in overlapping mode improved the terminal voltage. As a result of this rigorous conditioning Terminal voltage of 12.6 MV was achieved and beam has been delivered to users at 12 MV terminal. Details of this effort will be presented in this paper. (author)

Development of scintillation and luminescent detectors at BARC

International Nuclear Information System (INIS)

Pradhan, A.S.

1991-01-01

Research and development work carried out at the Bhabha Atomic Research Centre, Bombay, in the field of radiation detectors for various applications, particularly in the area of scintillation and luminescent detectors is reviewed. The review is presented in the form of 7 articles. (author). figs

NAA in characterization of matrices at ACD, BARC

International Nuclear Information System (INIS)

Rajan A, Nicy; Swain, Kallola K.; Kayasth, Satish

2006-01-01

The use of characterization in material science means an approach that indicates those features of materials related to its composition and structure. In simple terms, characterization of a material means what atoms are present and where they are. In general characterization deals with the complete and accurate information of composition of the material (major, minor, trace elements) for specific application. Neutron activation analysis (NAA) is identified as one of the most powerful analytical technique useful for performing both qualitative and quantitative multi-element analysis of major, minor, and trace elements in almost every conceivable field of scientific/technical interest and is extensively used for wide variety of materials

Partiality and Container Monads

DEFF Research Database (Denmark)

Uustalu, Tarmo; Veltri, Niccolò

2017-01-01

the relationship between containers and lifting monads. We show that the lifting monads usually employed in type theory can be specified in terms of containers. Moreover, we give a precise characterization of containers whose interpretations carry a lifting monad structure. We show that these conditions...

CONTAINER TERMINALS IN EUROPE

Directory of Open Access Journals (Sweden)

Bart W. WIEGMANS

2001-01-01

Full Text Available This paper aims to address the linkage between logistics (in particular, the management of marketing channel flows and transport markets, while also the interaction between these two markets and intermodal container terminals is analysed. The marketing channel theory is used to describe all relevant actors and flows that run through marketing channels, starting with customer needs and ending with customer satisfaction. Porter's theory of competitive advantages is used to review competitive forces in both markets. Finally, a competitor analysis is performed for the logistics and transport market. These theories are applied so as to be able to determine the competitive position of intermodal container terminals with a view to the management of marketing channel flows and the physical transport of freight flows. Hence, the central question of this paper is: Which markets are served by intermodal container terminals and with whom are they competing? At present, neither the maritime container terminals nor the continental container terminals appear to have a significant influence in the logistics service market; they concentrate mainly on the physical movement of containers (transshipment. Furthermore, maritime container terminals and continental container terminals are not dominant players in the transport service market. Our conclusion is that continental terminals are predominantly competing with unimodal road transport, with neighbouring continental terminals and with barge transport companies.

Medium Energy Industrial Electron Beam Accelerator (ILU-EBA) at Navi Mumbai for technology demonstration and commercial operations

International Nuclear Information System (INIS)

Benny, P.G.; Khader, S.A.; Sarma, K.S.S.

2017-01-01

BARC in early nineties installed a unique high pulse-powered electron beam accelerator of energy 2 MeV, (for the first time in India), in Trombay for developing industrial applications. The accelerator was capable of delivering powered electron beams up to 20kW average beam power (with 1200kW peak pulse power) with energy range from 1 to 2 MeV. Several applications have been developed and commercially exploited in the field of polymer cross linking, degradation, crystalline alterations etc. In addition, applications pertaining to the environmental remediation using electron beams were also worked out. The facility has been relocated at Navi Mumbai a decade ago operated under BARC safety regulatory body and was developed into a technology demonstration cum commercial plant with several product handling gadgets to evaluate the feasibility of different EB treatment processes for the industry viz. waste water treatment, polymer modifications, recycling to name a few

Effluent treatment plant and decontamination centre, Trombay

International Nuclear Information System (INIS)

Kaushik, C.P.; Agarwal, K.

2017-01-01

The Bhabha Atomic Research Centre, Trombay, has a number of plants and laboratories, which generate Radioactive Liquid Waste and Protective Wears. Two facilities have been established in late 1960s to cater to this requirement. The Centre, on the average generates about 50,000 m"3 of active liquid effluents of varying specific activities. The Effluent Treatment Plant was setup to receive and process radioactive liquids generated by various facilities of BARC in Trombay. It also serves a single-point discharge facility to enable monitoring of radioactive effluents discharged from the Trombay site. About 120-150 Te of protective wears and inactive apparel are generated annually from various radioactive facilities and laboratories of BARC. In addition, contaminated fuel assembly components are generated by DHRUVA and formerly by CIRUS. These components require decontamination before its recycle to the fuel assembly process. The Decontamination Centre, setup in late 1960s, is mandated to carry out the above mentioned decontamination activities

Design and development of R.F. LINAC accelerator components

International Nuclear Information System (INIS)

Abhay Kumar; Guha, S.; Balasubramaniam, R.; Jawale, S.B.

2003-01-01

Full text: Radio frequency linear accelerator, a high power electron LINAC technology, is being developed at BARC. These accelerators are considered to be the most compact and effective for a given power capacity. Important application areas of this LINAC include medical sterilization, food preservation, pollution control, semiconductor industries, radiation therapy and material science. Center for Design and Manufacture (CDM), BARC has been entrusted with the design, development and manufacturing of various mechanical components of the accelerator. Most critical and precision components out of them are Diagnostic chamber, Faraday cup, Drift tube and R.F. cavities. This paper deals with the design aspects in respect of Ultra high vacuum compatibility and the mechanism of operation. Also this paper discusses the state-of-art technology for machining of intricate contour using specially designed poly crystalline diamond tool and the inspection methodology developed to minimize the measurement errors on the machined contour. Silver brazing technique employed to join the LINAC cavities is also described in detail

Status of services, overexposure and QAC in TLD PMS to defence

International Nuclear Information System (INIS)

Rathore, A.S.; Gupta, D.K.; Samaria, H.C.; Chouhan, R.L.; Mishra, M.; Goyal, J.K.; Gautam, M.; Kalla, R.

2008-01-01

Individual monitoring has always played an important role in radiological protection. There is continuous development in the field of dosimetry systems and many changes have taken place in last many years. The use of radiation for peaceful purposes is increasing with advancement of technological growth in the country. Thermo luminescence dosimeters (TLDs) have emerged as one of the best alternatives for personal monitoring. Defence sector has nearly 2100 persons, who are working in various Military Hospitals, Military Colleges, DRDO Labs, Defence Ordinance factories and many others CPMFs like CISF, BSF, who are likely to receive radiation doses. Defence Laboratory, Jodhpur is providing the TLD personal monitoring service since Jan 1999 as per the guideline by B.A.R.C. to all the institutions mentioned above. This paper brings out salient features of this service in terms of facility available, procedures fulfilling the requirement of accreditation, over exposure reported, quality measures adopted and quality assurance results conducted by BARC, utility and suggestions for such type of services. (author)

Utilization of electron beam accelerators for polymer processing

International Nuclear Information System (INIS)

Sarma, K.S.S.

2013-01-01

During the last decade, electron beam processing has been amply demonstrated to the Indian cable industry by BARC using 2 MeV/20 kW electron beam (EB) accelerator (ILU-6 EBA facility) located at BARC-BRIT complex, Vashi. The electron beam accelerator is a machine producing high energy electrons which are made to impinge on the materials for inducing physical, chemical and biological modifications. The process is carried out at room temperature and in ambient atmospheric conditions. Lately, quite a few numbers of accelerators have been installed by the private cable industry and carrying out cross-linking of cable insulations for high performance viz. high temperature stability, good flame retardancy, lesser solvent-swelling, thinner insulations etc. The indigenously made accelerators at EB centre, particularly the 3 MeV/30 kW accelerator will be of much help for Indian industry for polymer processing as the market is poised to grow by adapting the technology

Generation of terrestrial radiation database in the Larsemann Hills, Antarctica

International Nuclear Information System (INIS)

Pal, Rupali; Dhabekar, Bhushan; Jose, Jis Romal; Chinnaesakki, S.; Bakshi, A.K.; Datta, D.; Pradeepkumar, K.S.

2018-01-01

Natural background radiation in the environment includes terrestrial radiation, cosmic radiation from space and air activity due to radon/thoron. It is known that cosmic contribution increases near the poles. The terrestrial component is largely due to 232 Th and 238 U series and 40 K. BARC under the cosmic ray dosimetry project with National Centre for Antarctic and Ocean Research (NCAOR) has taken up measurement of natural background radiation at Larsemann Hills, Antarctica. The project includes generation of baseline data on terrestrial radioactivity in water, soil and rock and estimation of cosmic ray doses. Extensive radiation surveys were carried out by the BARC team in the 35 th and 36 th expedition in and around Larsemann hills in East Antarctica where the third Indian station 'Bharati' is situated. This paper presents mapping of terrestrial radiation levels in Antarctica which will help in strengthening the background radiation database and develop a Radiation Informatics System (RIS)

Containing method for spent fuel and spent fuel containing vessel

International Nuclear Information System (INIS)

Maekawa, Hiromichi; Hanada, Yoshine.

1996-01-01

Upon containing spent fuels, a metal vessel main body and a support spacer having fuel containing holes are provided. The support spacer is disposed in the inside of the metal vessel main body, and spent fuel assemblies are loaded in the fuel containing holes. Then, a lid is welded at the opening of the metal vessel main body to provide a sealing state. In this state, heat released from the spent fuel assemblies is transferred to the wall of the metal vessel main body via the support spacer. Since the support spacer has a greater heat conductivity than gases, heat of the spent fuel assemblies tends to be released to the outside, thereby capable of removing heat of the spent fuel assemblies effectively. In addition, since the surfaces of the spent fuel assemblies are in contact with the inner surface of the fuel containing holes of the support spacer, impact-resistance and earthquake-resistance are ensured, and radiation from the spent fuel assemblies is decayed by passing through the layer of the support spacer. (T.M.)

7 CFR 51.911 - Container.

Science.gov (United States)

2010-01-01

... 7 Agriculture 2 2010-01-01 2010-01-01 false Container. 51.911 Section 51.911 Agriculture... Standards for Grades of Table Grapes (European or Vinifera Type) 1 Definitions § 51.911 Container. Container... of grapes in packages containing 5 pounds or less, mean the master container in which the individual...

Reactor container

International Nuclear Information System (INIS)

Kato, Masami; Nishio, Masahide.

1987-01-01

Purpose: To prevent the rupture of the dry well even when the melted reactor core drops into a reactor pedestal cavity. Constitution: In a reactor container in which a dry well disposed above the reactor pedestal cavity for containing the reactor pressure vessel and a torus type suppression chamber for containing pressure suppression water are connected with each other, the pedestal cavity and the suppression chamber are disposed such that the flow level of the pedestal cavity is lower than the level of the pressure suppression water. Further, a pressure suppression water introduction pipeway for introducing the pressure suppression water into the reactor pedestal cavity is disposed by way of an ON-OFF valve. In case if the melted reactor core should fall into the pedestal cavity, the ON-OFF valve for the pressure suppression water introduction pipeway is opened to introduce the pressure suppression water in the suppression chamber into the pedestal cavity to cool the melted reactor core. (Ikeda, J.)

75 FR 43536 - Agency Information Collection Activities: Permit To Transfer Containers to a Container Station

Science.gov (United States)

2010-07-26

... Activities: Permit To Transfer Containers to a Container Station AGENCY: U.S. Customs and Border Protection... Transfer Containers to a Container Station. This is a proposed extension of an information collection that... other technological techniques or other forms of information. Title: Permit to Transfer Containers to a...

Container code recognition in information auto collection system of container inspection

International Nuclear Information System (INIS)

Su Jianping; Chen Zhiqiang; Zhang Li; Gao Wenhuan; Kang Kejun

2003-01-01

Now custom needs electrical application and automatic detection. Container inspection should not only give the image of the goods, but also auto-attain container's code and weight. Its function and track control, information transfer make up the Information Auto Collection system of Container Inspection. Code Recognition is the point. The article is based on model match, the close property of character, and uses it to recognize. Base on checkout rule, design the adjustment arithmetic, form the whole recognition strategy. This strategy can achieve high recognition ratio and robust property

Testing, verification and application of CONTAIN for severe accident analysis of LMFBR-containments

International Nuclear Information System (INIS)

Langhans, J.

1991-01-01

Severe accident analysis for LMFBR-containments has to consider various phenomena influencing the development of containment loads as pressure and temperatures as well as generation, transport, depletion and release of aerosols and radioactive materials. As most of the different phenomena are linked together their feedback has to be taken into account within the calculation of severe accident consequences. Otherwise no best-estimate results can be assured. Under the sponsorship of the German BMFT the US code CONTAIN is being developed, verified and applied in GRS for future fast breeder reactor concepts. In the first step of verification, the basic calculation models of a containment code have been proven: (i) flow calculation for different flow situations, (ii) heat transfer from and to structures, (iii) coolant evaporation, boiling and condensation, (iv) material properties. In the second step the proof of the interaction of coupled phenomena has been checked. The calculation of integrated containment experiments relating natural convection flow, structure heating and coolant condensation as well as parallel calculation of results obtained with an other code give detailed information on the applicability of CONTAIN. The actual verification status allows the following conclusion: a caucious analyst experienced in containment accident modelling using the proven parts of CONTAIN will obtain results which have the same accuracy as other well optimized and detailed lumped parameter containment codes can achieve. Further code development, additional verification and international exchange of experience and results will assure an adequate code for the application in safety analyses for LMFBRs. (orig.)

NucleDyne's passive containment system

International Nuclear Information System (INIS)

Falls, O.B. Jr.; Kleimola, F.W.

1987-01-01

A simple definition of the passive containment system is that it is a total safeguards system for light water reactors designed to prevent and contain any accidental release of radioactivity. Its passive features utilize the natural laws of physics and thermodynamics. The system encompasses three basic containments constructed as one integrated structure on the reactor building foundation. The primary containment encloses the reactor pressure vessel and coolant system and passive engineered safety systems and components. Auxiliary containment enclosures house auxiliary systems and components. Secondary containment (the reactor building), housing the primary and auxiliary containment structures, provides a second containment barrier as added defense-in-depth against leakage of radioactivity for all accidents assumed by the industry. The generic features of the passive containment system are applicable to both the boiling water reactors and the pressurized water reactors as standardized features for all power ranges. These features provide for a zero source term, the industry's ultimate safety goal. This paper relates to a four-loop pressurized water reactor

PREFACE: International Symposium on Vacuum Science & Technology and its Application for Accelerators (IVS 2012)

Science.gov (United States)

Pandit, V. S.; Pal, Gautam

2012-11-01

on Vacuum and related topics are published. NIRVAT, news, announcements, and reports are the other features of the Bulletin. The articles in the Bulletin are internationally abstracted. The Bulletin is distributed free to all members of the society. The society also publishes the proceedings of National, International Symposia/Seminars, manuals, lecture notes etc. It has published 'Vacuum Directory' containing very useful information on vacuum technology and it is in the process of updating this. The IVS has also set up its own website (http://www.ivsnet.org) in January 2002. The website contains information about IVS, lists of EC members, events and news, abstracts of articles published in the Bulletin of Indian Vacuum Society, utilities, technical data, announcements, reports, membership and other forms including advertisements. Our Society is a member society of the International Union of Vacuum Science, Techniques and Applications (IUVSTA) and many IVS members are nominated in its various committees since 1970. In 1983, IVS conducted an International Symposium on Vacuum Technology and Nuclear Applications in BARC, Mumbai under the sponsorship of IUVSTA. In 1987, IVS arranged, the Triennial International Conference on Thin Films in New Delhi, where more than 200 foreign delegates participated. IVS also hosted the IUVSTA Executive Council Meeting along with the conference. The society organized yet again an International Conference on Vacuum Science and Technology (IVS-2007) during 28-30 November 2007 at TIFR, Colaba Camups, Mumbai. IVS organizes the prestigious Professor Balakrishnan Memorial Lecture in memory of its founder vice-president. Leading scientists in the field from India and abroad are invited to deliver the talk. So far 24 lectures have been held in this series. IVS has instituted the 'IVS- Professor D Y Phadke Memorial Prize' in memory of our founder President the late Professor D Y Phadke in the University of Mumbai. The prize is given every year to

Reactor containing facility

International Nuclear Information System (INIS)

Akagawa, Katsuhiko.

1992-01-01

A cooling space having a predetermined capacity is formed between a reactor container and concrete walls. A circulation loop disposed to the outside of the concrete walls is connected to the top and the bottom of the cooling space. The circulation loop has a circulation pump and a heat exchanger, and a cooling water supply pipe is connected to the upstream of the circulation pump for introducing cooling water from the outside. Upon occurrence of loss of coolant accident, cooling water is introduced from the cooling water supply pipe to the cooling space between the reactor container and the concrete walls after shut-down of the reactor operation. Then, cooling water is circulated while being cooled by the heat exchanger, to cool the reactor container by cooling water flown in the cooling space. This can cool the reactor container in a short period of time upon occurrence of the loss of coolant accident. Accordingly, a repairing operation for a ruptured portion can be conducted rapidly. (I.N.)

Pramana – Journal of Physics | Indian Academy of Sciences

Indian Academy of Sciences (India)

A 3 MeV, 30 mA radiofrequency quadrupole (RFQ) accelerator has been designed for the low-energy high-intensity proton accelerator (LEHIPA) project at BARC, India. The beam and cavity dynamics studies were performed using the computer codes LIDOS, TOUTATIS, SUPERFISH and CST microwave studio. We have ...

16oct AM poster prog rev.pmd

Indian Academy of Sciences (India)

Administrator

1530 T V Ramakrishnan. T V Ramakrishnan. T V Ramakrishnan, BHU, Varanasi. Walter Kohn and the rise of condensed matter physics. 1600 Swapan K Ghosh. Swapan K Ghosh. Swapan K Ghosh, BARC, Mumbai. Density functional theory for materials modeling at different length scales: A legacy of Walter Kohn.

Pilot production of track etch membranes (TEMS) using heavy ion beam scanner

International Nuclear Information System (INIS)

Nair, J.P.; Surendran, P.; Sparrow, Hillary; Ninawe, N.G.; Bhagwat, P.V.; Acharya, N.; Kulshreshta, V.; Rajesh Kumar; Vijay, Y.K.; Kurup, M.B.

2005-01-01

Various methods for making TEMs were conducted at Pelletron Accelerator Facility. The technique for production using ion beam scattering was also established. This is an effort to make TEMs on pilot basis at BARC- TIFR Pelletron Accelerator using Heavy Ion Beam Scanner till large rolling mechanism is implemented

Physics and technology of tunable pulsed single longitudinal mode ...

Indian Academy of Sciences (India)

Design and technology demonstration of compact, narrow bandwidth, high repetition rate, tunable SLM dye lasers in two different configurations, namely Littrow and grazing incidence grating (GIG), were carried out in our lab at BARC, India. The single longitudinal mode (SLM) dye laser generates single-mode laser beams ...

7 CFR 502.4 - Conformity with signs and emergency directions.

Science.gov (United States)

2010-01-01

... 7 Agriculture 6 2010-01-01 2010-01-01 false Conformity with signs and emergency directions. 502.4 Section 502.4 Agriculture Regulations of the Department of Agriculture (Continued) AGRICULTURAL RESEARCH..., MARYLAND § 502.4 Conformity with signs and emergency directions. Persons in and on property of BARC shall...

Effect of pipe rupture loads inside containment in the break exclusionary piping outside containment

International Nuclear Information System (INIS)

Weiss, G.

1987-01-01

The plant design for protection against piping failures outside containment should make sure that fluid system piping in containment penetration areas are designed to meet the break exclusionary provisions contained in the BTP MEB 3-1. According to these provisions, following a piping failure (main steam line) inside containment, the part of the flued head connected to the piping outside containment, should not exceed the ASME Code stress limits for the appropriate load combinations. A finite element analysis has been performed to evaluate the stress level in this area. (orig./HP)

Analysis of Electrical Power Consumption in Container Crane of Container Terminal Surabaya

Directory of Open Access Journals (Sweden)

A.A. Masroeri

2017-12-01

Full Text Available Container crane electrification is a re-powering process of container cranes from diesel to electricity. In electrification process, it is required an analysis of electrical power consumption that is needed in the operational of container crane. It aims to determine whether the amount of electrical power that is supplied by PLN can be optimally used in the operational of container crane to do loading and unloading activities. To perform the analysis of electrical power consumption, it is required various data and calculations. The required data are container crane specifications and other electrical equipment specifications, the amount of electrical power that is supplied by PLN, also the single line diagram from the electrical system at the port. While, the calculations that is needed to be performed are the calculation of electrical power load in motors and other electrical equipments, the calculation of nominal current and start current, the selection of cable and busbar, and the calculation of wiring diagram junction power. From the calculations that has been done, then the next step is to do the load flow analysis simulation by using software simulation, so an accurate and effective load flow analysis can be obtained to optimize loading and unloading activities at the port. The result of this research, it can be seen that container crane electrification will give advantages in both technical and economical for the company and for the ship, such as accelerate the loading and unloading time of containers and reduce idle time, especially in the operational of diesel generator.

Simulation-Based Optimization for Storage Allocation Problem of Outbound Containers in Automated Container Terminals

Directory of Open Access Journals (Sweden)

Ning Zhao

2015-01-01

Full Text Available Storage allocation of outbound containers is a key factor of the performance of container handling system in automated container terminals. Improper storage plans of outbound containers make QC waiting inevitable; hence, the vessel handling time will be lengthened. A simulation-based optimization method is proposed in this paper for the storage allocation problem of outbound containers in automated container terminals (SAPOBA. A simulation model is built up by Timed-Colored-Petri-Net (TCPN, used to evaluate the QC waiting time of storage plans. Two optimization approaches, based on Particle Swarm Optimization (PSO and Genetic Algorithm (GA, are proposed to form the complete simulation-based optimization method. Effectiveness of this method is verified by experiment, as the comparison of the two optimization approaches.

Quality assurance of radiation protection monitoring instruments in India

International Nuclear Information System (INIS)

Tripathi, S.M.; Daniel, Liji; Rao, Suresh; Sharma, D.N.

2008-01-01

Bhabha Atomic Research Centre (BARC) is the National Metrology Institute (NMI) for developing, maintaining and disseminating standards for ionizing radiation in India. Radiation Safety Systems Division (RSSD) of BARC has the requisite infrastructure in the form of experts, trained manpower, laboratories, equipment and facilities for providing calibration services to users and ascertaining traceability to international standards. It periodically participates in various international inter-comparisons. RSSD maintains reference radiation fields that are required for calibrating Radiation Protection Monitoring Instruments that form the backbone of the radiation monitoring programme for harnessing the benefits of nuclear energy and ionizing radiations. These instruments are type-tested and periodically calibrated at standard reference radiation fields to ensure their healthy working condition and fitness for their intended use. This paper describes the details of the standardization procedures adopted for reference radiation fields and infrastructure established and maintained at RSSD, BARC in accordance with the recommendations of ISO-4037. The paper describes the various tests that are carried out for radiation protection monitoring instrument to study the variation of the calibration factor with influencing quantities like linearity of response, energy response, angular dependence and overload characteristics. The results of these tests for typical instruments are also discussed. The present work also describes various types of indigenously developed radiation protection monitoring instruments and their performance characteristics. Adaptability of these instruments for the implementation of operational quantities are discussed briefly. It also dwells on the IAEA Quality Audit for radiation protection level calibrations, which RSSD has been participating since 2001. Our results of the quality audit are well within the acceptance limit (±7%) set by IAEA for the

Puzzles of J/Ψ production off nuclei

International Nuclear Information System (INIS)

Kopeliovich, B.Z.

2011-01-01

Nuclear effects for J/Ψ production in pA collisions are controlled by the coherence and color transparency effects. Color transparency onsets when the time of formation of the charmonium wave function becomes longer than the inter-nucleon spacing. In this energy regime the effective break-up cross section for a c-barc dipole depends on energy and nuclear path length, and agrees well with data from fixed target experiments, both in magnitude and energy dependence. At higher energies of RHIC and LHC coherence in c-barc pair production leads to charm quark shadowing which is a complement to the high twist break up cross section. These two effects explain well with no adjusted parameters the magnitude and rapidity dependence of nuclear suppression of J/Ψ observed at RHIC in dAu collisions, while the contribution of leading twist gluon shadowing is found to be vanishingly small. A novel mechanism of double color filtering for c-barc dipoles makes nuclei significantly more transparent in AA compared to pA collisions. This is one of the mechanisms which make impossible a model independent 'data driven' extrapolation from pA to AA. This effect also explains the enhancement of nuclear suppression observed at forward rapidities in AA collisions at RHIC, what hardly can be related to the produced dense medium. J/Ψ is found to be a clean and sensitive tool measuring the transport coefficient characterizing the dense matter created in AA collisions. RHIC data for p T dependence of J/Ψ production in nuclear collisions are well explained with the low value of the transport coefficient q-hat 0 2 /fm.

Plasma container

International Nuclear Information System (INIS)

Ebisawa, Katsuyuki.

1985-01-01

Purpose: To enable to easily detect that the thickness of material to be abraded is reduced to an allowable limit from the outerside of the plasma container even during usual operation in a plasma vessel for a thermonuclear device. Constitution: A labelled material is disposed to the inside or rear face of constituent members of a plasma container undergoing the irradiation of plasma particles. A limiter plate to be abraded in the plasma container is composed of an armour member and heat removing plate, in which the armour member is made of graphite and heat-removing plate is made of copper. If the armour member is continuously abraded under the effect of sputtering due to plasma particles, silicon nitride embedded so far in the graphite at last appears on the surface of the limiter plate to undergo the impact shocks of the plasma particles. Accordingly, abrasion of the limiter material can be detected by a detector comprising gas chromatography and it can easily be detected from the outside of the plasma content even during normal operation. (Horiuchi, T.)

Wind Forces on Container Ships

DEFF Research Database (Denmark)

Andersen, Ingrid Marie Vincent

2012-01-01

An investigation of the wind forces acting on a 9,000+ TEU container ship has been carried out through a series of wind tunnel tests. It was investigated how the wind forces depend on the container configuration on the deck using a 1:450 scale model and a series of appropriate container...... are presented as nondimensional coefficients. It is concluded, that the measured forces and moment depend on the container configuration on deck, and the results may provide a general idea of how the magnitude of the wind forces is affected by a given container stacking configuration on a similar container ship....

Comparison of CONTAIN and TCE calculations for direct containment heating of Surry

International Nuclear Information System (INIS)

Washington, K.E.; Stuart, D.S.

1996-01-01

This paper presents the results of several CONTAIN code calculations used to model direct containment heating (DCH) loads for the Surry plant. The results of these calculations are compared with the results obtained using the two-cell equilibrium (TCE) model for the same set of initial and boundary conditions. This comparison is important because both models have been favorably validated against the available DCH database, yet there are potentially important modeling differences. The comparisons are to quantitatively assess the impact of these differences. A major conclusion of this study is that, for the accident conditions studied and for a broad range of sensitivity cases, the peak pressures predicted by both TCE and CONTAIN are well below the failure pressure for the Surry containment. (orig.)

76 FR 46805 - Notice of Utah Adoption by Reference of the Pesticide Container Containment Rule

Science.gov (United States)

2011-08-03

... ENVIRONMENTAL PROTECTION AGENCY [FRL-9447-8] Notice of Utah Adoption by Reference of the Pesticide Container Containment Rule AGENCY: Environmental Protection Agency (EPA). ACTION: Notice. SUMMARY: This... Pesticide Container Containment (PCC) Rule regulations. In accordance with State of Utah Agricultural Code...

Residual Stresses In 3013 Containers

International Nuclear Information System (INIS)

Mickalonis, J.; Dunn, K.

2009-01-01

The DOE Complex is packaging plutonium-bearing materials for storage and eventual disposition or disposal. The materials are handled according to the DOE-STD-3013 which outlines general requirements for stabilization, packaging and long-term storage. The storage vessels for the plutonium-bearing materials are termed 3013 containers. Stress corrosion cracking has been identified as a potential container degradation mode and this work determined that the residual stresses in the containers are sufficient to support such cracking. Sections of the 3013 outer, inner, and convenience containers, in both the as-fabricated condition and the closure welded condition, were evaluated per ASTM standard G-36. The standard requires exposure to a boiling magnesium chloride solution, which is an aggressive testing solution. Tests in a less aggressive 40% calcium chloride solution were also conducted. These tests were used to reveal the relative stress corrosion cracking susceptibility of the as fabricated 3013 containers. Significant cracking was observed in all containers in areas near welds and transitions in the container diameter. Stress corrosion cracks developed in both the lid and the body of gas tungsten arc welded and laser closure welded containers. The development of stress corrosion cracks in the as-fabricated and in the closure welded container samples demonstrates that the residual stresses in the 3013 containers are sufficient to support stress corrosion cracking if the environmental conditions inside the containers do not preclude the cracking process.

Containment severe accident thermohydraulic phenomena

International Nuclear Information System (INIS)

Frid, W.

1991-08-01

This report describes and discusses the containment accident progression and the important severe accident containment thermohydraulic phenomena. The overall objective of the report is to provide a rather detailed presentation of the present status of phenomenological knowledge, including an account of relevant experimental investigations and to discuss, to some extent, the modelling approach used in the MAAP 3.0 computer code. The MAAP code has been used in Sweden as the main tool in the analysis of severe accidents. The dependence of the containment accident progression and containment phenomena on the initial conditions, which in turn are heavily dependent on the in-vessel accident progression and phenomena as well as associated uncertainties, is emphasized. The report is in three parts dealing with: * Swedish reactor containments, the severe accident mitigation programme in Sweden and containment accident progression in Swedish PWRs and BWRs as predicted by the MAAP 3.0 code. * Key non-energetic ex-vessel phenomena (melt fragmentation in water, melt quenching and coolability, core-concrete interaction and high temperature in containment). * Early containment threats due to energetic events (hydrogen combustion, high pressure melt ejection and direct containment heating, and ex-vessel steam explosions). The report concludes that our understanding of the containment severe accident progression and phenomena has improved very significantly over the parts ten years and, thereby, our ability to assess containment threats, to quantify uncertainties, and to interpret the results of experiments and computer code calculations have also increased. (au)

7 CFR 58.339 - Containers.

Science.gov (United States)

2010-01-01

... 7 Agriculture 3 2010-01-01 2010-01-01 false Containers. 58.339 Section 58.339 Agriculture... Procedures § 58.339 Containers. (a) Containers used for the packaging of butter and related products shall be commercially acceptable containers or packaging material that will satisfactorily protect the quality of the...

21 CFR 113.60 - Containers.

Science.gov (United States)

2010-04-01

... 21 Food and Drugs 2 2010-04-01 2010-04-01 false Containers. 113.60 Section 113.60 Food and Drugs... CONSUMPTION THERMALLY PROCESSED LOW-ACID FOODS PACKAGED IN HERMETICALLY SEALED CONTAINERS Control of Components, Food Product Containers, Closures, and In-Process Materials § 113.60 Containers. (a) Closures...

Modeling of hydrogen behaviour in a PWR nuclear power plant containment with the CONTAIN code

International Nuclear Information System (INIS)

Bobovnik, G.; Kljenak, I.

2001-01-01

Hydrogen behavior in the containment during a severe accident in a two-loop Westinghouse-type PWR nuclear power plant was simulated with the CONTAIN code. The accident was initiated with a cold-leg break of the reactor coolant system in a steam generator compartment. In the input model, the containment is represented with 34 cells. Beside hydrogen concentration, the containment atmosphere temperature and pressure and the carbon monoxide concentration were observed as well. Simulations were carried out for two different scenarios: with and without successful actuation of the containment spray system. The highest hydrogen concentration occurs in the containment dome and near the hydrogen release location in the early stages of the accident. Containment sprays do not have a significant effect on hydrogen stratification.(author)

Containment vessel drain system

Science.gov (United States)

Harris, Scott G.

2018-01-30

A system for draining a containment vessel may include a drain inlet located in a lower portion of the containment vessel. The containment vessel may be at least partially filled with a liquid, and the drain inlet may be located below a surface of the liquid. The system may further comprise an inlet located in an upper portion of the containment vessel. The inlet may be configured to insert pressurized gas into the containment vessel to form a pressurized region above the surface of the liquid, and the pressurized region may operate to apply a surface pressure that forces the liquid into the drain inlet. Additionally, a fluid separation device may be operatively connected to the drain inlet. The fluid separation device may be configured to separate the liquid from the pressurized gas that enters the drain inlet after the surface of the liquid falls below the drain inlet.

Development of liquid poison injection system (SDS-2) for 500 MWe PHWRs

International Nuclear Information System (INIS)

Nawathe, Shirish; Umashankari, P.; Balakrishnan, Kamala; Mahajan, S.C.; Kakodkar, A.

1991-01-01

A secondary shut-down system (SDS-2) in the form of a mecahnism for introducing poison into the moderator of the PHWR is under development in Reactor Engineering Division of BARC. The system, as conceived, consists of a tank containing pressurised helium connected to poison tanks through quick opening solenoid valves. The tanks are connected to horizontal injection tubes in the calandria. On system actuation, gadolinium nitrate solution from the tanks passes to the injection tubes which have a number of holes through which the poison enters the moderator. This report details the development work being done on this poison injection system. An experimental facility was set up to measure the poison jet growth rate and the jet spread after injection, and mathematical models were developed to convert the observed jets into reactivity worth values. A description of the work and the computed results are presented. (author). 21 graphs. , 15 tabs

Containing and discarding method for radiation contaminated materials and radiation contaminated material containing composite member

International Nuclear Information System (INIS)

Akagawa, Katsuhiko.

1995-01-01

A container for high level radiation contaminated materials is loaded in an outer container in a state of forming a gap between the outer container and a container wall, low level radiation contaminated materials are filled to the gap between the container of the radiation contaminated materials and the container wall, and then the outer container is sealed. In addition, the thickness of the layer of the low level radiation contaminated materials is made substantially uniform. Then, since radiation rays from the container of the radiation contaminated materials are decayed by the layer of the low level radiation contaminated materials at the periphery of the container and the level of the radiation rays emitted from the outer container is extremely reduced than in a case where the entire amount of high level radiation contaminated materials are filled, the level is suppressed to an extent somewhat higher than the level in the case where the entire amount of the low level radiation contaminated materials are filled. Accordingly, the management corresponds to that for the low level radiation contaminated materials, and the steps for the management and the entire volume thereof are reduced than in a case where the high level radiation contaminated materials and the low level radiation contaminated materials are sealed separately. (N.H.)

Containment long-term operational integrity

International Nuclear Information System (INIS)

Sammataro, R.F.

1990-01-01

Periodic integrated leak rate tests are required to assure that containments continue to meet allowable leakage limits. Although overall performance has been quite good to date, several major containment aging and degradation mechanisms have been identified. Two pilot plant life extension (PLEX) studies serve as models for extending the operational integrity of present containments for light-water cooled nuclear power plants in the United States. One study is for a Boiling-Water Reactor (BWR) and the second is for a Pressurized-Water Reactor (PWR). Research and testing programs for determining the ultimate pressure capacity and failure mechanisms for containments under severe loading conditions and studies for extending the life of current plants beyond the present 40-year licensed lifetime are under way. This paper presents an overview of containment designs in the United States. Also presented are a discussion of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) and regulatory authority requirements for the design, construction, inservice inspection, leakage testing and repair of steel and concrete containments. Findings for containments from the pilot PLEX studies and continuing containment integrity research and testing programs are discussed. The ASME Code and regulatory requirements together with recommendations from the PLEX studies and containment integrity research and testing provide a basis for continued containment long-term operational integrity. (orig./GL)

Untitled

Indian Academy of Sciences (India)

(2) For a given inlet pressure and temperature, the friction coefficient decreases with increase in the mass flow rate. Also it is found that empirically predicted ... Rohatgi V K, Venkatramani N 1981 Recent advances in MHD generation, BARC Report. Satyamurthy P 1983 Analysis of a combustion driven MHD generator using ...

Evolution of nuclear spectroscopy at Saha Institute of Nuclear Physics

Indian Academy of Sciences (India)

1990 to date a variety of medium energy heavy ions were made available from the BARC-TIFR Pel- letron and the Nuclear Science Centre Pelletron. The state of the art gamma detector arrays in these centres enabled the Saha Institute groups to undertake more sophisticated experiments. Front line nuclear spectroscopy ...

Stowing the Right Containers on Container Vessels

DEFF Research Database (Denmark)

Jensen, Rune Møller

2014-01-01

’s largest container vessels using standard mathematical programming techniques and off-the-shelf solvers. The presentation will provide basic insight into the domain, with pointers to further information that enable you to join in this promising new path of operations research and business....

Component nuclear containment structure

International Nuclear Information System (INIS)

Harstead, G.A.

1979-01-01

The invention described is intended for use primarily as a nuclear containment structure. Such structures are required to surround the nuclear steam supply system and to contain the effects of breaks in the nuclear steam supply system, or i.e. loss of coolant accidents. Nuclear containment structures are required to withstand internal pressure and temperatures which result from loss of coolant accidents, and to provide for radiation shielding during operation and during the loss of coolant accident, as well as to resist all other applied loads, such as earthquakes. The nuclear containment structure described herein is a composite nuclear containment structure, and is one which structurally combines two previous systems; namely, a steel vessel, and a lined concrete structure. The steel vessel provides strength to resist internal pressure and accommodate temperature increases, the lined concrete structure provides resistance to internal pressure by having a liner which will prevent leakage, and which is in contact with the concrete structure which provides the strength to resist the pressure

Radioactive waste sealing container

International Nuclear Information System (INIS)

Tozawa, S.; Kitamura, T.; Sugimoto, S.

1984-01-01

A low- to medium-level radioactive waste sealing container is constructed by depositing a foundation coating consisting essentially of zinc, cadmium or a zinc-aluminum alloy over a steel base, then coating an organic synthetic resin paint containing a metal phosphate over the foundation coating, and thereafter coating an acryl resin, epoxy resin, and/or polyurethane paint. The sealing container can consist of a main container body, a lid placed over the main body, and fixing members for clamping and fixing the lid to the main body. Each fixing member may consist of a material obtained by depositing a coating consisting essentially of cadmium or a zinc-aluminum alloy over a steel base

Lift-based up-ender and methods using same to manipulate a shipping container containing unirradiated nuclear fuel

Science.gov (United States)

Nilles, Michael J.

2017-08-01

A shipping container containing an unirradiated nuclear fuel assembly is lifted off the ground by operating a crane to raise a lifting tool comprising a winch. The lifting tool is connected with the shipping container by a rigging line connecting with the shipping container at a lifting point located on the shipping container between the top and bottom of the shipping container, and by winch cabling connecting with the shipping container at the top of the shipping container. The shipping container is reoriented by operating the winch to adjust the length of the winch cabling so as to rotate the shipping container about the lifting point. Shortening the winch cabling rotates the shipping container about the lifting point from a horizontal orientation to a vertical orientation, while lengthening the winch cabling rotates the shipping container about the lifting point from the vertical orientation to the horizontal orientation.

Corrosion resistance of titanium-containing dental orthodontic wires in fluoride-containing artificial saliva

International Nuclear Information System (INIS)

Lee, T.-H.; Wang, C.-C.; Huang, T.-K.; Chen, L.-K.; Chou, M.-Y.; Huang, H.-H.

2009-01-01

This study was to investigate the corrosion resistance of different Ti-containing dental orthodontic wires (including Ni-Ti, Ni-Ti-Cu, Ti-Mo-Zr-Sn, and Ti-Nb alloys) in acidic fluoride-containing artificial saliva using cyclic potentiodynamic polarization curve measurements. Different NaF concentrations (0%, 0.2%, and 0.5%), simulating the fluoride contents in commercial toothpastes, were added to the artificial saliva. Surface characterization was analyzed using X-ray photoelectron spectrometry. Cyclic potentiodynamic polarization curves showed that the presence of fluoride ions, especially 0.5% NaF, was detrimental to the protective ability of the TiO 2 -based film on the Ti-containing wires. This might lead to a decrease in the corrosion resistance of the tested alloys, i.e. an increase in the corrosion rate and anodic current density and a decrease in the passive film breakdown potential. Among the tested Ti-containing wires, the Ni-Ti and Ni-Ti-Cu wires containing mainly TiO 2 on surface film were more susceptible to fluoride-enhanced corrosion, while the Ti-Mo-Zr-Sn and Ti-Nb wires containing MoO 3 /ZrO 2 /SnO and Nb 2 O 5 , respectively, along with TiO 2 on surface film were pitting corrosion resistant and showed a lower susceptibility to fluoride-enhanced corrosion. The difference in corrosion resistance of the tested commercial Ti-containing dental orthodontic wires was significantly dependent on the passive film characteristics on wires' surface.

27 CFR 30.44 - Weighing containers.

Science.gov (United States)

2010-04-01

... 27 Alcohol, Tobacco Products and Firearms 1 2010-04-01 2010-04-01 false Weighing containers. 30.44... Weighing containers. (a) Weighing containers of more than 10 wine gallons. The weight of containers having.... (b) Weighing containers of 10 wine gallons or less. The weight for containers of a capacity of 10...

Multicusp plasma containment apparatus

International Nuclear Information System (INIS)

Limpaecher, R.

1980-01-01

It has been discovered that plasma containment by a chamber having multi-pole magnetic cusp reflecting walls in combination with electronic injection for electrostatic containment provides the means for generating magnetic field free quiescent plasmas for practical application in ion-pumps, electronic switches, and the like. 1250 ''alnico v'' magnets 1/2 '' X 1/2 '' X 1 1/2 '' provide containment in one embodiment. Electromagnets embodying toroidal funneling extend the principle to fusion apparatus

Vector coherent state representations of SO5 contains SU2 + SU2 contains U1 + U1 and SO5 contains U1 + U1

International Nuclear Information System (INIS)

Pan Feng

1991-01-01

VCS representations of SO 5 contains SU 2 + SU 2 contains U 1 + U 1 and SO 5 contains U 1 + U 1 are discussed. Reduced matrix elements for SO 5 contains SU 2 + SU 2 are derived. The multiplicity of a weight for SO 5 is determined by using the K-matrix technique

Container for spent fuel assembly

International Nuclear Information System (INIS)

Sawai, Takeshi.

1996-01-01

The container of the present invention comprises a container main body having a body portion which can contain spent fuel assemblies and a lid, and heat pipes having an evaporation portion disposed along the outer surface of the spent fuel assemblies to be contained and a condensation portion exposed to the outside of the container main body. Further, the heat pipe is formed spirally at the evaporation portions so as to surround the outer circumference of the spent fuel assemblies, branched into a plurality of portions at the condensation portion, each of the branched portion of the condensation portion being exposed to the outside of the container main body, and is tightly in contact with the periphery of the slit portions disposed to the container main body. Then, since released after heat is transferred to the outside of the container main body from the evaporation portion of the heat pipe along the outer surface of the spent fuel assemblies by way of the condensation portion of the heat pipes exposed to the outside of the container main body, the efficiency of the heat transfer is extremely improved to enhance the effect of removing heat of spent fuel assemblies. Further, cooling effect is enhanced by the spiral form of the evaporation portion and the branched condensation portion. (N.H.)

Beverage containers in municipal waste

Energy Technology Data Exchange (ETDEWEB)

Enhoerning, B

1979-01-01

The composition of containers (cans, glass) in Sweden's wastes is given. Recycling and reclamation of these containers are discussed. The energy demand of fabricating the containers is analyzed for recycling rates of 0 and 100%. The free forces of the market cannot be depended on to direct the containers back to the manufacturer; only a well-functioning deposit system can do this. 7 figures. (DLC)

Pituitary tumors containing cholecystokinin

DEFF Research Database (Denmark)

Rehfeld, J F; Lindholm, J; Andersen, B N

1987-01-01

We found small amounts of cholecystokinin in the normal human adenohypophysis and therefore examined pituitary tumors from 87 patients with acromegaly, Cushing's disease, Nelson's syndrome, prolactinoma, or inactive pituitary adenomas. Five adenomas associated with Nelson's syndrome contained......'s disease and 7 acromegaly with adenomas containing ACTH. The cholecystokinin peptides from the tumors were smaller and less sulfated than cholecystokinin from normal pituitary glands. We conclude that ACTH-producing pituitary cells may also produce an altered form of cholecystokinin....

Pramana – Journal of Physics | Indian Academy of Sciences

Indian Academy of Sciences (India)

A specific research and development program has been carried out by BARC in India to develop the technology for large area silicon strip detectors for application in nuclear and high energy physics experiments. These strip detectors will be used as pre-shower detector in the CMS experiment at LHC, CERN for 0/ ...

Fulltext PDF

Indian Academy of Sciences (India)

record our thanks to all of them, especially to the members of the International Advi- sory Committee, Organizing Committee and the members of the Nuclear Physics Division,. BARC, for their advice and help at various stages of organizing the symposium. The financial support provided by the Board of Research in Nuclear ...

Passive cooling containment study

International Nuclear Information System (INIS)

Shin, J.J.; Iotti, R.C.; Wright, R.F.

1993-01-01

Pressure and temperature transients of nuclear reactor containment following postulated loss of coolant accident with a coincident station blackout due to total loss of all alternating current power are studied analytically and experimentally for the full scale NPR (New Production Reactor). All the reactor and containment cooling under this condition would rely on the passive cooling system which removes reactor decay heat and provides emergency core and containment cooling. Containment passive cooling for this study takes place in the annulus between containment steel shell and concrete shield building by natural convection air flow and thermal radiation. Various heat transfer coefficients inside annular air space were investigated by running the modified CONTEMPT code CONTEMPT-NPR. In order to verify proper heat transfer coefficient, temperature, heat flux, and velocity profiles were measured inside annular air space of the test facility which is a 24 foot (7.3m) high, steam heated inner cylinder of three foot (.91m) diameter and five and half foot (1.7m) diameter outer cylinder. Comparison of CONTEMPT-NPR and WGOTHIC was done for reduced scale NPR

Mobile nuclear reactor containment vessel

International Nuclear Information System (INIS)

Thompson, R.E.; Spurrier, F.R.; Jones, A.R.

1978-01-01

A containment vessel for use in mobile nuclear reactor installations is described. The containment vessel completely surrounds the entire primary system, and is located as close to the reactor primary system components as is possible in order to minimize weight. In addition to being designed to withstand a specified internal pressure, the containment vessel is also designed to maintain integrity as a containment vessel in case of a possible collision accident

Corrosion resistance of titanium-containing dental orthodontic wires in fluoride-containing artificial saliva

Energy Technology Data Exchange (ETDEWEB)

Lee, T.-H. [Institute of Medicine, Chung Shan Medical University, Taichung 402, Taiwan (China); Department of Dentistry, Chung Shan Medical University Hospital, Taichung 402, Taiwan (China); Wang, C.-C. [Department of Dental Laboratory Technology, Min-Hwei College of Health Care Management, Tainan County 736, Taiwan (China); Huang, T.-K. [College of Dental Medicine, Kaohsiung Medical University, Kaohsiung 807, Taiwan (China); Chen, L.-K. [Department of Dentistry, Taipei City Hospital, Taipei 115, Taiwan (China); Chou, M.-Y. [Institute of Medicine, Chung Shan Medical University, Taichung 402, Taiwan (China); Department of Dentistry, Chung Shan Medical University Hospital, Taichung 402, Taiwan (China); Huang, H.-H., E-mail: hhhuang@ym.edu.t [Department of Dentistry, Taipei City Hospital, Taipei 115, Taiwan (China); Department of Dentistry, National Yang-Ming University, Taipei 112, Taiwan (China); Institute of Oral Biology, National Yang-Ming University, Taipei 112, Taiwan (China)

2009-11-20

This study was to investigate the corrosion resistance of different Ti-containing dental orthodontic wires (including Ni-Ti, Ni-Ti-Cu, Ti-Mo-Zr-Sn, and Ti-Nb alloys) in acidic fluoride-containing artificial saliva using cyclic potentiodynamic polarization curve measurements. Different NaF concentrations (0%, 0.2%, and 0.5%), simulating the fluoride contents in commercial toothpastes, were added to the artificial saliva. Surface characterization was analyzed using X-ray photoelectron spectrometry. Cyclic potentiodynamic polarization curves showed that the presence of fluoride ions, especially 0.5% NaF, was detrimental to the protective ability of the TiO{sub 2}-based film on the Ti-containing wires. This might lead to a decrease in the corrosion resistance of the tested alloys, i.e. an increase in the corrosion rate and anodic current density and a decrease in the passive film breakdown potential. Among the tested Ti-containing wires, the Ni-Ti and Ni-Ti-Cu wires containing mainly TiO{sub 2} on surface film were more susceptible to fluoride-enhanced corrosion, while the Ti-Mo-Zr-Sn and Ti-Nb wires containing MoO{sub 3}/ZrO{sub 2}/SnO and Nb{sub 2}O{sub 5}, respectively, along with TiO{sub 2} on surface film were pitting corrosion resistant and showed a lower susceptibility to fluoride-enhanced corrosion. The difference in corrosion resistance of the tested commercial Ti-containing dental orthodontic wires was significantly dependent on the passive film characteristics on wires' surface.

Containment vessel stability analysis

International Nuclear Information System (INIS)

Harstead, G.A.; Morris, N.F.; Unsal, A.I.

1983-01-01

The stability analysis for a steel containment shell is presented herein. The containment is a freestanding shell consisting of a vertical cylinder with a hemispherical dome. It is stiffened by large ring stiffeners and relatively small longitudinal stiffeners. The containment vessel is subjected to both static and dynamic loads which can cause buckling. These loads must be combined prior to their use in a stability analysis. The buckling loads were computed with the aid of the ASME Code case N-284 used in conjunction with general purpose computer codes and in-house programs. The equations contained in the Code case were used to compute the knockdown factors due to shell imperfections. After these knockdown factors were applied to the critical stress states determined by freezing the maximum dynamic stresses and combining them with other static stresses, a linear bifurcation analysis was carried out with the aid of the BOSOR4 program. Since the containment shell contained large penetrations, the Code case had to be supplemented by a local buckling analysis of the shell area surrounding the largest penetration. This analysis was carried out with the aid of the NASTRAN program. Although the factor of safety against buckling obtained in this analysis was satisfactory, it is claimed that the use of the Code case knockdown factors are unduly conservative when applied to the analysis of buckling around penetrations. (orig.)

27 CFR 19.581 - Authorized containers.

Science.gov (United States)

2010-04-01

... 27 Alcohol, Tobacco Products and Firearms 1 2010-04-01 2010-04-01 false Authorized containers. 19..., DEPARTMENT OF THE TREASURY LIQUORS DISTILLED SPIRITS PLANTS Containers and Marks Containers § 19.581 Authorized containers. (a) General. Proprietors shall use for any purpose of containing, storing...

Aircraft transporting container for nuclear fuel

International Nuclear Information System (INIS)

Kurakami, Jun-ichi; Kubo, Minoru.

1991-01-01

The present invention concerns an air craft transporting container for nuclear fuels. A sealing container that seals a nuclear fuel container and constitutes a sealed boundary for the transporting container is incorporated in an inner container. Shock absorbers are filled for absorbing impact shock energy in the gap between the inner container and the sealing container. The inner container is incorporated with wooden impact shock absorbers being filled so that it is situated in a substantially central portion of an external container. Partitioning cylinders are disposed coaxially in the cylindrical layer filled with wooden impact shock absorbers at an intermediate portion between the outer and the inner containers. Further, a plurality of longitudinally intersecting partitioning disks are disposed each at a predetermined distance in right and left cylindrical wooden impact shock absorbing layers which are in contact with the end face of the inner container. Accordingly, the impact shock energy can be absorbed by the wooden impact shock absorbers efficiently by a plurality of the partitioning disks and the partitioning cylinders. (I.N.)

Disposal/storage container development experience

International Nuclear Information System (INIS)

Morrow, R.W. Jr.; Van Hoesen, S.D.; Fowler, E.; Barreira, D.G.; Emmett, R.W.

1988-01-01

Developmental work is currently underway at the Oak Ridge National Laboratory to design and manufacture a radioactive waste container suitable for both storage and disposal of radioactive wastes. The container is designed to fulfill the Department of Energy and Nuclear Regulatory Commission requirements for on-site storage, as well as the Nuclear Regulatory Commission's requirements for high integrity containers. The project also involves meeting the strict design and manufacturing ANSI/ASME NQA-1 guidelines. Special provisions of the container include a double containment system, with the inner barrier being corrosion resistant, the capability to monitor the internal cavity of the container, and off-gas venting capability. Further, yet related developmental work includes evaluating the cask for other varied uses, such as a processing cask, an ALARA shield, and even the possibility of Department of Transportation approval for an over-the-road transport cask

Code manual for CONTAIN 2.0: A computer code for nuclear reactor containment analysis

International Nuclear Information System (INIS)

Murata, K.K.; Williams, D.C.; Griffith, R.O.; Gido, R.G.; Tadios, E.L.; Davis, F.J.; Martinez, G.M.; Washington, K.E.; Tills, J.

1997-12-01

The CONTAIN 2.0 computer code is an integrated analysis tool used for predicting the physical conditions, chemical compositions, and distributions of radiological materials inside a containment building following the release of material from the primary system in a light-water reactor accident. It can also predict the source term to the environment. CONTAIN 2.0 is intended to replace the earlier CONTAIN 1.12, which was released in 1991. The purpose of this Code Manual is to provide full documentation of the features and models in CONTAIN 2.0. Besides complete descriptions of the models, this Code Manual provides a complete description of the input and output from the code. CONTAIN 2.0 is a highly flexible and modular code that can run problems that are either quite simple or highly complex. An important aspect of CONTAIN is that the interactions among thermal-hydraulic phenomena, aerosol behavior, and fission product behavior are taken into account. The code includes atmospheric models for steam/air thermodynamics, intercell flows, condensation/evaporation on structures and aerosols, aerosol behavior, and gas combustion. It also includes models for reactor cavity phenomena such as core-concrete interactions and coolant pool boiling. Heat conduction in structures, fission product decay and transport, radioactive decay heating, and the thermal-hydraulic and fission product decontamination effects of engineered safety features are also modeled. To the extent possible, the best available models for severe accident phenomena have been incorporated into CONTAIN, but it is intrinsic to the nature of accident analysis that significant uncertainty exists regarding numerous phenomena. In those cases, sensitivity studies can be performed with CONTAIN by means of user-specified input parameters. Thus, the code can be viewed as a tool designed to assist the knowledge reactor safety analyst in evaluating the consequences of specific modeling assumptions

Code manual for CONTAIN 2.0: A computer code for nuclear reactor containment analysis

Energy Technology Data Exchange (ETDEWEB)

Murata, K.K.; Williams, D.C.; Griffith, R.O.; Gido, R.G.; Tadios, E.L.; Davis, F.J.; Martinez, G.M.; Washington, K.E. [Sandia National Labs., Albuquerque, NM (United States); Tills, J. [J. Tills and Associates, Inc., Sandia Park, NM (United States)

1997-12-01

The CONTAIN 2.0 computer code is an integrated analysis tool used for predicting the physical conditions, chemical compositions, and distributions of radiological materials inside a containment building following the release of material from the primary system in a light-water reactor accident. It can also predict the source term to the environment. CONTAIN 2.0 is intended to replace the earlier CONTAIN 1.12, which was released in 1991. The purpose of this Code Manual is to provide full documentation of the features and models in CONTAIN 2.0. Besides complete descriptions of the models, this Code Manual provides a complete description of the input and output from the code. CONTAIN 2.0 is a highly flexible and modular code that can run problems that are either quite simple or highly complex. An important aspect of CONTAIN is that the interactions among thermal-hydraulic phenomena, aerosol behavior, and fission product behavior are taken into account. The code includes atmospheric models for steam/air thermodynamics, intercell flows, condensation/evaporation on structures and aerosols, aerosol behavior, and gas combustion. It also includes models for reactor cavity phenomena such as core-concrete interactions and coolant pool boiling. Heat conduction in structures, fission product decay and transport, radioactive decay heating, and the thermal-hydraulic and fission product decontamination effects of engineered safety features are also modeled. To the extent possible, the best available models for severe accident phenomena have been incorporated into CONTAIN, but it is intrinsic to the nature of accident analysis that significant uncertainty exists regarding numerous phenomena. In those cases, sensitivity studies can be performed with CONTAIN by means of user-specified input parameters. Thus, the code can be viewed as a tool designed to assist the knowledge reactor safety analyst in evaluating the consequences of specific modeling assumptions.

Reactor container

International Nuclear Information System (INIS)

Shibata, Satoru; Kawashima, Hiroaki

1984-01-01

Purpose: To optimize the temperature distribution of the reactor container so as to moderate the thermal stress distribution on the reactor wall of LMFBR type reactor. Constitution: A good heat conductor (made of Al or Cu) is appended on the outer side of the reactor container wall from below the liquid level to the lower face of a deck plate. Further, heat insulators are disposed to the outside of the good heat conductor. Furthermore, a gas-cooling duct is circumferentially disposed at the contact portion between the good heat conductor and the deck plate around the reactor container. This enables to flow the cold heat from the liquid metal rapidly through the good heat conductor to the cooling duct and allows to maintain the temperature distribution on the reactor wall substantially linear even with the abrupt temperature change in the liquid metal. Further, by appending the good heat conductor covered with inactive metals not only on the outer side but also on the inside of the reactor wall to introduce the heat near the liquid level to the upper portion and escape the same to the cooling layer below the roof slab, the effect can be improved further. (Ikeda, J.)

Advanced Containment System

Science.gov (United States)

Kostelnik, Kevin M.; Kawamura, Hideki; Richardson, John G.; Noda, Masaru

2004-10-12

An advanced containment system for containing buried waste and associated leachate. A trench is dug on either side of the zone of interest containing the buried waste so as to accommodate a micro tunnel boring machine. A series of small diameter tunnels are serially excavated underneath the buried waste. The tunnels are excavated by the micro tunnel boring machine at a consistent depth and are substantially parallel to each other. As tunneling progresses, steel casing sections are connected end to end in the excavated portion of the tunnel so that a steel tube is formed. Each casing section has complementary interlocking structure running its length that interlocks with complementary interlocking structure on the adjacent casing section. Thus, once the first tube is emplaced, placement of subsequent tubes is facilitated by the complementary interlocking structure on the adjacent, previously placed, casing sections.

10 CFR 20.1904 - Labeling containers.

Science.gov (United States)

2010-01-01

... 10 Energy 1 2010-01-01 2010-01-01 false Labeling containers. 20.1904 Section 20.1904 Energy....1904 Labeling containers. (a) The licensee shall ensure that each container of licensed material bears... handling or using the containers, or working in the vicinity of the containers, to take precautions to...

49 CFR 178.318-2 - Container.

Science.gov (United States)

2010-10-01

... 49 Transportation 2 2010-10-01 2010-10-01 false Container. 178.318-2 Section 178.318-2... Specifications for Containers for Motor Vehicle Transportation § 178.318-2 Container. (a) Every container for... individual cell in the body of the container, into which each such cap shall snugly fit. There shall be...

About the movement of an ideal fluid contained in an elastic container

International Nuclear Information System (INIS)

Fraguela Collar, A.

1990-11-01

In this paper one considers the linearized problem about the determination of the movement of an ideal heavy fluid contained in an unbounded container with elastic walls. As initial data one knows the movement of the bottom and of the free surface of the fluid and also the strength of certain perturbation enough to take the bottom out of its rest state. One important point to be considered regards the influence of the bottom's geometry on the propagation of superficial waves. This problem has been already studied in other works without considering the elastic properties of the bottom and considering a cylindrical container with bounded section. (author). 8 refs

Accident resistant transport container

Science.gov (United States)

Anderson, J.A.; Cole, K.K.

The invention relates to a container for the safe air transport of plutonium having several intermediate wood layers and a load spreader intermediate an inner container and an outer shell for mitigation of shock during a hypothetical accident.

Accident resistant transport container

International Nuclear Information System (INIS)

Andersen, J.A.; Cole, J.K.

1980-01-01

The invention relates to a container for the safe air transport of plutonium having several intermediate wood layers and a load spreader intermediate an inner container and an outer shell for mitigation of shock during a hypothetical accident

Nuclear reactor containing facility

International Nuclear Information System (INIS)

Hidaka, Masataka; Murase, Michio.

1994-01-01

In a reactor containing facility, a condensation means is disposed above the water level of a cooling water pool to condensate steams of the cooling water pool, and return the condensated water to the cooling water pool. Upon occurrence of a pipeline rupture accident, steams generated by after-heat of a reactor core are caused to flow into a bent tube, blown from the exit of the bent tube into a suppression pool and condensated in a suppression pool water, thereby suppressing the pressure in the reactor container. Cooling water in the cooling water pool is boiled by heat conduction due to the condensation of steams, then the steams are exhausted to the outside of the reactor container to remove the heat of the reactor container to the outside of the reactor. In addition, since cooling water is supplied to the cooling water pool quasi-permanently by gravity as a natural force, the reactor container can be cooled by the cooling water pool for a long period of time. Since the condensation means is constituted with a closed loop and interrupted from the outside, radioactive materials are never released to the outside. (N.H.)

7 CFR 946.18 - Container.

Science.gov (United States)

2010-01-01

... 7 Agriculture 8 2010-01-01 2010-01-01 false Container. 946.18 Section 946.18 Agriculture Regulations of the Department of Agriculture (Continued) AGRICULTURAL MARKETING SERVICE (Marketing Agreements... Order Regulating Handling Definitions § 946.18 Container. Container means a sack, box, bag, crate...

7 CFR 925.13 - Container.

Science.gov (United States)

2010-01-01

... 7 Agriculture 8 2010-01-01 2010-01-01 false Container. 925.13 Section 925.13 Agriculture Regulations of the Department of Agriculture (Continued) AGRICULTURAL MARKETING SERVICE (Marketing Agreements... SOUTHEASTERN CALIFORNIA Definitions § 925.13 Container. Container means any lug, box, bag, crate, carton, or...

7 CFR 917.12 - Container.

Science.gov (United States)

2010-01-01

... 7 Agriculture 8 2010-01-01 2010-01-01 false Container. 917.12 Section 917.12 Agriculture Regulations of the Department of Agriculture (Continued) AGRICULTURAL MARKETING SERVICE (Marketing Agreements... CALIFORNIA Order Regulating Handling Definitions § 917.12 Container. Container means a box, bag, crate, lug...

7 CFR 922.17 - Container.

Science.gov (United States)

2010-01-01

... 7 Agriculture 8 2010-01-01 2010-01-01 false Container. 922.17 Section 922.17 Agriculture Regulations of the Department of Agriculture (Continued) AGRICULTURAL MARKETING SERVICE (Marketing Agreements... IN WASHINGTON Order Regulating Handling Definitions § 922.17 Container. Container means a box, bag...

7 CFR 956.9 - Container.

Science.gov (United States)

2010-01-01

... 7 Agriculture 8 2010-01-01 2010-01-01 false Container. 956.9 Section 956.9 Agriculture Regulations of the Department of Agriculture (Continued) AGRICULTURAL MARKETING SERVICE (Marketing Agreements and... OF SOUTHEAST WASHINGTON AND NORTHEAST OREGON Definitions § 956.9 Container. Container means a box...

7 CFR 959.13 - Container.

Science.gov (United States)

2010-01-01

... 7 Agriculture 8 2010-01-01 2010-01-01 false Container. 959.13 Section 959.13 Agriculture Regulations of the Department of Agriculture (Continued) AGRICULTURAL MARKETING SERVICE (Marketing Agreements... Regulating Handling Definitions § 959.13 Container. Container means a box, bag, crate, hamper, basket...

7 CFR 945.16 - Container.

Science.gov (United States)

2010-01-01

... 7 Agriculture 8 2010-01-01 2010-01-01 false Container. 945.16 Section 945.16 Agriculture Regulations of the Department of Agriculture (Continued) AGRICULTURAL MARKETING SERVICE (Marketing Agreements... Container. Container means a sack, box, bag, crate, hamper, basket, carton, package, barrel, or any other...

7 CFR 948.14 - Container.

Science.gov (United States)

2010-01-01

... 7 Agriculture 8 2010-01-01 2010-01-01 false Container. 948.14 Section 948.14 Agriculture Regulations of the Department of Agriculture (Continued) AGRICULTURAL MARKETING SERVICE (Marketing Agreements... Order Regulating Handling Definitions § 948.14 Container. Container means a sack, bag, crate, box...

7 CFR 966.13 - Container.

Science.gov (United States)

2010-01-01

... 7 Agriculture 8 2010-01-01 2010-01-01 false Container. 966.13 Section 966.13 Agriculture Regulations of the Department of Agriculture (Continued) AGRICULTURAL MARKETING SERVICE (Marketing Agreements... Regulating Handling Definitions § 966.13 Container. Container means a box, bag, crate, hamper, basket...

7 CFR 906.12 - Container.

Science.gov (United States)

2010-01-01

... 7 Agriculture 8 2010-01-01 2010-01-01 false Container. 906.12 Section 906.12 Agriculture Regulations of the Department of Agriculture (Continued) AGRICULTURAL MARKETING SERVICE (Marketing Agreements... RIO GRANDE VALLEY IN TEXAS Order Regulating Handling Definitions § 906.12 Container. Container means...

7 CFR 916.14 - Container.

Science.gov (United States)

2010-01-01

... 7 Agriculture 8 2010-01-01 2010-01-01 false Container. 916.14 Section 916.14 Agriculture Regulations of the Department of Agriculture (Continued) AGRICULTURAL MARKETING SERVICE (Marketing Agreements... Regulating Handling Definitions § 916.14 Container. Container means a box, bag, crate, lug, basket, carton...

7 CFR 923.17 - Container.

Science.gov (United States)

2010-01-01

... 7 Agriculture 8 2010-01-01 2010-01-01 false Container. 923.17 Section 923.17 Agriculture Regulations of the Department of Agriculture (Continued) AGRICULTURAL MARKETING SERVICE (Marketing Agreements... COUNTIES IN WASHINGTON Order Regulating Handling Definitions § 923.17 Container. Container means a box, bag...

Remote container monitoring and surveillance systems

International Nuclear Information System (INIS)

Resnik, W.M.; Kadner, S.P.

1995-01-01

Aquila Technologies Group is developing a monitoring and surveillance system to monitor containers of nuclear materials. The system will both visually and physically monitor the containers. The system is based on the combination of Aquila's Gemini All-Digital Surveillance System and on Aquila's AssetLAN trademark asset tracking technology. This paper discusses the Gemini Digital Surveillance system as well as AssetLAN technology. The Gemini architecture with emphasis on anti-tamper security features is also described. The importance of all-digital surveillance versus other surveillance methods is also discussed. AssetLAN trademark technology is described, emphasizing the ability to continually track containers (as assets) by location utilizing touch memory technology. Touch memory technology provides unique container identification, as well as the ability to store and retrieve digital information on the container. This information may relate to container maintenance, inspection schedules, and other information. Finally, this paper describes the combination of the Gemini system with AssetLAN technology, yielding a self contained, container monitoring and area/container surveillance system. Secure container fixture design considerations are discussed. Basic surveillance review functions are also discussed

Airborne microorganisms from waste containers.

Science.gov (United States)

Jedlicka, Sabrina S; Stravitz, David M; Lyman, Charles E

2012-01-01

In physician's offices and biomedical labs, biological waste is handled every day. This waste is disposed of in waste containers designed for holding red autoclave bags. The containers used in these environments are closed hands-free containers, often with a step pedal. While these containers protect the user from surface-borne microorganisms, the containers may allow airborne microorganisms to escape via the open/close mechanism because of the air current produced upon open/close cycles. In this study, the air current was shown to be sufficient to allow airborne escape of microorganisms held in the container, including Aspergillus niger. However, bacterial cultures, such as Escherichia coli and Lactococcus lactis did not escape. This may be due to the choice of bacterial cultures and the absence of solid waste, such as dust or other particulate matter in the waste containers, that such strains of bacteria could travel on during aerosolization. We compared these results to those obtained using a re-designed receptacle, which mimimizes air currents, and detected no escaping microorganisms. This study highlights one potential source of airborne contamination in labs, hospitals, and other environments that dispose of biological waste.

Design, development and operational experience of radio frequency (RF) power systems/technologies for LEHIPA and 400 keV RFQ

International Nuclear Information System (INIS)

Pande, Manjiri; Shrotriya, Sandip; Patel, Niranjan

2015-01-01

The important technology development for ion accelerators of 'accelerator driven sub critical reactor system (ADS) is being done under the program of Department of Atomic Energy (DAE). In BARC (BARC) of DAE, technology development of 400 keV radio frequency quadrupole (RFQ) accelerator is done and a 20 MeV - low energy high intensity proton accelerator (LEHIPA) is under development. A 400 KeV deuteron RFQ accelerator is already developed at BARC and its 60 kW radio frequency (RF) power system required for beam acceleration has been designed, developed and tested both in CW mode and in pulse mode for full power of 60 leW. It has been successfully integrated with RFQ via 6-1/8'', 50 ohm RF transmission line, to accelerate proton beam up to 200 KeV energy and deuteron beam to 400 KeV energy. LEHIPA requires about 3 MW of RF power for its operation. So, three 1 MW, 352 MHz RF systems based on klystron will be developed for RFQ and two DTLs. The klystron based RF system for 3 MeV RFQ is under commissioning. Its various subsystems like energy less and insulated gate bipolar transistor (IGBT) based high voltage and low voltage bias supplies, a critical and fast protection and control system - handling various types of field signals, fast acting hard wired instrumentation circuits for critical signals, 100 kV crowbar with its circuits, pulsing circuits and RF circuits have been successfully designed, developed and integrated with klystron. Latest technology development of solid state RF amplifiers at 325 MHz and 350 MHz for normal and super conducting accelerators has attained a certain power level. This paper will discuss all these high power RF systems in detail. (author)

Design and development of an ultrasonic pulser-receiver unit for non-destructive testing of materials

International Nuclear Information System (INIS)

Patankar, V.H.; Joshi, V.M.

2002-11-01

The pulser/receiver constitutes the most vital part of an ultrasonic flaw detector or an ultrasonic imaging system used for inspection of materials. The ultrasonic properties of the material and resolution requirements govern the choice of the frequency of ultrasound that can be optimally used. The pulser/receiver in turn decides the efficiency of excitation of the transducer and the overall signal to noise ratio of the system for best sensitivity and resolution. A variety of pulsers are used in the ultrasonic instruments employed for materials inspection. This report describes a square wave type of an ultrasonic pulser-receiver unit developed at Ultrasonic Instrumentation Section, Electronics Division, BARC. It has been primarily designed for excitation of the transducer that is used with a multi-channel ultrasonic imaging system ULTIMA 100M targeted for inspection of SS403 billets, which are in turn used as the base material for fabrication of end fittings for coolant channels of pressurized heavy water nuclear reactors (PHWRs). The design of the pulser is based upon very fast MOSFETs, configured as electronic switches. The pulser is operated with a linear bipolar H.V. supply (+/- 500V max.). The receiver provides a 60 dB gain with a -3 dB BW of 40 MHz. This pulser/receiver unit has been successfully interfaced with a 4 channel ULTIMA 100 M4 multichannel ultrasonic C-scan imaging system, also designed and developed by the authors at Ultrasonic Instrumentation Section (Electronics Division, BARC) and supplied to Centre for Design and Manufacturer - CDM, BARC. This system is being regularly used in C-scan imaging mode for volumetric inspection of SS403 billets for end fittings of 500 MWe PHWRs. (author)

Radiological safety experience in nuclear fuel cycle operations at Bhabha Atomic Research Center, Trombay, Mumbai, India

International Nuclear Information System (INIS)

Pushparaja; Gopalakrishnan, R.K.; Subramaniam, G.

2000-01-01

Activities at Bhabha Atomic Research Centre (BARC), Mumbai, cover nuclear fuel cycle operations based on natural uranium as the fuel. The facilities include: plant for purification and production of nuclear grade uranium metal, fuel fabrication, research reactor operation, fuel reprocessing and radioactive waste management in each stage. Comprehensive radiation protection programmes for assessment and monitoring of radiological impact of these operations, both in occupational and public environment, have been operating in BARC since beginning. These programmes, based on the 1990 ICRP Recommendations as prescribed by national regulatory body, the Atomic Energy Regulatory Board (AERB), are being successfully implemented by the Health, Safety and Environment Group, BARC. Radiation Hazards Control Units attached to the nuclear fuel cycle facilities provide radiation safety surveillance to the various operations. The radiation monitoring programme consists of measurement and control of external exposures by thermoluminescent dosimeters (TLDs), hand-held and installed instruments, and internal exposures by bioassay and direct whole body counting using shadow shield counter for beta gamma emitters and phoswich detector based system for plutonium. In addition, an environmental monitoring programme is in place to assess public exposures resulting from the operation of these facilities. The programme involves analysis of various matrices in the environment such as bay water, salt, fish, sediment and computation of resulting public exposures. Based on the operating experience in these plants, improved educating and training programmes for plant operators, have been designed. This, together with the application of new technologies have brought down individual as well as average doses of occupational workers. The environmental releases remain a small fraction of the authorised limits. The operating health physics experience in some of these facilities is discussed in this paper

Split-Hopkinson Pressure Bar: an experimental technique for high strain rate tests

International Nuclear Information System (INIS)

Sharma, S.; Chavan, V.M.; Agrawal, R.G.; Patel, R.J.; Kapoor, R.; Chakravartty, J.K.

2011-06-01

Mechanical properties of materials are, in general, strain rate dependent, i.e. they respond differently at quasi-static and higher strain rate condition. The Split-Hopkinson Pressure Bar (SHPB), also referred to as Kolsky bar is a commonly used setup for high strain rate testing. SHPB is suitable for high strain rate test in strain rate range of 10 2 to 10 4 s -1 . These high strain rate data are required for safety and structural integrity assessment of structures subjected to dynamic loading. As high strain rate data are not easily available in open literature need was felt for setting up such high strain rate testing machine. SHPB at BARC was designed and set-up inhouse jointly by Refuelling Technology Division and Mechanical Metallurgy Division, at Hall no. 3, BARC. A number of conceptual designs for SHPB were thought of and the optimized design was worked out. The challenges of precision tolerance, straightness in bars and design and proper functioning of pneumatic gun were met. This setup has been used extensively to study the high strain rate material behavior. This report introduces the SHPB in general and the setup at BARC in particular. The history of development of SHPB, the basic formulations of one dimensional wave propagation, the relations between the wave velocity, particle velocity and elastic strain in a one dimensional bar, and the equations used to obtain the final stress vs. strain curves are described. The calibration of the present setup, the pre-test calculations and the posttest analysis of data are described. Finally some of the experimental results on different materials such as Cu, SS305, SA516 and Zr, at room temperature and elevated temperatures are presented. (author)

7 CFR 924.17 - Container.

Science.gov (United States)

2010-01-01

... 7 Agriculture 8 2010-01-01 2010-01-01 false Container. 924.17 Section 924.17 Agriculture Regulations of the Department of Agriculture (Continued) AGRICULTURAL MARKETING SERVICE (Marketing Agreements... Container. Container means a box, bag, crate, lug, basket, carton, package, or any other type of receptacle...

7 CFR 920.14 - Container.

Science.gov (United States)

2010-01-01

... 7 Agriculture 8 2010-01-01 2010-01-01 false Container. 920.14 Section 920.14 Agriculture Regulations of the Department of Agriculture (Continued) AGRICULTURAL MARKETING SERVICE (Marketing Agreements... Definitions § 920.14 Container. Container means a box, bag, crate, lug, basket, carton, package, or any other...

Sensitivity of Landsat image-derived burn severity indices to immediate post-fire effects

Science.gov (United States)

A. T. Hudak; S. Lewis; P. Robichaud; P. Morgan; M. Bobbitt; L. Lentile; A. Smith; Z. Holden; J. Clark; R. McKinley

2006-01-01

The USFS Remote Sensing Applications Center (RSAC) and the USGS Center for Earth Resources Observation and Science (EROS) produce Burned Area Reflectance Classification (BARC) maps as a rapid, preliminary indication of burn severity on large wildfire events. Currently the preferred burn severity index is the delta Normalized Burn Ratio (dNBR), which requires NBR values...

Pramana – Journal of Physics | Indian Academy of Sciences

Indian Academy of Sciences (India)

BARC has developed large-area silicon detectors in collaboration with BEL to be used in the pre-shower detector of the CMS experiment at CERN. The use of floating guard rings (FGR) in improving breakdown voltage and reducing leakage current of silicon detectors is well-known. In the present work, it has been ...

Radioactive solid waste management at Trombay

International Nuclear Information System (INIS)

Jayaraman, A.P.; Balu, K.

1977-01-01

The Radioactive solid waste management programme at BARC, India during 1965-1975 is described in detail. The operational experience, which includes the handling treatment and disposal of these solid wastes is reported alongwith the special problems faced in the case of large volume low hazard potential wastes from the nuclear fuel cycle. (K.B.)

Fusion impulse containment

International Nuclear Information System (INIS)

Bohachevsky, I.O.

1979-01-01

The characteristics of impact fusion energy releases are not known sufficiently well to examine in detail specific containment vessel concepts or designs. Therefore it appears appropriate to formulate the impulse containment problem in general and to derive results in the form of explicit expressions from which magnitude estimates and parametric dependencies (trends) can be inferred conveniently and rapidly. In the following presentation we carry out this task using assumptions and approximations that are required to perform the analysis

Steel containment buckling

International Nuclear Information System (INIS)

Butler, T.A.; Baker, W.E.

1987-01-01

Two aspects of buckling of a free-standing nuclear containment building were investigated in a combined experimental and analytical program. In the first part of the study, the response of a scale model of a containment building to dynamic base excitation is investigated. A simple harmonic signal was used for preliminary studies followed by experiments with scaled earthquake signals as the excitation source. The experiments and accompanying analyses indicate that the scale model response to earthquake-type excitations is very complex and that current analytical methods may require that a dynamic capacity reduction factor be incorporated. The second part of the study quantified the effects of framing at large penetrations on the static buckling capacity of scale model containments. Results show little effect from the framing for the scale models constructed from the polycarbonate, Lexan. However, additional studies with a model constructed of the prototypic steel material are recommended. (orig.)

Steel containment buckling

International Nuclear Information System (INIS)

Butler, T.A.; Baker, W.E.

1986-01-01

Two aspects of buckling of a free-standing nuclear steel containment building were investigated in a combined experimental and analytical program. In the first part of the study, the response of a scale model of a containment building to dynamic base excitation is investigated. A simple harmonic signal was used for preliminary studies followed by experiments with scaled earthquake signals as the excitation source. The experiments and accompanying analyses indicate that the scale model response to earthquake-type excitations is very complex and that current analytical methods may require a dynamic capacity reduction factor to be incorporated. The second part of the study quantified the effects of framing at large penetrations on the static buckling capacity of scale model containments. Results show little effect from the framing for the scale models constructed from the polycarbonate, Lexan. However, additional studies with a model constructed of the prototypic steel material are suggested

CONTAIN calculations of direct containment heating in the Surry plant

International Nuclear Information System (INIS)

Williams, D.C.; Louie, D.L.Y.

1988-01-01

The draft NUREG-1150 risk analysis performed for the Surry plant identified direct containment heating (DCH) as a potentially dominant contributor to the total public risk associated with this plant. At that time, however, detailed mechanistic calculations of DCH loads were unavailable. Subsequently, a series of analyses of DCH scenarios using the CONTAIN-DCH code was performed in order to put the treatment of DCH on a firmer basis in the final draft of NUREG-1150. The present paper describes some of the results obtained for the Surry plant. A developmental model for DCH has been incorporated into CONTAIN code. This model includes mechanistic treatments of reasonably well-understood phenomena (e.g., heat and mass transfer), together with a parametric treatment of poorly understood phenomena for which mechanistic models are unavailable (e.g., debris de-entrainment from the gas stream due to debris-structure interactions). The DCH model was described in an earlier report, but the present version incorporates a number of advances, including treatment of the chemical equilibria involved in the iron-steam reaction

7 CFR 58.150 - Containers.

Science.gov (United States)

2010-01-01

... 7 Agriculture 3 2010-01-01 2010-01-01 false Containers. 58.150 Section 58.150 Agriculture... Identification § 58.150 Containers. (a) The size, style, and type of packaging used for dairy products shall be commercially acceptable containers and packaging materials which will satisfactorily cover and protect the...

27 CFR 28.143 - Containers.

Science.gov (United States)

2010-04-01

... 27 Alcohol, Tobacco Products and Firearms 1 2010-04-01 2010-04-01 false Containers. 28.143 Section....143 Containers. (a) Beer. Beer being exported, used as supplies on vessels and aircraft, or..., or bulk containers. (b) Beer concentrate. Concentrate may not be removed for export, or for transfer...

7 CFR 958.17 - Container.

Science.gov (United States)

2010-01-01

... 7 Agriculture 8 2010-01-01 2010-01-01 false Container. 958.17 Section 958.17 Agriculture... COUNTIES IN IDAHO, AND MALHEUR COUNTY, OREGON Order Regulating Handling Definitions § 958.17 Container. Container means a sack, box, bag, crate, hamper, basket, carton, package, or any other type of receptacle...

FFTF-containment air-cleaning system

International Nuclear Information System (INIS)

Mahaffey, M.K.; Stepnewski, D.D.

1981-01-01

The FFTF Containment can accommodate all design basis events and the hypothetical core disruptive accident with adequate margin without a venting or purging system; however, in concert with the development objective, a system was designed and constructed to evaluate technology related to containment atmosphere venting and cleanup functions. The system can be used to purge high H 2 concentrations or to vent excessive containment pressure. In either case containment atmosphere is exhausted through an aqueous scrubber system consisting of a venturi scrubber and fibrous filter bank

Development of a short sample test facility for evaluating superconducting wires

International Nuclear Information System (INIS)

Singh, M.R.; Kulkarni, D.G.; Sahni, V.C.; Ravikumar, G.; Patel, K.L.

2002-01-01

In this paper we describe a short sample test facility we have set up at Bhabha Atomic Research Centre (BARC). This facility has been used to measure critical currents of NbTi/Cu composite superconducting wires by recording V versus I data at 4.2 K. It offers sample current as large as 1500 A and a transverse magnetic field up to 7.4 T. A power law, V ∼I n( H) is fitted to the resistive transition region to estimate the exponent n, which is a measure of the uniformity of superconducting filaments in composite wires. It is observed that inadequate thermal stabilization of sample wire results in thermal runaway, which limits the V-I data to∼ 2μ V . This in turn affects the reliability of estimated filament uniformity. To mitigate this problem, we have used a sample holder made of OFHC-Cu which enhances thermal stabilization of the sample. With this sample holder, the results of measurements carried out on wires developed by the Atomic Fuel Division, BARC show a high filament uniformity (n ∼ 58). (author)

Draft report on the national seminar in nuclear medicine

International Nuclear Information System (INIS)

1977-01-01

The proceedings of the seminar on nuclear medicine have been conducted in four main sessions. In the first session a review of the current status of clinical nuclear medicine in India is reviewed. The use of radioisotopes in thyroid function studies, central nervous systems, liver disorders, lung and bone imaging, renal function studies, dynamic function studies, gastroenterology haematology etc. are described. The existing facilities and the future needs for radioimmunoassay and radiotherapy are discussed. In Session 2, the existing facilities in nuclear medicine in different states in India are reviewed. In Session 3, the available resources in nuclear medicine are reviewed. Radiation protection procedures are outlined. Various nuclear instruments developed at the Bhabha Atomic Research Centre, (BARC), Bombay, for use in nuclear medicine are briefly described. A list of radiopharmaceuticals developed by BARC and in current use, is given. The roles of the physicist, pharmacist and the nuclear medicine technologist in the hospitals having nuclear medicine units, are stressed. The importance of training and education for personnel in nuclear medicine and medical physics is pointed out. (A.K.)

Assembly and Characterization of Resistive Plate Chambers in India for the CMS Detector

CERN Document Server

AUTHOR|(CDS)2084269

2016-01-01

The Compact Muon Solenoid (CMS) experiment is a general purpose detector being operated at Large Hadron Collider (LHC) facility at CERN. The RE4 upgrade project was envisaged to improve the Level-1 trigger efficiency in the forward region, when LHC would run at its full designed energy and luminosity after the first Long Shutdown (LS-1, 2013-2014). About 200 RPCs were built for the upgrade at three assembly sites in India, CERN and Ghent. India contributed to 50, RE4/2 RPCs along with 200 Cu-cooling units for the entire upgrade for which the assembly and characterization of RPCs was carried out jointly by Nuclear Physics Division-BARC and Panjab University-Chandigarh. The gas-gaps after their arrival from KODEL, South Korea, underwent mechanical tests for leak and popped spacers, followed by electrical tests for long term monitoring of leakage currents. After the assembly, each RPC was evaluated for its efficiency, cluster size, noise and strip profiles. The Cu-cooling units build at BARC were also tested acc...

Containment integrity analysis under accidents

International Nuclear Information System (INIS)

Lin Chengge; Zhao Ruichang; Liu Zhitao

2010-01-01

Containment integrity analyses for current nuclear power plants (NPPs) mainly focus on the internal pressure caused by design basis accidents (DBAs). In addition to the analyses of containment pressure response caused by DBAs, the behavior of containment during severe accidents (SAs) are also evaluated for AP1000 NPP. Since the conservatism remains in the assumptions,boundary conditions and codes, margin of the results of containment integrity analyses may be overestimated. Along with the improvements of the knowledge to the phenomena and process of relevant accidents, the margin overrated can be appropriately reduced by using the best estimate codes combined with the uncertainty methods, which could be beneficial to the containment design and construction of large passive plants (LPP) in China. (authors)

Helical type vacuum container

International Nuclear Information System (INIS)

Owada, Kimio.

1989-01-01

Helical type vacuum containers in the prior art lack in considerations for thermal expansion stresses to helical coils, and there is a possibility of coil ruptures. The object of the present invention is to avoid the rupture of helical coils wound around the outer surface of a vacuum container against heat expansion if any. That is, bellows or heat expansion absorbing means are disposed to a cross section of a helical type vacuum container. With such a constitution, thermal expansion of helical coils per se due to temperature elevation of the coils during electric supply can be absorbed by expansion of the bellows or absorption of the heat expansion absorbing means. Further, this can be attained by arranging shear pins in the direction perpendicular to the bellows axis so that the bellows are not distorted when the helical coils are wound around the helical type vacuum container. (I.S.)

27 CFR 28.94 - Containers.

Science.gov (United States)

2010-04-01

... 27 Alcohol, Tobacco Products and Firearms 1 2010-04-01 2010-04-01 false Containers. 28.94 Section... Manufacturing Bonded Warehouse § 28.94 Containers. Distilled spirits authorized to be withdrawn without payment... be withdrawn from such establishment in such containers as may be authorized in part 19 of this...

T25 Qualification of old containers

International Nuclear Information System (INIS)

Hoerning, T.; Kasparek, E.M.; Voelzke, H.

2013-01-01

Radioactive waste for final disposal in the repository Konrad has to be packaged in licensed containers. The qualification of containers is performed according the respective standards and BfS requirements. The latter ones differ for different container types with respect to accident resistance based on the release behavior of the waste. Usually qualification of container types is performed before series production. The qualification of already produced containers (''old containers'') is significantly more complicated. The differences of quality assurance and materials properties of the older containers have to be evaluated. A main tool for this evaluation is the numerical re-calculation of accident scenarios for estimation of the safety margins. The validation of appropriate finite element models is available. Based on these date it might be possible to abandon additional drop tests with the existing old containers to prove the structural integrity.

Identification and assessment of containment and release management strategies for a BWR Mark II containment

International Nuclear Information System (INIS)

Lin, C.C.; Lehner, J.R.

1992-06-01

Accident management strategies that have the potential to maintain containment integrity and control or mitigate the release of radioactivity following a severe accident at a boiling water reactor with a Mark 2 type of containment are identified and evaluated. The strategies are referred to as containment and release strategies. Using information available from probabilistic risk assessments and other existing severe accident research, and employing simplified containment and release event trees, this report identified the challenges a Mark 2 containment may encounter during a severe accident, the mechanisms behind these challenges, and the strategies that could be used to mitigate the challenge. By means of a safety objective tree, the strategies are linked to the general safety objectives of containment and release management. As part of the assessment process, the strategies are applied to certain severe accident sequence categories deemed important to a Mark 2 containment. These sequence categories exhibit one or more of the following characteristics: high probability of core damage, high consequences, lead to a number of challenges, and involve the failure of multiple systems. The Limerick Generating Station is used as a representative Mark 2 plant to illustrate plant specifics in this report

Container corporation: The financial, management, and operating implications of a universal beverage container recovery system: Executive summary

Energy Technology Data Exchange (ETDEWEB)

1991-01-01

This report contains an overview of the system. It discusses containers and container materials, elements of the system, and the container recovery cost structure. It includes a financial evaluation and addresses issues of implementation.

International Containment Technology Conference: Proceedings

International Nuclear Information System (INIS)

1997-01-01

This document contains the manuscripts of the papers and posters presented at the 1997 International Containment Technology Conference and Exhibition. These manuscripts represent a valuable compilation of information and data on the environmental challenges and technology-based solutions associated with containment technologies. The purpose of the conference was to promote the advancement of containment technologies by providing a forum from which participants from related disciplines could meet to exchange ideas and information on recent developments. Selected papers were indexed separately for inclusion in the Energy Science and Technology Database

Container for nuclear fuel powders

International Nuclear Information System (INIS)

Etheredge, B.F.; Larson, R.I.

1982-01-01

A critically safe container is disclosed for the storage and rapid discharge of enriched nuclear fuel material in powder form is disclosed. The container has a hollow, slab-shaped container body that has one critically safe dimension. A powder inlet is provided on one side wall of the body adjacent to a corner thereof and a powder discharge port is provided at another corner of the body approximately diagonal the powder inlet. Gas plenum for moving the powder during discharge are located along the side walls of the container adjacent the discharge port

Identification and assessment of containment and release management strategies for a BWR Mark III containment

International Nuclear Information System (INIS)

Lin, C.C.; Lehner, J.R.; Vandenkieboom, J.J.

1992-02-01

This report identifies and assesses accident management strategies which could be important for preventing containment failure and/or mitigating the release of fission products during a severe accident in a BWR plant with a Mark III type of containment. Based on information available from probabilistic risk assessments and other existing severe accident research, and using simplified containment and release event trees, the report identifies the challenges a Mark III containment could face during the course of a severe accident, the mechanisms behind these challenges, and the strategies that could be used to mitigate the challenges. The strategies are linked to the general safety objectives which apply for containment and release management by means of a safety objective tree. The strategies were assessed by applying them to certain severe accident sequence categories deemed important for a Mark III containment because of one or more of the following characteristics: high probability of core damage, high consequences, lead to a number of challenges, and involve the failure of multiple systems

Containment bellows testing under extreme loads

International Nuclear Information System (INIS)

Splezter, B.L.; Lambert, L.D.; Parks, M.B.

1993-01-01

Sandia National Laboratories (SNL) is conducting several research programs to help develop validated methods for the prediction of the ultimate pressure capacity, at elevated temperatures, of light water reactor (LWR) containment structures. To help understand the ultimate pressure of the entire containment pressure boundary, each component must be evaluated. The containment pressure boundary consists of the containment shell and many access, piping, and electrical penetrations. The focus of the current research program is to study the ultimate behavior of flexible metal bellows that are used at piping penetrations. Bellows are commonly used at piping penetrations in steel containments; however, they have very few applications in concrete (reinforced or prestressed) containments. The purpose of piping bellows is to provide a soft connection between the containment shell and the pipe are attached while maintaining the containment pressure boundary. In this way, piping loads caused by differential movement between the piping and the containment shell are minimized. SNL is conducting a test program to determine the leaktight capacity of containment bellows when subjected to postulated severe accident conditions. If the test results indicate that containment bellows could be a possible failure mode of the containment pressure boundary, then methods will be developed to predict the deformation, pressure, and temperature conditions that would likely cause a bellows failure. Results from the test program would be used to validate the prediction methods. This paper provides a description of the use and design of bellows in containment piping penetrations, the types of possible bellows loadings during a severe accident, and an overview of the test program, including available test results at the time of writing

Passive heat removal from containment

International Nuclear Information System (INIS)

Gou, P.F.; Townsend, H.E.

1990-01-01

This patent describes a heat removal system for removing heat from a containment of a nuclear reactor. It comprises: a sealed suppression chamber in the containment; means for venting steam from the nuclear reactor into the suppression chamber upon occurrence of an event requiring dissipation of heat from the nuclear reactor. The suppression chamber containing a quantity of water; the suppression chamber having a gas-containing space above the water; a heat exchanger disposed within the gas-containing space of the suppression chamber; the heat exchanger including an enclosed structure for holding a heat-exchange fluid; means for metering a supply of heat-exchange fluid to the heat exchanger to maintain a predetermined level thereof in the enclosed structure. The heat-exchange fluid boiling in the heat exchanger in consequence of heat transfer thereto from steam present in the suppression chamber; means for separating a heat-exchange fluid vapor in the heat exchanger from the heat-exchange fluid; and means for discharging the vapor immediately following its separation from heat-exchange fluid directly from the heat exchanger to a location exterior of the containment, whereby heat is discharged from the suppression chamber, and the containment is maintained at a temperature and pressure below its design value

Rapid Sampling from Sealed Containers

International Nuclear Information System (INIS)

Johnston, R.G.; Garcia, A.R.E.; Martinez, R.K.; Baca, E.T.

1999-01-01

The authors have developed several different types of tools for sampling from sealed containers. These tools allow the user to rapidly drill into a closed container, extract a sample of its contents (gas, liquid, or free-flowing powder), and permanently reseal the point of entry. This is accomplished without exposing the user or the environment to the container contents, even while drilling. The entire process is completed in less than 15 seconds for a 55 gallon drum. Almost any kind of container can be sampled (regardless of the materials) with wall thicknesses up to 1.3 cm and internal pressures up to 8 atm. Samples can be taken from the top, sides, or bottom of a container. The sampling tools are inexpensive, small, and easy to use. They work with any battery-powered hand drill. This allows considerable safety, speed, flexibility, and maneuverability. The tools also permit the user to rapidly attach plumbing, a pressure relief valve, alarms, or other instrumentation to a container. Possible applications include drum venting, liquid transfer, container flushing, waste characterization, monitoring, sampling for archival or quality control purposes, emergency sampling by rapid response teams, counter-terrorism, non-proliferation and treaty verification, and use by law enforcement personnel during drug or environmental raids

The Container Stowage Problem

DEFF Research Database (Denmark)

Janstrup, Kira; Rose, Trine Høyer; Andersen, Kent Høj

The main purpose of this project is to use integer programming to create a model that minimizes the costs for container transportation by ship. To make the model as realistic as possible it will be based on information from a large shipping company about the vessel layout and container types....... In addition to our project two other projects are made where an optimal solution to the container stowage problem also is tried to be found, but by using constraint programming and local search instead respectively. We will therefore in the end compare these three methods and the achieved results on fastness...

The Container Stowage Problem

DEFF Research Database (Denmark)

Janstrup, Kira

2010-01-01

The main purpose of this project is to use integer programming to create a model that minimizes the costs for container transportation by ship. To make the model as realistic as possible it will be based on information from a large shipping company about the vessel layout and container types....... In addition to our project two other projects are made where an optimal solution to the container stowage problem also is tried to be found, but by using constraint programming and local search instead respectively. We will therefore in the end compare these three methods and the achieved results on fastness...

Alternatives for high-level waste forms, containers, and container processing systems

International Nuclear Information System (INIS)

Crawford, T.W.

1995-01-01

This study evaluates alternatives for high-level waste forms, containers, container processing systems, and onsite interim storage. Glass waste forms considered are cullet, marbles, gems, and monolithic glass. Small and large containers configured with several combinations of overpack confinement and shield casks are evaluated for these waste forms. Onsite interim storage concepts including canister storage building, bore holes, and storage pad were configured with various glass forms and canister alternatives. All favorable options include the monolithic glass production process as the waste form. Of the favorable options the unshielded 4- and 7-canister overpack options have the greatest technical assurance associated with their design concepts due to their process packaging and storage methods. These canisters are 0.68 m and 0.54 m in diameter respectively and 4.57 m tall. Life-cycle costs are not a discriminating factor in most cases, varying typically less than 15 percent

Reactor container

International Nuclear Information System (INIS)

Furukawa, Hideyasu; Oyamada, Osamu; Uozumi, Hiroto.

1976-01-01

Purpose: To provide a container for a reactor provided with a pressure suppressing chamber pool which can prevent bubble vibrating load, particularly negative pressure generated at the time of starting to release exhaust from a main steam escape-safety valve from being transmitted to a lower liner plate of the container. Constitution: This arrangement is characterized in that a safety valve exhaust pool for main steam escape, in which a pressure suppressing chamber pool is separated and intercepted from pool water in the pressure suppressing chamber pool, a safety valve exhaust pipe is open into said safety valve exhaust pool, and an isolator member, which isolates the bottom liner plate in the pressure suppressing chamber pool from the pool water, is disposed on the bottom of the safety valve exhaust pool. (Nakamura, S.)

27 CFR 27.121 - Containers.

Science.gov (United States)

2010-04-01

... 27 Alcohol, Tobacco Products and Firearms 1 2010-04-01 2010-04-01 false Containers. 27.121 Section... Spirits In Bulk § 27.121 Containers. Imported distilled spirits may be bottled in either domestic or imported containers conforming to the provisions of subpart N of this part. (72 Stat. 1374; 26 U.S.C. 5301...

Glove boxes and similar containments

International Nuclear Information System (INIS)

Anon.

1975-01-01

According to the present invention a glove box or similar containment is provided with an exhaust system including a vortex amplifier venting into the system, the vortex amplifier also having its main inlet in fluid flow connection with the containment and a control inlet in fluid flow connection with the atmosphere outside the containment. (U.S.)

7 CFR 987.48 - Container regulation.

Science.gov (United States)

2010-01-01

... 7 Agriculture 8 2010-01-01 2010-01-01 false Container regulation. 987.48 Section 987.48... IN RIVERSIDE COUNTY, CALIFORNIA Order Regulating Handling Container Regulation § 987.48 Container regulation. Whenever the Committee deems it advisable to establish a container regulation for any variety of...

7 CFR 922.110 - Container exemption.

Science.gov (United States)

2010-01-01

... 7 Agriculture 8 2010-01-01 2010-01-01 false Container exemption. 922.110 Section 922.110... COUNTIES IN WASHINGTON Container Exemption; Waivers of Inspection and Certification § 922.110 Container exemption. Whenever container limitations are effective pursuant to § 922.52, a handler may make test...

Temperature effects on the structure of liquid D-methanol through ...

Indian Academy of Sciences (India)

Here, the liquid consists of deuterated methanol and neutron data was collected on the high- diffractometer at Dhruva, BARC. The corrected data at elevated temperatures (BP (boiling point) and double the BP) show that there is a large change in the H-bonded structure of this liquid. The pre-peak or hump, known to be ...

The relationship of multispectral satellite imagery to immediate fire effects

Science.gov (United States)

Andrew T. Hudak; Penelope Morgan; Michael J. Bobbitt; Allstair M. S. Smith; Sarah A. Lewis; Leigh B. Lentile; Peter R. Robichaud; Jess T. Clark; Randy A. McKinley

2007-01-01

The Forest Service Remote Sensing Applications Center (RSAC) and the U.S. Geological Survey Earth Resources Observation and Science (EROS) Data Center produce Burned Area Reflectance Classification (BARC) maps for use by Burned Area Emergency Response (BAER) teams in rapid response to wildfires. BAER teams desire maps indicative of fire effects on soils, but green and...

Online Decision Support System (IRODOS) - an emergency preparedness tool for handling offsite nuclear emergency

International Nuclear Information System (INIS)

Vinod Kumar, A.; Oza, R.B.; Chaudhury, P.; Suri, M.; Saindane, S.; Singh, K.D.; Bhargava, P.; Sharma, V.K.

2009-01-01

A real time online decision support system as a nuclear emergency response system for handling offsite nuclear emergency at the Nuclear Power Plants (NPPs) has been developed by Health, Safety and Environment Group, Bhabha Atomic Research Centre (BARC), Department of Atomic Energy (DAE) under the frame work of 'Indian Real time Online Decision Support System 'IRODOS'. (author)

Neutron and X-ray facilities in new Purnima extension building

International Nuclear Information System (INIS)

Sarkar, P.S.; Patel, Tarun; Gadkari, S.C.

2017-01-01

Neutron and X-ray Physics Section of Technical Physics Division has laboratories involving X-ray, gamma ray and neutrons in the New Purnima Extension Building (NPEB), behind Purnima Laboratories, BARC. Research activities related to X-ray, Gamma and neutron based detection and imaging for societal, departmental and security applications are being carried out in these laboratories

Pramana – Journal of Physics | Indian Academy of Sciences

Indian Academy of Sciences (India)

The folded tandem ion accelerator (FOTIA) project at BARC has been commissioned. The analysed carbon beams of 40 nA(3+) and 25 nA(4+), at terminal voltage of 2.5 MV with N2 + CO2 as insulating gas, were obtained. The beams were characterized by performing the Rutherford back scattering (RBS) on gold, tin and ...

Fusion cross sections for 6,7Li + 24Mg at energies around the barrier

International Nuclear Information System (INIS)

Ray, Maitreyi; Pradhan, M.K.; Kshetri, R.; Mukherjee, A.; Saha Sarkar, M.; Biswas, M.; Roy, S.; Basu, P.; Majumdar, H.; Dasmahapatra, B.; Sinha, M.; Palit, R.; Mazumdar, I.; Joshi, P.K.; Jain, H.C.

2006-01-01

The 6,7 Li + 24 Mg reactions in the energy interval E lab = 11-32 MeV using 6,7 Li beams have been investigated from the 14 UD BARC-TIFR Pelletron accelerator at TIFR, Mumbai. The γ-ray cross sections were measured using a Compton suppressed clover detector, placed at 55 deg with respect to the beam direction

Untitled

Indian Academy of Sciences (India)

of practically all uranium ores in the world attempts to beneficiate the low-grade ores (0.4–1.0 kg U3Os per ton) have been unsuccessful. However, some of the investigations by the Ore Dressing Laboratories of BARC on the recovery of uranium as a byproduct from the tailings of copper concentration plants and on the.

76 FR 51367 - China Shipping Container Lines Co., Ltd.; COSCO Container Lines Company Limited; Evergreen Line A...

Science.gov (United States)

2011-08-18

... FEDERAL MARITIME COMMISSION [Docket No. 11-12] China Shipping Container Lines Co., Ltd.; COSCO Container Lines Company Limited; Evergreen Line A Joint Service Agreement; Hanjin Shipping Co., Ltd... Maritime Commission (Commission) by China Shipping Container Lines Co., Ltd.; COSCO Container Lines Company...

Self-folding micropatterned polymeric containers.

Science.gov (United States)

Azam, Anum; Laflin, Kate E; Jamal, Mustapha; Fernandes, Rohan; Gracias, David H

2011-02-01

We demonstrate self-folding of precisely patterned, optically transparent, all-polymeric containers and describe their utility in mammalian cell and microorganism encapsulation and culture. The polyhedral containers, with SU-8 faces and biodegradable polycaprolactone (PCL) hinges, spontaneously assembled on heating. Self-folding was driven by a minimization of surface area of the liquefying PCL hinges within lithographically patterned two-dimensional (2D) templates. The strategy allowed for the fabrication of containers with variable polyhedral shapes, sizes and precisely defined porosities in all three dimensions. We provide proof-of-concept for the use of these polymeric containers as encapsulants for beads, chemicals, mammalian cells and bacteria. We also compare accelerated hinge degradation rates in alkaline solutions of varying pH. These optically transparent containers resemble three-dimensional (3D) micro-Petri dishes and can be utilized to sustain, monitor and deliver living biological components.

46 CFR 160.026-3 - Container.

Science.gov (United States)

2010-10-01

... 46 Shipping 6 2010-10-01 2010-10-01 false Container. 160.026-3 Section 160.026-3 Shipping COAST...: SPECIFICATIONS AND APPROVAL LIFESAVING EQUIPMENT Water, Emergency Drinking (In Hermetically Sealed Containers), for Merchant Vessels § 160.026-3 Container. (a) General. The emergency drinking water container shall...

MgAl2O4 spinel refractory as containment liner for high-temperature alkali salt containing environments

Science.gov (United States)

Peascoe-Meisner, Roberta A [Knoxville, TN; Keiser, James R [Oak Ridge, TN; Hemric, James G [Knoxville, TN; Hubbard, Camden R [Oak Ridge, TN; Gorog, J Peter [Kent, WA; Gupta, Amul [Jamestown, NY

2008-10-21

A method includes containing a high-temperature alkali salt containing environment using a refractory containment liner containing MgAl.sub.2O.sub.4 spinel. A method, includes forming a refractory brick containing MgAl.sub.2O.sub.4 spinel having an exterior chill zone defined by substantially columnar crystallization and an interior zone defined by substantially equiaxed crystallization; and removing at least a portion of the exterior chill zone from the refractory brick containing MgAl.sub.2O.sub.4 spinel by scalping the refractory brick containing MgAl.sub.2O.sub.4 spinel to define at least one outer surface having an area of substantially equiaxed crystallization. A product of manufacture includes a refractory brick containing MgAl.sub.2O.sub.4 spinel including an interior zone defined by substantially equiaxed crystallization; and at least one outer surface having an area of substantially equiaxed crystallization.

Emergency reactor container cooling facility

International Nuclear Information System (INIS)

Suzuki, Hiroaki; Matsumoto, Tomoyuki.

1992-01-01

The present invention concerns an emergency cooling facility for a nuclear reactor container having a pressure suppression chamber, in which water in the suppression chamber is effectively used for cooling the reactor container. That is, the lower portion of a water pool in the pressure suppression chamber and the inside of the reactor container are connected by a pipeline. The lower end of the pipeline and a pressurized incombustible gas tank disposed to the outside of the reactor container are connected by a pipeline by way of valves. Then, when the temperature of the lower end of the pressure vessel exceeds a predetermined value, the valves are opened. If the valves are opened, the incombustible gas flows into the lower end of the pipeline connecting the lower portion of the water pool in the pressure suppression chamber and the inside of the reactor container. Since the inside of the pipeline is a two phase flow comprising a mixture of a gas phase and a liquid phase, the average density is decreased. Therefore, the water level of the two phase flow is risen by the level difference between the inside and the outside of the pipeline and, finally, the two phase mixture is released into the reactor container. As a result, the reactor container can be cooled by water in the suppression chamber by a static means without requiring pumps. (I.S.)

Performance of containment of Indian PHWR

International Nuclear Information System (INIS)

Mohan, Nalini; Ghadge, S.G.; Bajaj, S.S.

2006-01-01

This paper summarizes the various requirements and activities relevant to the testing of containment system of Indian Pressurized Heavy Water Reactor (PHWR). All Indian PHWR containments are constructed from concrete either reinforced or prestressed or a combination of both and lined with polymeric coating based on Epoxy or Vinyl in order to achieve the leak tightness necessary from the radiological considerations following an accident. The current concept includes a complete double containment (except the base raft) extended to all penetrations and some of the pipings (those open to the containment atmosphere). The primary containment fitted with a passive pressure suppression system is enveloped in the secondary containment (confinement) where slight vacuum is maintained during normal operation as well as post accident condition. The Integrated leakage Rate Test (ILRT) conducted so far on the containment indicate that the overall leakages from the containment are lower than those necessary to meet the radiological limits following a postulated accident and interception of leakages by secondary containment as per design. The details of the, tests, repairs carried out and observations are given in this paper. The experience of ILRT also indicate improvement in leak tightness in many areas. (author)

Performance of Sequoyah Containment Anchorage System

International Nuclear Information System (INIS)

Fanous, F.; Greimann, L.; Wassef, W.; Bluhm, D.

1993-01-01

Deformation of a steel containment anchorage system during a severe accident may result in a leakage path at the containment boundaries. Current design criteria are based on either ductile or brittle failure modes of headed bolts that do not account for factors such as cracking of the containment basemat or deformation of the anchor bolt that may affect the behavior of the containment anchorage system. The purpose of this study was to investigate the performance of a typical ice condenser containment's anchorage system. This was accomplished by analyzing the Sequoyah Containment Anchorage System. Based on a strength of materials approach and assuming that the anchor bolts are resisting the uplift caused by the internal pressure, one can estimate that the failure of the anchor bolts would occur at a containment pressure of 79 psig. To verify these results and to calibrate the strength of materials equation, the Sequoyah containment anchorage system was analyzed with the ABAQUS program using a three-dimensional, finite-element model. The model included portions of the steel containment building, shield building, anchor bolt assembly, reinforced concrete mat and soil foundation material

Shielded transport containers for reactor waste

International Nuclear Information System (INIS)

Grundfelt, B.; Eriksson, E.

The report presents that part of risk analysis which deals with the frequency of breakdowns and the damage on containers. The report focusses on shielded containers made of reinforced concrete. Also a container made of steel is referred to the cases of breakdown are closely allied to collisions with ships. The frequency of breakdowns which might damage the containers is low in all respects, namely 1.10 -5 per year or lower for the shielded container. (G.B.)

Radioactive materials transporting container and vehicles

International Nuclear Information System (INIS)

Reese, S.L.

1980-01-01

A container and vehicle therefor for transporting radioactive materials is provided. The container utilizes a removable system of heat conducting fins made of a light weight highly heat conductive metal, such as aluminum or aluminum alloys. This permits a substantial reduction in the weight of the container during transport, increases the heat dissipation capability of the container and substantially reduces the scrubbing operation after loading and before unloading the radioactive material from the container. The vehicle utilizes only a pair of horizontal side beams interconnecting a pair of yoke members to support the container and provide the necessary strength and safety with a minimum of weight

Gross Containment Leakage Monitoring System (GCLM) applied to accidental impairment of containment integrity determination

International Nuclear Information System (INIS)

Dinu, Camelia; Talpalariu, A.; Constantinescu, G.

2007-01-01

The Prioritization of Generic Safety Issues (NUREG-0933 of October 2006), section 1 task II.E.4 item II.E.4.3 recommends that a method of periodic or continuous testing has to be available, in order to detect unknown gross openings in the nuclear power plants containment structure. The Palisades incident and three other incidents are exemplified, when the reactor was operated for about 1.5 years, while the containment isolation valves in a purge system bypass line were unknowingly locked in the open position. It was estimated that the presence of a GCLM system could identify an unknown breach and reduce the expected unavailability of containment due to containment integrity breach events, to a 1.6x10 -3 /year demand. (authors)

27 CFR 44.187 - Shipping containers.

Science.gov (United States)

2010-04-01

... 27 Alcohol, Tobacco Products and Firearms 2 2010-04-01 2010-04-01 false Shipping containers. 44... Shipping containers. Each shipping case, crate, or other container in which tobacco products, or cigarette... same containers in which they were received from the factory. (72 Stat. 1418, as amended; 26 U.S.C...

Gas-gun facility for shock wave research at BARC

International Nuclear Information System (INIS)

Gupta, S.C.; Jyoti, G.; Suresh, N.; Sikka, S.K.; Chidambaram, R.; Agarwal, R.G.; Roy, S.; Kakodkar, A.

1995-01-01

For carrying out shock-wave experiments on materials, we have built a 63 mm diameter gas-gun facility at our laboratory. It is capable of accelerating projectiles (about half kg in weight) to velocities up to 1 km/s using N 2 and He gases. These on impacting a target generate shock pressures up to 40 GPa, depending upon the impedance of the impactor and the target. The barrel of the gun is slotted so that a keyed projectile can be fired for combined compression- shear studies. Large samples can be shocked (about 60 mm diameter and 5-10 mm thick), with pressures lasting for a few microseconds. The gun is similar in design to the one at Washington State University. A number of diagnostic techniques have also been developed. These include measurement of projectile velocity, tilt between the impactor and the target, shock velocity in the target, and time resolved in-material stress wave histories in the shock loaded samples. Recovery capsules have also been made to retrieve shocked samples on unloading, which are then analysed using microscopic techniques like x-ray diffraction, Raman and electron microscopy. The gun has been performing well and has already been used for a few phase transition studies. (author). 73 refs., 42 figs

Radiation monitoring methodologies and their applications at BARC site

International Nuclear Information System (INIS)

Divkar, J.K.; Chatterjee, M.K.; Patra, R.P; Morali, S.; Singh, Rajvir

2016-01-01

Radiation monitoring methodology can be planned for various objectives during normal as well as emergency situations. During radiological emergency, radiation monitoring data provides useful information required for management of the abnormal situation. In order to assess the possible consequences accurately and to implement adequate measure, the emergency management authorities should have a well-prepared monitoring strategy in readiness. Fixed monitoring method is useful to analyze the behavior of nuclear plant site and to develop holistic model for it mobile monitoring is useful for quick impact assessment and will be the backbone of emergency response, particularly in case of non availability of fixed monitoring system caused due to natural disaster like floods, earthquake and tsunami

Accelerator mass spectrometry programme at BARC-TIFR pelletron accelerator

International Nuclear Information System (INIS)

Surendran, P.; Shrivastava, A.; Gupta, A.K.; Nair, J.P.; Yadav, M.L.; Gore, J.A.; Sparrow, H.; Bhagwat, P.V.; Kailas, S.

2006-01-01

Accelerator based mass spectrometry (ABMs) is an ultra sensitive means of counting individual atoms having sufficiently long half life and available in small amount. The 14 U D Pelletron Accelerator is an ideal machine to carry out ABMs studies with heavy isotopes like 36 Cl and 129 I. Cosmogenic radio isotope 36 Cl is widely being detected using ABMs as it has got applications in ground water research, radioactive waste management, atmospheric 36 Cl transport mechanism studies of Arctic Alpine ice core etc. As a part of the ongoing ABMs programme at 14UD Pelletron Accelerator Facility at Mumbai, a segmented gas detector developed for identification of 36 Cl was tested for performance. Recently a beam chopper required for this measurement has been developed. Further progress made in this programme is discussed in this paper. (author)

21 CFR 1230.47 - Rejected containers.

Science.gov (United States)

2010-04-01

... 21 Food and Drugs 8 2010-04-01 2010-04-01 false Rejected containers. 1230.47 Section 1230.47 Food... FEDERAL CAUSTIC POISON ACT Imports § 1230.47 Rejected containers. (a) In all cases where the containers... notification to the importer that the containers must be exported under customs supervision within 3 months...

7 CFR 58.729 - Forming containers.

Science.gov (United States)

2010-01-01

... 7 Agriculture 3 2010-01-01 2010-01-01 false Forming containers. 58.729 Section 58.729 Agriculture... Procedures § 58.729 Forming containers. Containers either lined or unlined shall be assembled and stored in a sanitary manner to prevent contamination. The handling of containers by filler crews should be done with...

Integrated analysis of core debris interactions and their effects on containment integrity using the CONTAIN computer code

International Nuclear Information System (INIS)

Carroll, D.E.; Bergeron, K.D.; Williams, D.C.; Tills, J.L.; Valdez, G.D.

1987-01-01

The CONTAIN computer code includes a versatile system of phenomenological models for analyzing the physical, chemical and radiological conditions inside the containment building during severe reactor accidents. Important contributors to these conditions are the interactions which may occur between released corium and cavity concrete. The phenomena associated with interactions between ejected corium debris and the containment atmosphere (Direct Containment Heating or DCH) also pose a potential threat to containment integrity. In this paper, we describe recent enhancements of the CONTAIN code which allow an integrated analysis of these effects in the presence of other mitigating or aggravating physical processes. In particular, the recent inclusion of the CORCON and VANESA models is described and a calculation example presented. With this capability CONTAIN can model core-concrete interactions occurring simultaneously in multiple compartments and can couple the aerosols thereby generated to the mechanistic description of all atmospheric aerosol components. Also discussed are some recent results of modeling the phenomena involved in Direct Containment Heating. (orig.)

Containment and surveillance devices

International Nuclear Information System (INIS)

Campbell, J.W.; Johnson, C.S.; Stieff, L.R.

The growing acceptance of containment and surveillance as a means to increase safeguards effectiveness has provided impetus to the development of improved surveillance and containment devices. Five recently developed devices are described. The devices include one photographic and two television surveillance systems and two high security seals that can be verified while installed

Transient shielded liquid hydrogen containers

International Nuclear Information System (INIS)

Varghese, A.P.; Herring, R.H.

1990-01-01

The storage of hydrogen in the liquid phase has been limited in duration due to the thermal performance constraints of conventional Liquid Hydrogen containers available. Conventional Liquid Hydrogen containers lose hydrogen because of their relatively high heat leak and variations in usage pattern of hydrogen due to shutdowns. Local regulations also discourage venting of hydrogen. Long term storage of Liquid Hydrogen without product loss was usually accomplished using Liquid Nitrogen sacrificial shields. This paper reports on a new low heat leak container developed and patented that will extend the storage time of liquid hydrogen by five hundred percent. The principle of operation of the Transient Shields which makes the extraordinary performance of this container feasible is described in this paper. Also covered are the impact of this new container on present applications of hydrogen and the new opportunities afforded to Liquid hydrogen in the world hydrogen market

Authenticated Secure Container System (ASCS)

International Nuclear Information System (INIS)

1991-01-01

Sandia National Laboratories developed an Authenticated Secure Container System (ASCS) for the International Atomic Energy Agency (IAEA). Agency standard weights and safeguards samples can be stored in the ASCS to provide continuity of knowledge. The ASCS consists of an optically clear cover, a base containing the Authenticated Item Monitoring System (AIMS) transmitter, and the AIMS receiver unit for data collection. The ASCS will provide the Inspector with information concerning the status of the system, during a surveillance period, such as state of health, tampering attempts, and movement of the container system. The secure container is located inside a Glove Box with the receiver located remotely from the Glove Box. AIMS technology uses rf transmission from the secure container to the receiver to provide a record of state of health and tampering. The data is stored in the receiver for analysis by the Inspector during a future inspection visit. 2 refs

7 CFR 58.923 - Filling containers.

Science.gov (United States)

2010-01-01

... 7 Agriculture 3 2010-01-01 2010-01-01 false Filling containers. 58.923 Section 58.923 Agriculture... Procedures § 58.923 Filling containers. (a) The filling of small containers with product shall be done in a sanitary manner. The containers shall not contaminate or detract from the quality of the product in any way...

40 CFR 265.171 - Condition of containers.

Science.gov (United States)

2010-07-01

... 40 Protection of Environment 25 2010-07-01 2010-07-01 false Condition of containers. 265.171... DISPOSAL FACILITIES Use and Management of Containers § 265.171 Condition of containers. If a container... transfer the hazardous waste from this container to a container that is in good condition, or manage the...

40 CFR 264.171 - Condition of containers.

Science.gov (United States)

2010-07-01

... 40 Protection of Environment 25 2010-07-01 2010-07-01 false Condition of containers. 264.171... Use and Management of Containers § 264.171 Condition of containers. If a container holding hazardous... leak, the owner or operator must transfer the hazardous waste from this container to a container that...

21 CFR 100.100 - Misleading containers.

Science.gov (United States)

2010-04-01

... 21 Food and Drugs 2 2010-04-01 2010-04-01 false Misleading containers. 100.100 Section 100.100... containers. In accordance with section 403(d) of the act, a food shall be deemed to be misbranded if its container is so made, formed, or filled as to be misleading. (a) A container that does not allow the...

7 CFR 201.42 - Small containers.

Science.gov (United States)

2010-01-01

... 7 Agriculture 3 2010-01-01 2010-01-01 false Small containers. 201.42 Section 201.42 Agriculture... REGULATIONS Sampling in the Administration of the Act § 201.42 Small containers. In sampling seed in small containers that it is not practical to sample as required in § 201.41, a portion of one unopened container or...

46 CFR 160.036-6 - Container.

Science.gov (United States)

2010-10-01

... 46 Shipping 6 2010-10-01 2010-10-01 false Container. 160.036-6 Section 160.036-6 Shipping COAST... § 160.036-6 Container. (a) General. The container for storing the signals on lifeboats and liferafts is not required to be of a special design or be approved by the Coast Guard. The container must meet the...

46 CFR 160.023-6 - Container.

Science.gov (United States)

2010-10-01

... 46 Shipping 6 2010-10-01 2010-10-01 false Container. 160.023-6 Section 160.023-6 Shipping COAST... Container. (a) General. The container for storing the signals on lifeboats and liferafts is not required to be of a special design or be approved by the Coast Guard. The container must meet the requirements in...

Storage vessel for radiation contaminated container

International Nuclear Information System (INIS)

Sakatani, Tadatsugu.

1996-01-01

In a storage vessel of the present invention, a plurality of radiation contaminated material containing bodies are vertically stacked in a cell chamber. Then, the storage vessel comprises a containing tube for containing a plurality of the containing bodies, cooling coils wound around the containing tube, a cooling medium circulating system connected to the cooling coils and circulating cooling medium, and a heat exchanger interposed to the cooling medium circulating system for removing heat of the cooling medium. Heat of the radioactive material containing bodies is transferred to cooling air and cooling coils by way of the container tube, thereby cooling the containing bodies. By the operation of circulating pumps in a cooling medium circulation system, the cooling medium circulates through a circulation channel comprising a cooling medium transfer pipes, cooling medium branching tubes, cooling coils and the heat exchanger, then heat of the cooling medium is transferred to a heat utilizing system by way of the heat exchanger to attain effective utilization of the heat. In this case, heat can be taken out stably even when the storage amount fluctuates and heat releasing amount is reduced, and improvement of heat transfer promotes the cooling of the containing bodies, which enables minimization of the size of the storage vessel. (T.M.)

Large panel design for containment air baffle

International Nuclear Information System (INIS)

Orr, R.S.

1992-01-01

The movable air baffle shield means in accordance with the present invention provides an efficient method of cooling the space surrounding the containment vessel while also providing the capability of being moved away from the containment vessel during inspection. The containment apparatus comprises a generally cylindrical sealed containment vessel for containing at least a portion of a nuclear power generation plant, a disparate shield building surrounding and housing the containment vessel therein and spaced outwardly thereof so as to form an air annulus in the space between the shield building and the containment vessel, a shield baffle means positioned in the air annulus around at least a portion of the sides of the containment vessel providing a coolant path between the baffle means and the containment vessel to permit cooling of the containment vessel by air, the shield baffle means being movable to afford access to the containment vessel. 9 figs

Container for hydrogen isotopes

Energy Technology Data Exchange (ETDEWEB)

1976-01-12

A container is described for storage, shipping and and dispensing of hydrogen isotopes such as hydrogen, deuterium, tritium, or mixtures of the same. The container is compact, safe against fracture or accident, and is reusable. It consists of an outer housing with suitable inlet and outlet openings and electrical feed elements, the housing containing an activated sorber material in the form, for example of titanium sponge or an activated zirconium aluminate cartridge. The gas to be stored is introduced into the chamber under conditions of heat and vacuum and is retained in the sorber material. Subsequently, it may be released by heating the unit to drive off the stored gas at desired rates.

Container for liquefied gas

Energy Technology Data Exchange (ETDEWEB)

Short, A J

1967-05-18

Containers for liquefied gases are of double-wall construction with a vacuum between the 2 walls; the upper end of the neck contains a vapor chamber and is equipped with means for withdrawing gas from the container. According to this invention, the vapor chamber is connected to a damping chamber by means of a choke line which has an internal diameter of at least 1.6 mm and a length equal to at least 52 times the diameter. The damping chamber has a volume of at least 5 cu cm and is larger than the outer part of the chamber. The interior length of the damping chamber is at least twice the diameter of the choke line. (5 claims)

Subatmospheric double containment system

International Nuclear Information System (INIS)

Gans, D. Jr.; Noble, J.H.

1978-01-01

A reinforced concrete double wall nuclear containment structure with each wall including an essentially impervious membrane or liner and porous concrete filling the annulus between the two walls is described. The interior of the structure is maintained at subatmospheric pressure, and the annulus between the two walls is maintained at a subatmospheric pressure intermediate between that of the interior and the surrounding atmospheric pressure, during normal operation. In the event of an accident within the containment structure the interior pressure may exceed atmospheric pressure, but leakage from the interior to the annulus between the double walls will not result in the pressure of the annulus exceeding atmospheric pressure so that there is no net outleakage from the containment structure

Container for hydrogen isotopes

International Nuclear Information System (INIS)

1976-01-01

A container is described for storage, shipping and and dispensing of hydrogen isotopes such as hydrogen, deuterium, tritium, or mixtures of the same. The container is compact, safe against fracture or accident, and is reusable. It consists of an outer housing with suitable inlet and outlet openings and electrical feed elements, the housing containing an activated sorber material in the form, for example of titanium sponge or an activated zirconium aluminate cartridge. The gas to be stored is introduced into the chamber under conditions of heat and vacuum and is retained in the sorber material. Subsequently, it may be released by heating the unit to drive off the stored gas at desired rates

Container for hydrogen isotopes

International Nuclear Information System (INIS)

Solomon, D.E.

1977-01-01

A container for the storage, shipping and dispensing of hydrogen isotopes such as hydrogen, deuterium, tritium, or mixtures of the same which has compactness, which is safe against fracture or accident, and which is reusable is described. The container consists of an outer housing with suitable inlet and outlet openings and electrical feed elements, the housing containing an activated sorber material in the form, for example, of titanium sponge or an activated zirconium aluminate cartridge. The gas to be stored is introduced into the chamber under conditions of heat and vacuum and will be retained in the sorber material. Subsequently, it may be released by heating the unit to drive off the stored gas at desired rates

Analysis of Depressurization Performance in Containment of Wolsong NPP Unit 1 through Containment Filtered Venting System

International Nuclear Information System (INIS)

Lee, Sunghan; Kim, Jinhyuck; Suh, Nam Duk; Cho, Songwon

2014-01-01

Containment filtered venting system (CFVS) is designed to open and to close isolation valves passively by an operator. CFVS is operated when the containment pressure exceeds the design pressure (225 kPa(a)) and is closed when the containment pressure decreases below 151 kPa(a). The aim of this study is to analyze the depressurization performance of Wolsong unit 1 through CFVS during SBO. The thermal-hydraulic behavior in containment of Wolsong unit 1 was evaluated using the MELCOR 1.8.6 code developed at Sandia National Laboratories (SNL) for the U.S. Nuclear Regulatory Commission (NRC). In addition, in order to evaluate the effects of the CFVS according to the venting area, a sensitivity study depending on different venting area of the CFVS was conducted. Finally, an analysis of the effects of filtering and scrubbing of radioactive material for CFVS is important but not treated in this paper. The SBO accident is chosen to analyze the thermal-hydraulic behavior of Wolsong unit 1. During SBO, the analysis of CFVS affecting on the depressurization of the containment was conducted using MELCOR 1.8.6 code. Also, a sensitivity study was carried out to evaluate the depressurization performance according to the venting area of CFVS. The results show that the containment pressure is considerably decreased and the integrity of the containment could be maintained in case of CFVS operating. Therefore, CFVS has the capacity to keep the containment pressure below the design pressure during SBO. In addition, there are large differences in the containment pressure depending on venting area. We found that the decreasing rate of the pressure in the containment and water level in CFVS depends on the venting area. In the future, a proper requirement for CFVS sizing criteria according to accident scenarios such as LBLOCA, SBLOCA and SGTR, etc. should be evaluated in order to review the licensing for CFVS. Finally, analyses of aerosols, fission product, and radioactive material

Explosive composition containing water

Energy Technology Data Exchange (ETDEWEB)

Cattermole, G.R.; Lyerly, W.M.; Cummings, A.M.

1971-11-26

This addition to Fr. 1,583,223, issued 31 May 1968, describes an explosive composition containing a water in oil emulsion. The composition contains an oxidizing mineral salt, a nitrate base salt as sensitizer, water, an organic fuel, a lipophilic emulsifier, and incorporates gas bubbles. The composition has a performance which is improved over and above the original patent.

CONTAINER FOR USED TEXTILES

CERN Multimedia

Relation with the Host States

2001-01-01

We should like to remind you that a special container for textiles for the Association 'Réalise/Rapid Service' of Geneva is located in the car park outside the Meyrin site. The Association has informed us that 3 306 kg of textiles were deposited in the container in 2000 and wishes to convey its warm gratitude to all donors.

Consumer Products Containing Radioactive Materials

Science.gov (United States)

Fact Sheet Adopted: February 2010 Health Physics Society Specialists in Radiation Safety Consumer Products Containing Radioactive Materials Everything we encounter in our daily lives contains some radioactive material, ...

An analysis of containment venting as a severe accident mitigation strategy for the BWR Mark II containment

International Nuclear Information System (INIS)

Kelly, D.L.; Galyean, W.J.

1990-01-01

An evaluation of a BWR/4 reactor with a Mark-II containment has identified the effects of containment venting on core damage frequency and containment failure mode, and has performed a limited evaluation of the effects on the off-site consequences. The analysis was founded upon an existing probabilistic risk assessment (PRA) with the addition of a proposed filtered containment venting system, based on the Swedish Filtra system installed at the Barseback nuclear power station in southern Sweden. Three different containment venting strategies were examined for their effects on plant risk. These are discussed

Tougher containment design goals

International Nuclear Information System (INIS)

O'Farrelly, C.

1978-01-01

Present day LWR containment design goals are reviewed, together with their potential failure modes. Rasmussen's estimates of failure probabilities are discussed and the concept of ''delayed failure'' is seen to be a valuable safety goal for hypothetical accidents. The paper investigates the inherent coremelt resistance capability of various containment designs and suggests improvements, with special emphasis on increasing the failure delay times. (author)

40 CFR 165.45 - Refillable container standards.

Science.gov (United States)

2010-07-01

... 40 Protection of Environment 23 2010-07-01 2010-07-01 false Refillable container standards. 165.45... PESTICIDE MANAGEMENT AND DISPOSAL Refillable Container Standards: Container Design § 165.45 Refillable container standards. (a) What Department of Transportation (DOT) standards do my refillable containers have...

Container for radioactive materials

International Nuclear Information System (INIS)

Housholder, W.R.; Greer, N.L.

1976-01-01

The improvement of the construction of containers for the transport of nuclear fuels is proposed where above all, the insulating mass suggested is important as it acts as a safeguard in case of an accident. The container consists of a metal casing in which there is a pressure boiler and a gamma-shielding device, spacers between the metal casing and the shielding device as well as an insulation filling the space between them. The insulating material is a water-in-resin emulsion which is hardened or cross-linked by peroxide and which can furthermore contain up to 50 wt.% solid silicious material such as vermuculite or chopped glass fibre. The construction and variations of the insulating mass composition are described in great detail. (HR) [de

Trends in the development of reactor containments

International Nuclear Information System (INIS)

Turricchia, A.

1977-01-01

The paper presents a review of the technical developments which the containment systems of BWRs, PWRs and HWRs have undergone in the USA, Europe and Canada. The great variety of existing containment systems have been classified for each type of reactor, according to: principle of operation (i.e. dry containment; pressure suppression containment; containment with vacuum building; sub-atmospheric containment; etc.); type and number of the physical barriers provided against the dispersion of fission products to the environment (single containment, double containment, single containment with local collection of the leaks from the most probable leakage paths, or with pressurization of the potential leakage paths, etc.); and structural characteristics of the containment barriers (reinforced concrete, prestressed concrete, metal containment, liners). In the framework of this classification the main features of the various containment systems are illustrated, with special emphasis on the most modern designs. The difference in trend among various countries and various designers are highlighted. A review is also made of the various containment auxiliary systems which would operate in accident conditions (isolation systems, heat removal system, atmosphere control system, etc.). Also for these systems the main design criteria are set forth and present trends are described. Finally, a brief survey is also made of the present trends with regards to the design of containment structures against external events be they of natural origin (earthquake, tornadoes, etc.) or connected with human activities (airplane crash, explosions, etc.) [fr

Alternative pathways to antimatter containment

International Nuclear Information System (INIS)

Rejcek, J.M.; Browder, M.K.; Fry, J.L.; Koymen, A.; Weiss, A.H.

2003-01-01

Antimatter containment is a gateway technology for future advancements in many areas. Immediate applications in propulsion, medicine, and instrumentation have already been envisioned and many others are yet to be considered. Key to this technological advance is identifying one or more pathways to achieve safe reliable containment of antimatter in sufficient quantities to be useful on an engineering and industrial scale. The goal of this paper is to review current approaches and discuss possible alternative pathways to antimatter containment. Specifically, this paper will address the possibility of designing a solid-state containment system that will safely hold antimatter in quantities dense enough to be of any engineering utility. A discussion of the current research, the needed engineering requirements, and a survey of current research is presented

Nondestructive Examination Of Plutonium-Bearing Material Containers

International Nuclear Information System (INIS)

Yerger, L.; Mcclard, J.; Traver, L.; Grim, T.

2010-01-01

The first nondestructive examination (NDE) of 3013-type containers as part of the Department of Energy's (DOE's) Integrated Surveillance Program (ISP) was performed in February, 2005. Since that date 280 NDE surveillances on 255 containers have been conducted. These containers were packaged with plutonium-bearing materials at multiple DOE sites. The NDE surveillances were conducted at Hanford, Lawrence Livermore National Laboratory (LLNL), and Savannah River Site (SRS). These NDEs consisted of visual inspection, mass verification, radiological surveys, prompt gamma analysis, and radiography. The primary purpose of performing NDE surveillances is to determine if there has been a significant pressure buildup inside the inner 3013 container. This is done by measuring the lid deflection of the inner 3013 container using radiography images. These lid deflection measurements are converted to pressure measurements to determine if a container has a pressure of a 100 psig or greater. Making this determination is required by Surveillance and Monitoring Plan (S and MP). All 3013 containers are designed to withstand at least 699 psig as specified by DOE-STD-3013. To date, all containers evaluated have pressures under 50 psig. In addition, the radiography is useful in evaluating the contents of the 3013 container as well as determining the condition of the walls of the inner 3013 container and the convenience containers. The radiography has shown no signs of degradation of any container, but has revealed two packaging anomalies. Quantitative pressure measurements based on lid deflections, which give more information than the 'less than or greater than 100 psig' (pass/fail) data are also available for many containers. Statistical analyses of the pass/fail data combined with analysis of the quantitative data show that it is extremely unlikely that any container in the population of 3013 containers considered in this study (e.g., containers packaged according to the DOE-STD-3013

The evolution of CANDU containment design

International Nuclear Information System (INIS)

Pendergast, Duane R.; Meneley, Daniel A.

1995-01-01

This paper reviews Canadian containment design, reflects on forces which have shaped the evolving designs and contemplates future containment design subject to existing constraints of Canadian and International nuclear power regulations. The discussion mentions modifications which could play a role in easing customary restrictions on siting while meeting the intent and literal definition of Canadian licensing requirements. Many different containment concepts have been considered and deployed over the years. Professor Birkhofer points out that the earliest systems installed were 'dry containment'. These rely on large containment buildings designed to contain all the the steam from a loss of coolant. It was soon realized the large water inventory of boiling water reactors would require very large and expensive containment buildings. This led to the development of pressure suppression concepts. Various pressure suppression schemes have been devised to condense steam and thus reduce design pressure and volume requirements. Examples include the forcing of steam into condensing water pools of BWR's steam condensation by passage into arrays of ice, dousing spray systems in CANDU reactors, and the spray condenser systems of late model Soviet designed VVER - 440 reactors. The fundamental concept of energy removal by steam condensation can result in a small containment volume requiring low design pressure capability

Reactor container and controlling method thereof

International Nuclear Information System (INIS)

Hosaka, Seiichi.

1990-01-01

An object of the present invention is to prevent stress corrosion crack caused in pipelines made of stainless steels by preventing deposition of chlorine, etc. on the surface, etc. of the pipelines. That is, an internal evolving gas elimination system comprises a gas extraction device for extracting gases in the reactor container, an obstacle elimination device for eliminating obstacles contained in the extracted gases and an internal gas elimination device for eliminating internal evolving gases contained in the extracted gases. Further, gases in the upper portion of the reactor container are extracted and then the ingredients of the internal evolving gases contained in the gases are eliminated and, thereafter, the gases are supplied to the lower portion of the container to keep the relative humidity in the reactor container to less than 20%RH. As a result, since the internal evolving gases are eliminated and the relative humidity at the inside is kept to less than 20%RH, deposition of chlorine or salts on the pipelines can be prevented to thereby prevent the stress corrosion cracks. (I.S.)

Nuclear fuel element and container

International Nuclear Information System (INIS)

Grubb, W.T.; King, L.H.

1981-01-01

The invention is based on the discovery that a substantial reduction in metal embrittlement or stress corrosion cracking from fuel pellet-cladding interaction can be achieved by the use of a copper layer or liner in proximity to the nuclear fuel, and an intermediate zirconium oxide barrier layer between the copper layer and the zirconium cladding substrate. The intermediate zirconia layer is a good copper diffusion barrier; also, if the zirconium cladding surface is modified prior to oxidation, copper can be deposited by electroless plating. A nuclear fuel element is described which comprises a central core of fuel material and an elongated container using the system outlined above. The method for making the container is again described. It comprises roughening or etching the surface of the zirconium or zirconium alloy container, oxidizing the resulting container, activating the oxidized surface to allow for the metallic coating of such surfaces by electroless deposition and further coating the activated-oxidized surface of the zirconium or zirconium alloy container with copper, iron or nickel or an alloy thereof. (U.K.)

Weapon container catalog. Volumes 1 & 2

Energy Technology Data Exchange (ETDEWEB)

Brown, L.A.; Higuera, M.C.

1998-02-01

The Weapon Container Catalog describes H-gear (shipping and storage containers, bomb hand trucks and the ancillary equipment required for loading) used for weapon programs and for special use containers. When completed, the catalog will contain five volumes. Volume 1 for enduring stockpile programs (B53, B61, B83, W62, W76, W78, W80, W84, W87, and W88) and Volume 2, Special Use Containers, are being released. The catalog is intended as a source of information for weapon program engineers and also provides historical information. The catalog also will be published on the SNL Internal Web and will undergo periodic updates.

TRUPACT-II container maintenance program plan

International Nuclear Information System (INIS)

1990-11-01

This document details the maintenance/repair and replacement of components, as well as the documentation required and the procedures to be followed to maintain the integrity of the TRUPACT-II container, in accordance with requirements of the TRUPACT-II Container Operations and Maintenance Manual, OM-134, the TRUPACT-II Container Safety Analysis Report (SARP), and the TRUPACT-II Container Certificate of Compliance (Number 9218). The routine shipping and receiving inspections required by the Department of Transportation (DOT), Department of Energy (DOE), Nuclear Regulatory Commission (NRC) and other regulations are not addressed in this document. This document applies to all DOE shipping and receiving sites that use the TRUPACT-II containers

40 CFR 265.173 - Management of containers.

Science.gov (United States)

2010-07-01

... 40 Protection of Environment 25 2010-07-01 2010-07-01 false Management of containers. 265.173... DISPOSAL FACILITIES Use and Management of Containers § 265.173 Management of containers. (a) A container... waste. (b) A container holding hazardous waste must not be opened, handled, or stored in a manner which...

40 CFR 264.173 - Management of containers.

Science.gov (United States)

2010-07-01

... 40 Protection of Environment 25 2010-07-01 2010-07-01 false Management of containers. 264.173... Use and Management of Containers § 264.173 Management of containers. (a) A container holding hazardous... container holding hazardous waste must not be opened, handled, or stored in a manner which may rupture the...

CONTAINER FOR USED TEXTILES

CERN Multimedia

Relations avec les Pays hôtes

2000-01-01

We should like to remind you that a special container for textiles for the Association 'Réalise/Rapid Service' of Geneva is located in the car park outside the Meyrin site.The Association has informed us that 2 530 kg of textiles were deposited in the container in 1998 and wishes to convey its warm gratitude to all donors.Relations with the Host StatesTel. 75152

FDA Peanut-Containing Product Recall

Data.gov (United States)

U.S. Department of Health & Human Services — The FDA Peanut-Containing Product Recall widget allows you to browse the Food and Drug Administration (FDA) database of peanut butter and peanut-containing products...

Material containment enclosure

International Nuclear Information System (INIS)

Carlson, D.O.

1993-01-01

An isolation enclosure and a group of isolation enclosures are described which are useful when a relatively large containment area is required. The enclosure is in the form of a ring having a section removed so that a technician may enter the center area of the ring. In a preferred embodiment, an access zone is located in the transparent wall of the enclosure and extends around the inner perimeter of the ring so that a technician can insert his hands into the enclosure to reach any point within. The inventive enclosures provide more containment area per unit area of floor space than conventional material isolation enclosures. 3 figures

Simulation of containment phenomena during the Phebus FPT1 test with the CONTAIN code

International Nuclear Information System (INIS)

Kljenak, I.; Mavko, B.

2002-01-01

Thermal-hydraulic and aerosol phenomena which occurred in the containment vessel of the Phebus integral experimental facility during the first 30000 s of the Phebus FPT1 test were simulated with the CONTAIN thermal-hydraulic computer code. A single-cell input model of the vessel was developed, and boundary and initial conditions that were determined during the experiment were applied. The comparison of experimental and calculated results shows that, although the atmosphere temperature was well simulated, the calculated condensation rate was apparently too high, resulting in a lower pressure of the containment atmosphere. The aerosol deposition process was well simulated.(author)

Transient behaviour and coupling aspects of a hybrid MSF-RO nuclear desalination plant

International Nuclear Information System (INIS)

Tewari, P.K.; Misra, B.M.

1998-01-01

BARC is setting up a 6300 M 3 /day (1.4 MGD) hybrid MSF-RO nuclear desalination plant for sea water desalination at Madras Atomic Power Station (MAPS) coupled to a 170 MWe Pressurised Heavy Water Reactor (PHWR). The transient behaviour and coupling aspects of this dual purpose plant has been discussed. A hybrid desalination plant appears to offer high availability factor. (author)

Biological clearance and committed dose equivalent in pulmonary region from inhaled radioaerosols for lung scanning

Energy Technology Data Exchange (ETDEWEB)

Soni, P.S.; Sharma, S.M.; Raghunath, B.; Somasundaram, S.

1987-01-01

Biological clearance half-lives (Tsub(b)) of different /sup 99/Tcsup(m)-labelled compounds from each lung have been determined, after administering the radioaerosol to normal subjects using the BARC dry aerosol generation and inhalation system. Based on these experimental clearance half-lives, the committed dose equivalent to the lungs has been computed using both the ICRP lung model and MIRD-11 values.

Biological clearance and committed dose equivalent in pulmonary region from inhaled radioaerosols for lung scanning

International Nuclear Information System (INIS)

Soni, P.S.; Sharma, S.M.; Raghunath, B.; Somasundaram, S.

1987-01-01

Biological clearance half-lives (Tsub(b)) of different 99 Tcsup(m)-labelled compounds from each lung have been determined, after administering the radioaerosol to normal subjects using the BARC dry aerosol generation and inhalation system. Based on these experimental clearance half-lives, the committed dose equivalent to the lungs has been computed using both the ICRP lung model and MIRD-11 values. (author)

Brain germinoma presenting as a first psychotic episode in an adolescent male

OpenAIRE

2010-01-01

Brain germinoma presenting as a first psychotic episode in an adolescent male phone: +34-93-2275477 (Undurraga, Juan) (Undurraga, Juan) Department of Psychiatry, Institute of Neuroscience, Hospital Clinic de Barcelona - Servicio de Psiquiatria (Escalera 9, Planta 6), Calle Villarroel, 170 - 08036 - Barcelona - SPAIN (Undurraga, Juan) Department of Child and Adolescent Psychology and Psychiatry, Institute of Neuroscience, Hospital Clinic de Barcelona - Barc...

Development of Pneumatic Transport System (PTS) for safe handling of uranium oxide powder in UMP/UED

International Nuclear Information System (INIS)

Manna, S.; Satpati, S.K.; Roy, S.B.

2009-01-01

Tonnage quantity radioactive uranium oxide powder of particle size sub micron to 100 micron is handled in Uranium Metal Plant (UMP), UED/BARC for production of nuclear grade uranium metal, required for fuelling research reactors - Dhruva and Cirus. A Pneumatic Transfer System (PTS) using vacuum has been introduced and is being used for handling radioactive powder to improve radiation protection

Multipurpose container for low-level radioactive waste

International Nuclear Information System (INIS)

Anderson, R.T.; Pearson, S.D.

1993-01-01

A method is described for disposing of low-level radioactive waste, comprising the steps of (a) introducing the waste into a multipurpose container, the multipurpose container comprising a polymeric inner container disposed within a concrete outer shell, the shape of the inner container conforming substantially to the shape of the outer shell's inner surface, (b) transporting the waste in the same multipurpose container to a storage location, and (c) storing the container at the storage location

Lightweight engine containment. [Kevlar shielding

Science.gov (United States)

Weaver, A. T.

1977-01-01

Kevlar fabric styles and weaves were studied, as well as methods of application for advanced gas turbine engines. The Kevlar material was subjected to high speed impacts by simple projectiles fired from a rifle, as well as more complex shapes such as fan blades released from gas turbine rotors in a spin pit. Just contained data was developed for a variety of weave and/or application techniques, and a comparative containment weight efficiency was established for Kevlar containment applications. The data generated during these tests is being incorporated into an analytical design system so that blade containment trade-off studies between Kevlar and metal case engine structures can be made. Laboratory tests and engine environment tests were performed to determine the survivability of Kevlar in a gas turbine environment.

Hydrogen transport in the containment; Wasserstofftransport im Containment

Energy Technology Data Exchange (ETDEWEB)

Royl, P.; Mueller, C.; Travis, J.R.; Wilson, T.

1995-08-01

For the description of transport phenomena in water vapor/hydrogen mixtures released in nuclear meltdown accidents, an integrated analytical model is being developed for LWR containments. Thermal and mechanical loads due to recombination and combustion are to be calculable. The 3-dimensional GASFLOW code was taken over from LANL in exchange for HDR experimental results and Battelle BMC program results. (orig.)

A research on verification of the CONTAIN CODE model and the uncertainty reduction method for containment integrity

Energy Technology Data Exchange (ETDEWEB)

Park, Jae-Hong; Kim, Moo-Hwan; Bae, Seong-Won; Byun, Sang-Chul [Pohang University of Science and Technology, Pohang (Korea, Republic of)

1998-03-15

The final objectives of this study are to establish the way of measuring the integrity of containment building structures and safety analysis in the period of a postuIated severe accidents and to decrease the uncertainty of these methods. For that object, the CONTAIN 1.2 codes model for analyzing the severe accidents phenomena and the heat transfer between the air inside the containment buildings and inner walls have been reviewed and analyzed. For the double containment wall provided to the next generation nuclear reactor, which is different to the previous type of containment, the temperature and pressure rising history were calculated and compared to the results of previous ones.

Passive heat transport in advanced CANDU containment

International Nuclear Information System (INIS)

Krause, M.; Mathew, P.M.

1994-01-01

A passive CANDU containment design has been proposed to provide the necessary heat removal following a postulated accident to maintain containment integrity. To study its feasibility and to optimize the design, multi-dimensional containment modelling may be required. This paper presents a comparison of two CFD codes, GOTHIC and PHOENICS, for multi-dimensional containment analysis and gives pressure transient predictions from a lumped-parameter and a three-dimensional GOTHIC model for a modified CANDU-3 containment. GOTHIC proved suitable for multidimensional post-accident containment analysis, as shown by the good agreement with pressure transient predictions from PHOENICS. GOTHIC is, therefore, recommended for passive CANDU containment modelling. (author)

40 CFR 264.1086 - Standards: Containers.

Science.gov (United States)

2010-07-01

... 40 Protection of Environment 25 2010-07-01 2010-07-01 false Standards: Containers. 264.1086... Air Emission Standards for Tanks, Surface Impoundments, and Containers § 264.1086 Standards: Containers. (a) The provisions of this section apply to the control of air pollutant emissions from...

46 CFR 160.028-6 - Container.

Science.gov (United States)

2010-10-01

... 46 Shipping 6 2010-10-01 2010-10-01 false Container. 160.028-6 Section 160.028-6 Shipping COAST GUARD, DEPARTMENT OF HOMELAND SECURITY (CONTINUED) EQUIPMENT, CONSTRUCTION, AND MATERIALS... Container. (a) General. Containers for the stowage of signal pistols and pistol projected parachute red...

Histidine-Containing Peptide Nucleic Acids

DEFF Research Database (Denmark)

2000-01-01

Peptide nucleic acids containing histidine moieties are provided. These compounds have applications including diagnostics, research and potential therapeutics.......Peptide nucleic acids containing histidine moieties are provided. These compounds have applications including diagnostics, research and potential therapeutics....

Hydrogen distribution analysis for CANDU 6 containment using the GOTHIC containment analysis code

International Nuclear Information System (INIS)

Nguyen, T.H.; Collins, W.M.

1995-01-01

Hydrogen may be generated in the reactor core by the zircaloy-steam reaction for a postulated loss of coolant accident (LOCA) scenario with loss of emergency core cooling (ECC). It is important to predict hydrogen distribution within containment in order to determine if flammable mixtures exist. This information is required to determine the best locations in containment for the placement of mitigation devices such as igniters and recombiners. For large break loss coolant accidents, hydrogen is released after the break flow has subsided. Following this period of high discharge the flow in the containment building undergoes transition from forced flow to a buoyancy driven flow (particularly when local air coolers (LACS) are not credited). One-dimensional computer codes (lumped parameter) are applicable during the initial period when a high degree of mixing occurs due to the forced flow generated by the break. However, during the post-blowdown phase the assumption of homogeneity becomes less accurate, and it is necessary to employ three-dimensional codes to capture local effects. This is particularly important for purely buoyant flows which may exhibit stratification effects. In the present analysis a three-dimensional model of CANDU 6 containment was constructed with the GOTHIC computer code using a relatively coarse mesh adequate enough to capture the salient features of the flow during the blowdown and hydrogen release periods. A 3D grid representation was employed for that portion of containment in which the primary flow (LOCA and post-LOCA) was deemed to occur. The remainder of containment was represented by lumped nodes. The results of the analysis indicate that flammable concentrations exist for several minutes in the vicinity of the break and in the steam generator enclosure. This is due to the fact that the hydrogen released from the break is primarily directed upwards into the steam generator enclosure due to buoyancy effects. Once hydrogen production ends

7 CFR 2902.21 - Disposable containers.

Science.gov (United States)

2010-01-01

... 7 Agriculture 15 2010-01-01 2010-01-01 false Disposable containers. 2902.21 Section 2902.21... Items § 2902.21 Disposable containers. (a) Definition. Products designed to be used for temporary... paragraph (d): Disposable containers can include boxes and packaging made from paper. Under the Resource...

40 CFR 265.1087 - Standards: Containers.

Science.gov (United States)

2010-07-01

... 40 Protection of Environment 25 2010-07-01 2010-07-01 false Standards: Containers. 265.1087... DISPOSAL FACILITIES Air Emission Standards for Tanks, Surface Impoundments, and Containers § 265.1087 Standards: Containers. (a) The provisions of this section apply to the control of air pollutant emissions...

Seal welded cast iron nuclear waste container

International Nuclear Information System (INIS)

Filippi, A.M.; Sprecace, R.P.

1987-01-01

An article of manufacture is described comprising a cast iron container having an opening at one end and a cast iron plug; a first nickel-carbon alloy fusion weldable insert surrounding the opening and metallurgically bonded to the cast iron container at the one end of the container; a second nickel-carbon alloy insert metallurgically bonded to the cast iron plug located within the opening and surrounded by the first insert the inserts being jointed by a fusion bond in the opening without heating the cast iron container to an austenite formation temperature thereby sealing the interior of the container from the exterior ambient outside the opening; the nickel-carbon alloy containing about 2 to 5 w% carbon; and both the nickel-carbon alloy insert and the cast iron container have a microstructure containing a graphite phase

Radioactive liquid containing vessel

International Nuclear Information System (INIS)

Sakurada, Tetsuo; Kawamura, Hironobu.

1993-01-01

Cooling jackets are coiled around the outer circumference of a container vessel, and the outer circumference thereof is covered with a surrounding plate. A liquid of good conductivity (for example, water) is filled between the cooling jackets and the surrounding plate. A radioactive liquid is supplied to the container vessel passing through a supply pipe and discharged passing through a discharge pipe. Cooling water at high pressure is passed through the cooling water jackets in order to remove the heat generated from the radioactive liquid. Since cooling water at high pressure is thus passed through the coiled pipes, the wall thickness of the container vessel and the cooling water jackets can be reduced, thereby enabling to reduce the cost. Further, even if the radioactive liquid is leaked, there is no worry of contaminating cooling water, to prevent contamination. (I.N.)

27 CFR 20.177 - Encased containers.

Science.gov (United States)

2010-04-01

... 27 Alcohol, Tobacco Products and Firearms 1 2010-04-01 2010-04-01 false Encased containers. 20.177... Users of Specially Denatured Spirits Operations by Dealers § 20.177 Encased containers. (a) A dealer may package specially denatured spirits in unlabeled containers which are completely encased in wood...

27 CFR 20.145 - Encased containers.

Science.gov (United States)

2010-04-01

... 27 Alcohol, Tobacco Products and Firearms 1 2010-04-01 2010-04-01 false Encased containers. 20.145... Denatured Alcohol § 20.145 Encased containers. Completely denatured alcohol may be packaged by distributors in unlabeled containers which are completely encased in wood, fiberboard, or similar material so that...

Sample container for neutron activation analysis

International Nuclear Information System (INIS)

Lersmacher, B.; Verheijke, M.L.; Jaspers, H.J.

1983-01-01

The sample container avoids contaminating the sample substance by diffusion of foreign matter from the wall of the sample container into the sample. It cannot be activated, so that the results of measurements are not falsified by a radioactive container wall. It consists of solid carbon. (orig./HP) [de

7 CFR 956.162 - Container markings.

Science.gov (United States)

2010-01-01

... 7 Agriculture 8 2010-01-01 2010-01-01 false Container markings. 956.162 Section 956.162... WALLA VALLEY OF SOUTHEAST WASHINGTON AND NORTHEAST OREGON Rules and Regulations § 956.162 Container markings. Effective April 15, 1997, no handler shall ship any container of Walla Walla Sweet Onions except...

Containment leakage rate testing requirements

International Nuclear Information System (INIS)

Arndt, E.G.

1992-01-01

This report presents the status of several documents under revision or development that provide requirements and guidance for testing nuclear power plant containment systems for leakage rates. These documents include the general revision to 10 CFR Part 50, Appendix J; the regulatory guide affiliated with the revision to Appendix J; the national standard that the regulatory guide endorses, ANSI/ANS-56.8, 'Containment System Leakage Rate Testing Requirements'; and the draft industry Licensing Topical Report, 'Standardized Program for Primary Containment Integrity Testing'. The actual or potential relationships between these documents are also explored

Reliability analysis of steel-containment strength

International Nuclear Information System (INIS)

Greimann, L.G.; Fanous, F.; Wold-Tinsae, A.; Ketalaar, D.; Lin, T.; Bluhm, D.

1982-06-01

A best estimate and uncertainty assessment of the resistance of the St. Lucie, Cherokee, Perry, WPPSS and Browns Ferry containment vessels was performed. The Monte Carlo simulation technique and second moment approach were compared as a means of calculating the probability distribution of the containment resistance. A uniform static internal pressure was used and strain ductility was taken as the failure criterion. Approximate methods were developed and calibrated with finite element analysis. Both approximate and finite element analyses were performed on the axisymmetric containment structure. An uncertainty assessment of the containment strength was then performed by the second moment reliability method. Based upon the approximate methods, the cumulative distribution for the resistance of each of the five containments (shell modes only) is presented

Pricing Scheme of Ocean Carrier for Inbound Container Storage for Assistance of Container Supply Chain Finance

Directory of Open Access Journals (Sweden)

Mingzhu Yu

2014-01-01

Full Text Available The aim of this paper is to investigate the pricing scheme of ocean carrier for inbound container storage so as to assist container supply chain finance. In this paper, how an ocean carrier should set price of inbound container storage to the customer while facing the contract from the container terminal operator is first analyzed. Then, two different contract systems, the free-time contract system which is widely used in practice and the free-space contract system which is newly developed recently, are considered. In the two different contract systems, inbound container storage pricing models are constructed, and accordingly optimal solution approaches for the ocean carrier are provided. For comparison purpose, some numerical experiments for the two different contract systems are conducted to investigate the effects of the container terminal operator’s decision on the system outcomes. Numerical experiments show that (1 the carrier is more flexible in the free-space contract system and can receive more profit by using the free-storage-space as a pooling storage system and (2 the free-space contract system benefits both the carrier in profit and the busy terminal in traffic control.

Residual Stress Testing of Outer 3013 Containers

International Nuclear Information System (INIS)

Dunn, K.

2004-01-01

A Gas Tungsten Arc Welded (GTAW) outer 3013 container and a laser welded outer 3013 container have been tested for residual stresses according to the American Society for Testing Materials (ASTM) Standard G-36-94 [1]. This ASTM standard describes a procedure for conducting stress-corrosion cracking tests in boiling magnesium chloride (MgCl2) solution. Container sections in both the as-fabricated condition as well as the closure welded condition were evaluated. Significantly large residual stresses were observed in the bottom half of the as-fabricated container, a result of the base to can fabrication weld because through wall cracks were observed perpendicular to the weld. This observation indicates that regardless of the closure weld technique, sufficient residual stresses exist in the as-fabricated container to provide the stress necessary for stress corrosion cracking of the container, at the base fabrication weld. Additionally, sufficiently high residual stresses were observed in both the lid and the body of the GTAW as well as the laser closure welded containers. The stresses are oriented perpendicular to the closure weld in both the container lid and the container body. Although the boiling MgCl2 test is not a quantitative test, a comparison of the test results from the closure welds shows that there are noticeably more through wall cracks in the laser closure welded container than in the GTAW closure welded container

Materials for high-level waste containment

International Nuclear Information System (INIS)

Marsh, G.P.

1982-01-01

The function of the high-level radioactive waste container in storage and of a container/overpack combination in disposal is considered. The consequent properties required from potential fabrication materials are discussed. The strategy adopted in selecting containment materials and the experimental programme underway to evaluate them are described. (U.K.)

7 CFR 160.32 - Marking containers.

Science.gov (United States)

2010-01-01

... 7 Agriculture 3 2010-01-01 2010-01-01 false Marking containers. 160.32 Section 160.32 Agriculture... STANDARDS FOR NAVAL STORES Analysis, Inspection, and Grading on Request § 160.32 Marking containers. The interested person shall provide any labor necessary for marking the containers, after the contents have been...

27 CFR 44.254 - Shipping containers.

Science.gov (United States)

2010-04-01

... 27 Alcohol, Tobacco Products and Firearms 2 2010-04-01 2010-04-01 false Shipping containers. 44.254 Section 44.254 Alcohol, Tobacco Products and Firearms ALCOHOL AND TOBACCO TAX AND TRADE BUREAU... Requirements § 44.254 Shipping containers. Each shipping case, crate, or other container, in which cigars are...

Analysis of failures in concrete containments

International Nuclear Information System (INIS)

Moreno-Gonzalez, A.

1989-09-01

The function of Containment, in an accident event, is to avoid the release of radioactive substances into the surroundings. Containment failure, therefore, is defined as the appearance of leak paths to the external environment. These leak paths may appear either as a result of loss of leaktightness due to degradation of design conditions or structural failure with containment material break. This document is a survey of the state of the art of Containment Failure Analysis. It gives a detailed description of all failure mechanisms, indicating all the possible failure modes and their causes, right from failure resulting from degradation of the materials to structural failure and linear breake failure. Following the description of failure modes, possible failure criteria are identified, with special emphasis on structural failure criteria. These criteria have been obtained not only from existing codes but also from the latest experimental results. A chapter has been dedicated exclusively to failure criteria in conventional structures, for the purpose of evaluating the possibility of application to the case of containment. As the structural behaviour of the containment building is very complex, it is not possible to define failure through a single parameter. It is therefore advisable to define a methodology for containment failure analysis which could be applied to a particular containment. This methodology should include prevailing load and material conditions together with the behaviour of complex conditions such as the liner-anchorage-cracked concrete interaction

The Soviet RBMK-1000 containment system

International Nuclear Information System (INIS)

Joosten, J.K.

1988-01-01

Following the accident in April, 1986, considerable attention was focused on the failure of the containment at the Chernobyl RBMK-1000 nuclear power plant. Conflicting statements arose regarding the nature of the plant's containment system primarily because of terminology differences, translation difficulties and lack of reliable information. This article, based on reports and briefings by the Soviet delegation, during the post-accident review meetings in Vienna and prior publications is intended to clarify perceptions of the Soviet RMBK-1000 nuclear power plant containment system design, and its relevance to containment management concepts. (author)

Storage chamber for container of radiation-contaminated material

International Nuclear Information System (INIS)

Takakura, Masahide.

1996-01-01

The present invention concerns a storage chamber for containing radiation-contaminated materials in containing tubes and having cooling fluids circulated at the outer side of the containing tubes. The storage chamber comprises a gas supply means connected to the inside of the container tube for supplying a highly heat-conductive gas and a gas exhaustion means for discharging the gas present in the container tube. When containing vessels for radiation-contaminated materials are contained in the container tube, the gases present inside of the container tube is exhausted by means of the gas exhaustion means, and highly heat conductive gases are filled from the gas supply means to the space between the container tube and the containing vessels for the radiation-contaminated materials. When the temperature of the highly heat conductive gas is elevated due to the heat generation of the radiation-contaminated materials, the container tube is heated, and then cooled by the cooling fluid at the outer side of the container tube. In this case, the heat of the radiation-contaminated material-containing vessels is removed by the heat conduction by the highly heat conductive gas to reduce temperature gradient between the containing vessels and the containing tube. This can enhance the cooling effect. (T.M.)

Sargent and Lundy containment tests revisited

International Nuclear Information System (INIS)

Henry, Robert E.; Hammersley, Robert J.

2005-01-01

The pressurization experiments performed in the intermediate scale Sargent and Lundy containment test facility provide numerous insights into the dominant heat and mass transfer processes under design basis accident conditions similar to a large break Loss of Coolant Accident (LOCA). These experiments were the first integral tests to examine the containment response to a dynamic blowdown from the Reactor Coolant System (RCS). Measurements included the blowdown rate of the simulated Reactor Pressure Vessel (RPV), the pressure in containment as well as the containment temperatures in the top and bottom of the containment vessel. Furthermore, various experiments were performed with the blowdown location changed from the vessel bottom to the lower third of the vessel, the upper third of the vessel and near the top of the RPV to examine the influence of different types of break elevations, i.e. different characterizations of the exhausting steam-water mixture. Perhaps the most insightful set of measurements from these experiments were those that varied the cold water mass initially resident in the bottom of the simulated containment vessel. The role of this water as a function of its initial mass and the break location showed substantial influence of this water if the blowdown location provided sufficient energy to disperse this cold water into the containment building atmosphere. This is demonstrated in Figure 1 taken from Kolflat, 1960. All of these are relevant to an understanding of the dominant physical processes for this type of postulated accident condition. As such, it is important that all of these insights are retained and used in models for the containment building thermal-hydraulic response under accident conditions. Reference: Kolflat, A., 1960, 'Resulting of 1959 Nuclear Power Plant Containment Test', Sargent and Lundy Report SL-1800; Kolflat, A. and Chittenden, W. A., 1957, 'A New Approach to the Design of Containment Shells for Atomic Power Plants

AP1000 Containment Design and Safety Assessment

International Nuclear Information System (INIS)

Wright, Richard F.; Ofstun, Richard P.; Bachere, Sebastien

2002-01-01

The AP1000 is an up-rated version of the AP600 passive plant design that recently received final design certification from the US NRC. Like AP600, the AP1000 is a two-loop, pressurized water reactor featuring passive core cooling and passive containment safety systems. One key safety feature of the AP1000 is the passive containment cooling system which maintains containment integrity in the event of a design basis accident. This system utilizes a high strength, steel containment vessel inside a concrete shield building. In the event of a pipe break inside containment, a high pressure signal actuates valves which allow water to drain from a storage tank atop the shield building. Water is applied to the top of the containment shell, and evaporates, thereby removing heat. An air flow path is formed between the shield building and the containment to aid in the evaporation and is exhausted through a chimney at the top of the shield building. Extensive testing and analysis of this system was performed as part of the AP600 design certification process. The AP1000 containment has been designed to provide increased safety margin despite the increased reactor power. The containment volume was increased to accommodate the larger steam generators, and to provide increased margin for containment pressure response to design basis events. The containment design pressure was increased from AP600 by increasing the shell thickness and by utilizing high strength steel. The passive containment cooling system water capacity has been increased and the water application rate has been scaled to the higher decay heat level. The net result is higher margins to the containment design pressure limit than were calculated for AP600 for all design basis events. (authors)