Promoting radiation protection and safety for X-ray inspection systems

International Nuclear Information System (INIS)

Maharaj, Harri P.

2008-01-01

This paper aims to present a regulatory perspective on radiation protection and safety relevant to facilities utilizing baggage X-ray inspection systems. Over the past several years there has been rapid growth in the acquisition and utilization of X-ray tube based inspection systems for security screening purposes worldwide. In addition to ensuring compliance with prescribed standards applicable to such X-ray systems, facilities subject to federal jurisdiction in Canada are required to comply with established codes of practice, which, not only are in accordance with occupational health and safety legislation but also are consistent with international guidance. Overall, these measures are aimed at reducing radiation risks and adverse health effects. Data, acquired in the past several years in a number of facilities through various instruments, namely, monitoring and surveillance, radiation safety audits, onsite evaluations, device registration processes and information developed, were considered in conjunction with detrimental traits. Changes are necessary to reduce radiation and safety risks from both an ALARA point of view and an accountability perspective. Establishing, developing, implementing and following a radiation protection program is warranted and advocated. Minimally, such a program shall be managed by a radiation safety officer. It shall promote and sustain a radiation safety culture in the workplace; shall ensure properly qualified individuals operate and service the X-ray systems in accordance with established and authorized procedures; and shall incorporate data recording and life cycle management principles. Such a program should be the norm for a facility that utilizes baggage X-ray inspection systems for security purposes, and it shall be subject to continuous regulatory oversight. (author)

Fuel element box inspection device

International Nuclear Information System (INIS)

Ortmayer, R.M.; Pick, W.

1985-01-01

The invention concerns a device for inspecting the outer geometry of a long fuel element box by measuring the surface contours over its longitudinal crossection and along its length by sensors. These are kept in a sledge which can be moved along the fuel element guide in a slot guide. The measurement signals reach an evaluation device outside the longitudinal box. (orig./HP) [de

Manipulator arm for a nuclear reactor vessel inspection device

International Nuclear Information System (INIS)

1980-01-01

A manipulator arm for a reactor vessel in-service inspection apparatus is adapted to transport a transducer array for ultrasonic examination of welds at any point in the vessel. The removal of the inspection device from the reactor vessel in an emergency presents a problem where a relatively long manipulator arm is used. This invention provides an improved arm with means for changing the normal orientation of the arm to a shorter one to permit safe removal of the inspection device from the reactor vessel. (author)

Monitor inspection device

International Nuclear Information System (INIS)

Ueshima, Yoshinobu.

1995-01-01

The device of the present invention reliably conducts monitoring by radiation monitors in a nuclear power plant thereby contributing to save the number of radiation operators and reduction of radiation exposure. Namely, radiation monitors continuously measure a plurality of γ-ray levels. A branched simultaneously counting circuit receives these signals. The output of the branched simultaneously counting circuit is inputted to a differentiation means. The differentiation means calculates a variation coefficient for each of the radiation monitoring values, namely, equivalent dose rates, and records and monitors change with time of the equivalent dose rates. With such procedures, the results of the monitoring of γ-ray levels can be judged objectively corresponding to the increase of the equivalent dose rates. As a result, the number of radiation operators can be saves and radiation exposure of the radiation operators can be reduced. (I.S.)

Device for inspecting the inside of a nuclear reactor

International Nuclear Information System (INIS)

Kurata, Masuo.

1985-01-01

Purpose: To apply illumination concentrically to a particular place and enable rapid and accurate inspection for the detailed portions by making such that the viewing direction of a television camera disposed in water and the direction of illumination of a submerged illumination tool can be varied optionally by remote control. Constitution: In the conventional inspection equipments for the inside of the reactor, a submerged illumination tool has merely been suspended by a cable and it has been difficult to effectively control the relative position with the television camera disposed in water. In this invention, the television camera disposed in water and a submerged illumination tool are rotatably disposed by way of a clamp to an inspection device main body. Then, the clamp can be rotated by the remote control and, further, the inspection device is suspended by way of a rope from a winding device disposed above the pressure vessel. In such a constitution, the submerged illumination tool can be adjusted to an optimal position to the television camera disposed in water. (Kamimura, M.)

Non fuel bearing component(NFBC) inspection device

International Nuclear Information System (INIS)

Kurokawa, Hideyuki; Kosaka, Tatsuya.

1994-01-01

The device of the present invention continuously inspects the length and abrasion/corrosion states for a plurality of non-fuel bearing components (NFBC) under water in a pit. That is, the device comprises the following components. Two sets of frames are planted vertically on a pit wall. A support stand capable of opening and closing is disposed at the upper portion of the frame to sustain each control rods of the NFBC. An abrasion/corrosion measuring tool is disposed vertically movably on the frame at the lower portion of the support stand for detecting abrasion/corrosion states on the surface of each of the fuel rods. A lifting device is disposed outside of the pit for lifting the abrasion/corrosion measuring tools. The measuring tool is disposed vertically movably at a lower portion of the frame for measuring the length of each of the control rods. Then NFBCs are inserted and positioned reliably underwater in the pit, the length of the NFBCs and the abrasion/corrosion states on the surface of the control rod can be observed, the inspecting tools can be exchanged easily since the support stand is capable of opening and closing, and the inspection can be made continuously because of the dual structure according to the present invention. (I.S.)

Operation control device under radiation exposure

International Nuclear Information System (INIS)

Kimura, Kiichi; Murakami, Toichi.

1994-01-01

The device of the present invention performs smooth progress of operation by remote control for a plurality of operations in periodical inspections in controlled areas of a nuclear power plant, thereby reducing the operator's exposure dose. Namely, the device monitors the progressing state of the operation by displaying the progress of operation on a CRT of a centralized control device present in a low dose area remote from an operation field through an ITV camera disposed in the vicinity of the operation field. Further, operation sequence and operation instruction procedures previously inputted in the device are indicated to the operation field through an operation instruction outputting device (field CRT) in accordance with the progress of the operation steps. On the other hand, the operation progress can be aided by inputting information from the operation field such as start or completion of the operation steps. Further, the device of the present invention can monitor the change of operation circumstances and exposure dose of operators based on the information from a radiation dose measuring device disposed in the operation circumstance and to individual operators. (I.S.)

Inspection device for buried equipment

International Nuclear Information System (INIS)

Hanawa, Jun.

1994-01-01

In an inspection device for a buried equipment, a rail is suspended at the upper portion of a vessel of a pit-vessel type pump buried in a plant building floor, and a truck movable vertical in the vessel along the rail, and an ultrasonic wave probe contained in the truck and urged to the vessel by an electromagnet are disposed. In addition, an elevator moving vertically along a shaft is disposed, and an arm having the ultrasonic probe disposed at the end portion and driven by a piston are disposed to the elevator. The ultrasonic wave probe moves vertically together with the truck along the rail in the vessel while being urged to the vessel by the electromagnet to inspect and measure the state at the inner and outer surfaces of the vessel. Further, the length of the arm is controlled so as to set a predetermined distance between the ultrasonic wave probe and the vessel. Subsequently, the elevator is moved vertically along a shaft passing through a shaft hole of a mount, and the shaft is rotated thereby enabling to inspect and measure the state of the inner and outer surfaces of the vessel. (N.H.)

Regulatory inspections in nuclear plants in the field of radiation protection

International Nuclear Information System (INIS)

Hort, M.; Fuchsova, D.

2014-01-01

State Office for Nuclear Safety executes state administration and performs inspections at peaceful use of nuclear energy and ionizing radiation in the field of radiation protection and nuclear safety. Inspections on radiation protection at nuclear power plants are secured by inspectors of the Department of Radiation Protection in Fuel Cycle, who work at the Regional centre Brno and Ceske Budejovice. (authors)

Development of automated ultrasonic device for in-service inspection of ABWR pressure vessel bottom head

International Nuclear Information System (INIS)

Kojima, Y.; Matsuyama, A.

1995-01-01

An automated device and its controller have been developed for the bottom head weld examination of pressure vessel of Advanced Boiling Water Reactor (ABWR). The internal pump casings and the housings of control rod prevent a conventional ultrasonic device from scanning the required inspection zone. With this reason, it is required to develop a new device to examine the bottom head area of ABWR. The developed device is characterized by the following features. (1) Composed of a mother vehicle and a compact inspection vehicle. They are connected only by an electric wire without using the conventional arm mechanism. (2) The mother vehicle travels on a track and lift up the inspection vehicle to the vessel. (3) The mother vehicle can automatically attach the inspection vehicle to the bottom head, and detach the inspection vehicle from it. (4) Collision avoidance control function with a touch sensor is installed at the front of the inspection vehicle. The device was successfully demonstrated using a mock-up of reactor pressure vessel

Application of ICT in the non-destructive inspection of explosive device

International Nuclear Information System (INIS)

Wang Zhe; Li Tiantuo; Liu Zhiqiang; Pei Zhihua; Wang Zhiping

2003-01-01

The inspection of explosive device is an important task in the store of the weapons. The technique of non-destructive examination with radial, especially the ICT, is an effective method. The paper mainly introduces the design and the theories on the inspection system and software system of the application of industrial ICT in the non-destructive examination of explosive device, and gives a reference to the work in such fields

Radiation protection and safety guide no. GRPB-G-4: inspection

International Nuclear Information System (INIS)

Schandorf, C.; Darko, O.; Yeboah, J.; Osei, E.K.; Asiamah, S.D.

1995-01-01

The use of ionizing radiation and radiation sources in Ghana is on the increase due to national developmental efforts in Health Care, Food and Agriculture, Industry, Science and Technology. This regulatory Guide has been developed to assist both the Regulatory Body (Radiation Protection Board) and operating organizations to perform systematic inspections commensurate with the level of hazard associated with the application of radiation sources and radioactive materials. The present Guide applies to the Radiation Protection and Safety inspection and/or audit conducted by the Radiation Protection Board or Radiation Safety Officer. The present Guide is applicable in Ghana and to foreign suppliers of radiation sources. The present Guide applies to notifying person, licensee, or registrant and unauthorized practice

System for inspection of stacked cargo containers

Science.gov (United States)

Derenzo, Stephen [Pinole, CA

2011-08-16

The present invention relates to a system for inspection of stacked cargo containers. One embodiment of the invention generally comprises a plurality of stacked cargo containers arranged in rows or tiers, each container having a top, a bottom a first side, a second side, a front end, and a back end; a plurality of spacers arranged in rows or tiers; one or more mobile inspection devices for inspecting the cargo containers, wherein the one or more inspection devices are removeably disposed within the spacers, the inspection means configured to move through the spacers to detect radiation within the containers. The invented system can also be configured to inspect the cargo containers for a variety of other potentially hazardous materials including but not limited to explosive and chemical threats.

Assessment of patient radiation protection in external radiotherapy departments after inspections performed by the ASN 2008

International Nuclear Information System (INIS)

Franchi, Vincent; Marchal, Carole

2009-10-01

This report proposes an assessment of patient radiation protection in external radiotherapy. It is based on inter-regional syntheses of inspections performed by the ASN in external radiotherapy departments during 2008. It addresses 6 main themes related to patient radiation protection: human and material resources, organisation of medical physics, training in patient radiation protection, mastering of equipment (maintenance, internal quality controls of medical devices), safety and care quality management (formalization of the patient care process and definition of responsibilities, patient identity control, treatment preparation, and treatment execution), and risk management (a priori risk analysis, declaration, recording and internal processing of dysfunctions, improvements of care quality and safety management system)

Development of Yb-169 radiation source for new nondestructive inspection

International Nuclear Information System (INIS)

Yamabayashi, Hisamichi

1994-01-01

As the nondestructive inspection method for large structures, there has been radiography, and X-ray and γ-ray have been used as the radiation. The transmissivity of radiation through materials changes by the energy of the radiation and the density and thickness of the materials. At present about 880 γ-ray radiography apparatuses are used in Japanese private enterprises, and about 70% of them use 192 Ir γ-ray sources, and about 30% use 60 Co or 137 Cs sources. Recently the defect inspection for the worlded parts of thin wall small tubes and so on have become to be regarded as important, and the 169 Yb source that emits lower energy γ-ray is suitable to the purpose. There are many reports that 169 Yb radiography was applied successfully. As the 169 Yb radiation source, pellets and balls are on the market. 169 Yb is made by the neutron irradiation of 168 Yb in nuclear reactors. The characteristics of 169 Yb, the manufacture of 169 Yb radiation sources and the applicability of 169 Yb radiation sources to nondestructive inspection are reported. Also in Japan, many basic experiments on 169 Yb radiation sources have been carried out, and the irradiation apparatuses are small and light, and the control area can be set small. (K.I.)

Underwater inspection training in intense radiation field

International Nuclear Information System (INIS)

Taniguchi, Ryoichi

2017-01-01

Osaka Prefecture University has a large dose cobalt 60 gamma ray source of about 2 PBq, and is engaged in technological training and human resource development. It is assumed that the decommissioning underwater operation of Fukushima Daiichi Nuclear Power Station would be the focus. The university aims at acquisition of the basic of underwater inspection work under radiation environment that is useful for the above purpose, radiation measurement under water, basic training in image measurement, and aims as well to evaluate the damage of imaging equipment due to radiation, and master practical knowledge for the use of inspection equipment under a large dose. In particular, it is valuable to train in the observation of Cherenkov light emitted from a large dose cobalt radiation source in water using a high sensitivity camera. The measurement of radiation dose distribution in water had difficulty in remote measurement due to water shielding effect. Although it took much time before, the method using high sensitivity camera is easy to sequentially perform two-dimensional measurement, and its utility value is large. Its effect on the dose distribution measurement of irregularly shaped sources is great. The contents of training includes the following: radiation source imaging in water, use of a laser rangefinder in water, dose distribution measurement in water and Cherenkov light measurement, judgment of equipment damage due to irradiation, weak radiation measurement, and measurement and decontamination of surface contamination. (A.O.)

Device for remote inspection and testing of a structure

International Nuclear Information System (INIS)

Blanc, B.; Boudou, J.; Castaing, A.; Clasquin, J.; Gallet, B.; Saglio, R.; Samoel, A.

1976-01-01

A self-propelled carriage for inspecting the primary vessel of a fast reactor is capable of displacement within the interspace between the primary vessel and the containment vessel in order to inspect and test any predetermined zone of the primary vessel, the carriage being associated with a drive mechanism and applied against the oppositely facing wall of the containment vessel. The carriage is suspended from a composite cable actuated by a handling apparatus for introducing the carriage into the interspace and withdrawing it therefrom. The composite cable supplies electric power as well as the different fluids required for positioning and operation of the inspection devices which are mounted on the carriage. 9 claims, 6 drawing figures

GRI testing facility available for pipeline inspection devices

International Nuclear Information System (INIS)

Anon.

1990-01-01

As part of a program to help improve detection and characterization of defects that may occur in pipelines, the Gas Research Institute has announced the completion of the first phase of a testing facility for the evaluation of new and existing pipeline inspection technologies. GRI is a private, not-for-profit membership organization based in Chicago. The first phase of the facility consists of a pull rig which includes four 300-foot lengths of pipe with diameters of 12, 24, 30, and 36 inches. NDE inspection devices can be pulled through these pipe segments by a winch at speeds up to 25 miles per hour

Radiation effects in optoelectronic devices

International Nuclear Information System (INIS)

Barnes, C.E.

1977-03-01

A summary is given of studies on radiation effects in light-emitting diodes, laser diodes, detectors, optical isolators and optical fibers. It is shown that the study of radiation damage in these devices can provide valuable information concerning the nature of the devices themselves, as well as methods of hardening these devices for applications in radiation environments

Effectiveness of X-ray grating interferometry for non-destructive inspection of packaged devices

Science.gov (United States)

Uehara, Masato; Yashiro, Wataru; Momose, Atsushi

2013-10-01

It is difficult to inspect packaged devices such as IC packages and power modules because the devices contain various components, such as semiconductors, metals, ceramics, and resin. In this paper, we demonstrated the effectiveness of X-ray grating interferometry (XGI) using a laboratory X-ray tube for the industrial inspection of packaged devices. The obtained conventional absorption image showed heavy-elemental components such as metal wires and electrodes, but the image did not reveal the defects in the light-elemental components. On the other hand, the differential phase-contrast image obtained by XGI revealed microvoids and scars in the encapsulant of the samples. The visibility contrast image also obtained by XGI showed some cracks in the ceramic insulator of power module sample. In addition, the image showed the silicon plate surrounded by the encapsulant having the same X-ray absorption coefficient. While these defects and components are invisible in the conventional industrial X-ray imaging, XGI thus has an attractive potential for the industrial inspection of the packaged devices.

Operation aid device upon periodical inspection of nuclear power plant

International Nuclear Information System (INIS)

Fukusaka, Ryoji.

1997-01-01

The present invention provides an operation aid device upon periodical inspection of a nuclear power plant, capable of controlling a plurality of control rods safely at good operation efficiency while maintaining subcritical state. Namely, a fuel exchange computer controls an operation for exchanging fuel assemblies upon periodical inspection. An operation aiding computer aids the exchanging operation of fuel assemblies. A control rod position monitoring device allows withdrawal of one control rod under the condition of establishment of entire control rod insertion signal upon operation of exchanging fuel assemblies. Whether all of the four fuel assemblies around one control rod have been entirely taken out or not is judged based on information on the fuel assembly exchanging operation. When conditions for the judgement for operation aiding computer are established, the all insertion signals for the entire control rods as the condition for the withdrawal of the control rods are bypassed, and operation enable signals for plurality control rods are outputted to a control rod manual operation device. (I.S.)

MIR: an in-service inspection device for Superphenix 1 vessels

International Nuclear Information System (INIS)

Asty, M.; Ceccato, S.; Lerat, B.; Viard, J.

1986-06-01

The main and safety vessels of SUPERPHENIX 1 were designed to allow in-service inspections. The remote controlled inspection device MIR was developed for this purpose. It allows both visual and ultrasonic examinations to be performed. Basically, MIR consists of a tetrahedral structure provided with four steering and traction wheels, two for each vessel. A computer assisted control system enables it to be driven to any position on either the main or safety vessels. Operating conditions are briefly reviewed and the main features of MIR presented

Radiation analysis devices, radiation analysis methods, and articles of manufacture

Science.gov (United States)

Roybal, Lyle Gene

2010-06-08

Radiation analysis devices include circuitry configured to determine respective radiation count data for a plurality of sections of an area of interest and combine the radiation count data of individual of sections to determine whether a selected radioactive material is present in the area of interest. An amount of the radiation count data for an individual section is insufficient to determine whether the selected radioactive material is present in the individual section. An article of manufacture includes media comprising programming configured to cause processing circuitry to perform processing comprising determining one or more correction factors based on a calibration of a radiation analysis device, measuring radiation received by the radiation analysis device using the one or more correction factors, and presenting information relating to an amount of radiation measured by the radiation analysis device having one of a plurality of specified radiation energy levels of a range of interest.

Analysis of Radiation Accident of Non-destructive Inspection and Rational Preparing Bills

International Nuclear Information System (INIS)

Bae, Junwoo; Yoo, Donghan; Kim, Hee Reyoung

2013-01-01

After 2006, according to enactment of Non-destructive Inspection Promotion Act, the number of non-destructive inspection companies and corresponding accident is increased sharply. In this research, it includes characteristic analysis of field of the non-destructive inspection. And from the result of analysis, the purpose of this research is discovering reason for 'Why there is higher accident ratio in non-destructive inspection field, relatively' and preparing effective bill for reducing radiation accidents. The number of worker for non-destructive inspect is increased steadily and non-destructive inspect worker take highest dose. Corresponding to these, it must be needed to prepare bills to protect non-destructive inspect workers. By analysis of accident case, there are many case of carelessness that tools are too heavy to carry it everywhere workers go. And there are some cases caused by deficiency of education that less understanding of radiation and poor operation by less understanding of structure of tools. Also, there is no data specialized to non-destructive inspect field. So, it has to take information from statistical data. Because of this, it is hard to analyze nondestructive inspect field accurately. So, it is required to; preparing rational bills to protect non-destructive inspect workers nondestructive inspect instrument lightening and easy manual which can understandable for low education background people accurate survey data from real worker. To accomplish these, we needs to do; analyze and comprehend the present law about non-destructive inspect worker understand non-destructive inspect instruments accurately and conduct research for developing material developing rational survey to measuring real condition for non-destructive inspect workers

9 CFR 312.3 - Official marks and devices to identify inspected and passed equine products.

Science.gov (United States)

2010-01-01

... inspected and passed equine products. 312.3 Section 312.3 Animals and Animal Products FOOD SAFETY AND... § 312.3 Official marks and devices to identify inspected and passed equine products. (a) The official... § 317.2 of this subchapter to identify inspected and passed mule and other (nonhorse) equine carcasses...

Process and device for remote inspection of parts of a nuclear plant

International Nuclear Information System (INIS)

Schmalfuss, H.

1987-01-01

The process is suitable for remote position inspection of the parts of the plant in a large hot cell, for example of a reprocessing plant. A device with a TV camera was selected as the inspection system, where pictures obtained by photography are compared (photogrammetry). The possible resolution is considerably increased by using two spatially movable separate picture systems with the associated drawing media. (DG) [de

Apparatus for locating inspection device in a nuclear reactor vessel

International Nuclear Information System (INIS)

1980-01-01

A method for accurately locating an inspection device with a PWR or BWR pressure vessel uses a plurity of guide members and an internal location element, the exact position of which is known. Used for defining the size, orientation and position of a flow. (U.K.)

Cecil gives in-bundle access for inspection and lancing [steam generators

International Nuclear Information System (INIS)

Trovato, S.A.; Ruggieri, S.K.

1989-01-01

Cecil (Consolidated Edison Combined Inspection and Lancing System) is a robotic device which makes it possible to take inspection and sludge lancing equipment deep inside steam generator tube bundles. Cecil is teleoperated to perform tube bundle inspections, sludge sampling and sludge lancing. The first field test of Cecil at Indian Point 2 reactor, successfully demonstrated its capability for high quality inspection, and its potential for improved sludge removal, both with reduced personnel radiation exposure. (U.K.)

Probabilistic safety analysis about the radiation risk for the driver in a fast-scan container/vehicle inspection system

International Nuclear Information System (INIS)

Li Junli; Zhu Guoping; Ming Shenjin; Cao Yanfeng

2008-01-01

A new Container/Vehicle Inspection System called fast-scan inspection system has been developed and used in some countries, which has a special advantage in scanning efficiency of 200 - 400 containers per hour. However, for its unique scanning mode, the fast-scan inspection system causes some worries about the radiation risk for the truck drivers, who will drive the container truck to pass through the scanning tunnel and might be exposed by the radiation beam in accidents. A PSA analysis, which has been widely used to evaluate the safety of nuclear power plant in the past, is presented here to estimate the probability of accidental exposure to the driver and evaluate the health risk. The fault tree and event tree analysis show that the probability of accidental exposure to the driver is pretty low and the main failure contributions are human errors and scanning control devices failures, which provides some recommendations for the further improvement about this product. Furthermore, on the basic of ICRP No.60 and 76 reports, the health risk to the truck driver is only about 4.0x10 -14 /a. Compared with the exempt level of 5x10 -7 /a, it can be concluded that the fast-scan system is safe enough for the truck driver. (author)

Status of radiation protection in interventional radiology. Assessment of inspections in 2009 by the ASN

International Nuclear Information System (INIS)

2011-01-01

This report first describes the organization of inspections performed in health institutions, indicates the inspected establishments, the types of fixed installations in interventional radiology, the use of imagery in the operating theatre, and discusses the regulatory arrangements applicable to interventional radiology (in the Public Health Code, in the Labour Code). Then, the report discusses the results of inspections regarding radiation protection in interventional radiology: application of public health code arrangements (justification, patient training in radiation protection, radiological procedures and protocols, patient dosimetry monitoring), application of Labour Code arrangements (designation of the person with expertise in radiation protection, risk assessment and delimitation of monitored and controlled areas, workstation analysis, workers' training in radiation protection, individual protection equipment, workers' dosimetric monitoring, workers' medical monitoring, radiation protection technical controls), significant events, radiation protection in operating theatre. Propositions are stated regarding the differences noticed within or between the health establishments, the methodological and organisational difficulties faced by persons with expertise in radiation protection (PCR), the need of an interdisciplinary team

Radiological protection requirements applicable to non-invasive inspection of charges with ionizing radiation

International Nuclear Information System (INIS)

Crespo, S.C.; Palmieri, J.A.S.; Silva, F.C.A. da

2017-01-01

The US twin towers attack in 2001 raised concerns about terrorism, illicit trafficking of materials and the possible use of a 'dirty bomb' (DDR), affecting the control of entry and exit of products. Thus, the use of ionizing radiation scanning systems of containers at ports and borders was started to investigate possible entries of illegal material. Brazil, adhering to this concern and due to the holding of major events such as RIO + 20, World Cup, Olympics, etc., increased safety in the movement of goods using non-invasive inspection. Linear electron accelerators, which produce high energy X-rays in the range of 1.5 to 9 MeV, are used to inspect the containers. Since in Brazil there is no specific technical regulation for the operation of non-invasive inspection equipment with X-rays and linear accelerators, ten main technical requirements are presented. It is essential that a technical regulation is drawn up by placing the system of non-invasive inspection of cargo with ionizing radiation in the international radiation protection standard

Radiation effects in optoelectronic devices

International Nuclear Information System (INIS)

Barnes, C.E.; Wiczer, J.J.

1984-05-01

Purpose of this report is to provide not only a summary of radiation damage studies at Sandia National Laboratories, but also of those in the literature on the components of optoelectronic systems: light emitting diodes (LEDs), laser diodes, photodetectors, optical fibers, and optical isolators. This review of radiation damage in optoelectronic components is structured according to device type. In each section, a brief discussion of those device properties relevant to radiation effects is given

MINAC, A new radiographic inspection capability

International Nuclear Information System (INIS)

Lapides, M.E.; Schonberg, R.

1983-01-01

In service, radiographic inspection of thick section, metallic components has historically been limited to the capabilities of radioisotopic sources such as cobalt and iridium. Although practical in many applications, these sources tend to be restricted by output intensity, by resolution obtainable, and by the physical size and weight of necessary transport shielding. In nuclear plant applications, any radiography is also frequently inhibited by the presence of a radiation background from activated corrosion products on the inspection object which may fog the film before the desired exposure is achieved. In recognition of these limitations and the need for improved capability in the conduct of mandated ten-year inspection of U.S. nuclear plant components such as reactor coolant pumps, pressure vessel nozzles and valve bodies, the Electric Power Research Institute (EPRI) undertook the development of a high energy, X-ray device appropriate for in service inspection of thick section (up to approximately 30 cm of steel) components. The development was conducted by Schonberg Radiation (U.S.A). The product, MINAC, a miniaturized linear accelerator system, has been in use in many plant inspections since April 1981. This paper describes the development and typical applications of MINAC

Development of the radiation inspection system for food materials

Energy Technology Data Exchange (ETDEWEB)

Min, Sujung; Kim, Heeyoung; Kim, Myungjin; Lee, Unjang [ORIONENC Co., Seoul (Korea, Republic of)

2015-10-15

Radioactive contamination of processed foodstuffs, livestock, marine products, farm products imported from Japan and fishes caught in coastal waters of Korea has become an important social issue. Recently, there are also needs of inspection system for monitoring of public meals such like school feedings of kindergarten, elementary school, middle school, high school and university. Radioactivity inspections of those foods are executed manually with portable measuring instruments or at labs using their samples. But, radioactivity inspections of those foods should execute field survey in real time. In consequence, there are some problem of time delay and low reliability. To protect the health of citizens from radioactivity contained in Japanese marine products imported to Korea, a system to inspect radioactivity in real time is developed. The system is to measure the radioactivity level of farm and marine products and public meals continuously and automatically at inspection sites of an agency checking radiation of imported foodstuffs to determine radioactive contamination. Performance was identified through the performance test (Cs-137 30, 50, 300, 900Bq/kg) at Korea Research Institute of Standards and Science (KRISS). NaI(Tl) detector was satisfied the performance for measurement.

Development of the radiation inspection system for food materials

International Nuclear Information System (INIS)

Min, Sujung; Kim, Heeyoung; Kim, Myungjin; Lee, Unjang

2015-01-01

Radioactive contamination of processed foodstuffs, livestock, marine products, farm products imported from Japan and fishes caught in coastal waters of Korea has become an important social issue. Recently, there are also needs of inspection system for monitoring of public meals such like school feedings of kindergarten, elementary school, middle school, high school and university. Radioactivity inspections of those foods are executed manually with portable measuring instruments or at labs using their samples. But, radioactivity inspections of those foods should execute field survey in real time. In consequence, there are some problem of time delay and low reliability. To protect the health of citizens from radioactivity contained in Japanese marine products imported to Korea, a system to inspect radioactivity in real time is developed. The system is to measure the radioactivity level of farm and marine products and public meals continuously and automatically at inspection sites of an agency checking radiation of imported foodstuffs to determine radioactive contamination. Performance was identified through the performance test (Cs-137 30, 50, 300, 900Bq/kg) at Korea Research Institute of Standards and Science (KRISS). NaI(Tl) detector was satisfied the performance for measurement

Radiation area monitor device and method

Science.gov (United States)

Vencelj, Matjaz; Stowe, Ashley C.; Petrovic, Toni; Morrell, Jonathan S.; Kosicek, Andrej

2018-01-30

A radiation area monitor device/method, utilizing: a radiation sensor; a rotating radiation shield disposed about the radiation sensor, wherein the rotating radiation shield defines one or more ports that are transparent to radiation; and a processor operable for analyzing and storing a radiation fingerprint acquired by the radiation sensor as the rotating radiation shield is rotated about the radiation sensor. Optionally, the radiation sensor includes a gamma and/or neutron radiation sensor. The device/method selectively operates in: a first supervised mode during which a baseline radiation fingerprint is acquired by the radiation sensor as the rotating radiation shield is rotated about the radiation sensor; and a second unsupervised mode during which a subsequent radiation fingerprint is acquired by the radiation sensor as the rotating radiation shield is rotated about the radiation sensor, wherein the subsequent radiation fingerprint is compared to the baseline radiation fingerprint and, if a predetermined difference threshold is exceeded, an alert is issued.

Radiation flux measuring device

International Nuclear Information System (INIS)

Corte, E.; Maitra, P.

1977-01-01

A radiation flux measuring device is described which employs a differential pair of transistors, the output of which is maintained constant, connected to a radiation detector. Means connected to the differential pair produce a signal representing the log of the a-c component of the radiation detector, thereby providing a signal representing the true root mean square logarithmic output. 3 claims, 2 figures

Development of inspection equipment for fuel bundles of CANDU-PHWR using R981 underwater radiation tolerant camera

Energy Technology Data Exchange (ETDEWEB)

Koo, Dae-Seo; Cho, Moon-Sung; Jo, Chang-Keun; Jun, Ji-Su; Jung, Jong Yeob; Park, Kwang-June; Suk, Ho-Chun

2005-03-15

The inspection equipment of fuel bundles was developed, which could perform visual inspection and dimensional measurement on fuel bundles of CANDU-PHWR, to evaluate, analyze the defective behavior of fuel bundles and inner surface of pressure tubes of inherent two-phase flow over 24kg/s in CANDU-6. The R981 radiation tolerant camera system with pan and tilt function was ordered and manufactured, which was waterproof, shielding radiation in underwater 10m in depth. The performance test, of the system ,due to camera-object distance was carried out in air/underwater atmosphere. The results of performance test of R981 radiation tolerant camera system are good. The inspection equipment of fuel bundles using R981 radiation tolerant camera system and underwater-radiation tolerant LVDT sensor(D5/200AW) was fabricated, which could perform visual inspection and dimensional measurement on fuel bundles of CANDU-PHWR with measurement accuracy 10{mu}m. This equipment will be utilizable integrity evaluation of fuel bundles which are irradiated in pressure tube of CANDU-PHWR.

Silicon solid state devices and radiation detection

CERN Document Server

Leroy, Claude

2012-01-01

This book addresses the fundamental principles of interaction between radiation and matter, the principles of working and the operation of particle detectors based on silicon solid state devices. It covers a broad scope with respect to the fields of application of radiation detectors based on silicon solid state devices from low to high energy physics experiments including in outer space and in the medical environment. This book covers stateof- the-art detection techniques in the use of radiation detectors based on silicon solid state devices and their readout electronics, including the latest developments on pixelated silicon radiation detector and their application.

Radiation ray measuring device

International Nuclear Information System (INIS)

Maekawa, Tatsuyuki; Ida, Masaki.

1997-01-01

The present invention provides a chained-radiation ray monitoring system which can be applied to an actual monitoring system of a nuclear power plant or the like. Namely, this device comprises a plurality of scintillation detectors. Each of the detectors has two light take-out ports for emitting light corresponding to radiation rays irradiated from the object of the measurement to optical fibers. In addition, incident light from the optical fiber by way of one of the light take-out optical ports is transmitted to the other of the ports and sent from the other optical port to the fibers. Plurality sets of measuring systems are provided in which each of the detectors are disposed corresponding to a plurality of objects to be measured. A signal processing device is (1) connected with optical fibers of plurality sets of measuring systems in conjunction, (2) detects the optical pulses inputted from the optical fibers to identify the detector from which the optical pulses are sent and (3) measures the amount of radiation rays detected by the identified detector. As a result, the device of the present invention can form a measuring system with redundancy. (I.S.)

Radiation-Tolerance Assessment of a Redundant Wireless Device

Science.gov (United States)

Huang, Q.; Jiang, J.

2018-01-01

This paper presents a method to evaluate radiation-tolerance without physical tests for a commercial off-the-shelf (COTS)-based monitoring device for high level radiation fields, such as those found in post-accident conditions in a nuclear power plant (NPP). This paper specifically describes the analysis of radiation environment in a severe accident, radiation damages in electronics, and the redundant solution used to prolong the life of the system, as well as the evaluation method for radiation protection and the analysis method of system reliability. As a case study, a wireless monitoring device with redundant and diversified channels is evaluated by using the developed method. The study results and system assessment data show that, under the given radiation condition, performance of the redundant device is more reliable and more robust than those non-redundant devices. The developed redundant wireless monitoring device is therefore able to apply in those conditions (up to 10 M Rad (Si)) during a severe accident in a NPP.

Radiation sterilization of medical devices

International Nuclear Information System (INIS)

Kaluska, I.; Stuglik, Z.

1996-01-01

Overview of sterilization methods of medical devices has been given, with the special stress put on radiation sterilization. A typical validation program for radiation sterilization has been shown and also a comparison of European and ISO standards concerning radiation sterilization has been discussed. (author). 13 refs, 1 fig., 2 tabs

Development of the module inspection system for new standardized radiation monitoring modules

International Nuclear Information System (INIS)

Furukawa, Masami; Shimizu, Kazuaki; Hiruta, Toshihito; Mizugaki, Toshio; Ohi, Yoshihiro; Chida, Tooru.

1994-10-01

This report mentions about the module inspection system which does the maintenance check of the monitoring modules adapted the new monitoring standard, as well as the result of the verification of the modules. The module inspection system is the automatic measurement system with the computer. The system can perform the functional and the characteristic examination of the monitoring modules, the calibration with radiation source and inspection report. In the verification of the monitoring module, three major items were tested, the adaptability for the new monitoring standard, the module functions and each characteristics. All items met the new monitoring standard. (author)

Radiation monitoring device

International Nuclear Information System (INIS)

Sato, Toshifumi.

1993-01-01

The device of the present invention concerns a reactor start-up region monitor of a nuclear power plant. In an existent start-up region monitor, bias voltage is limited, if the reactor moves to a power region, in order to prevent degradation of radiation detectors. Accordingly, since the power is lower than an actual reactor power, the reactor power can not be monitored. The device of the present invention comprises a memory means for previously storing a Plateau's characteristic of the radiation detectors and a correction processing means for obtaining a correction coefficient in accordance with the Plateau's characteristic to correct and calculate the reactor power when the bias voltage is limited. With such a constitution, when the reactor power exceeds a predetermined value and the bias voltage is limited, the correction coefficient can be obtained by the memory means and the correction processing means. Corrected reactor power can also be obtained from the start-up region monitor by the correction coefficient. As a result, monitoring of the reactor power can be continued while preventing degradation of the radiation detector even if the bias voltage is limited. (I.S.)

Radiation effects in charge coupled devices

International Nuclear Information System (INIS)

Williams, R.A.; Nelson, R.D.

1975-01-01

Charge coupled devices (CCD s) exhibit a number of advantages (low cost, low power, high bit density) in their several applications (serial memories, imagers, digital filters); however, fairly elementary theoretical considerations indicate that they will be very vulnerable to permanent radiation damage, by both neutrons and ionizing radiation, and to transient upset by pulsed ionizing radiation. Although studies of permanent ionizing-radiation damage in CCD's have been reported, little information has been published concerning their overall nuclear radiation vulnerability. This paper presents a fairly comprehensive experimental study of radiation effects in a 256-cell surface-channel, CCD shift-register. A limited amount of similar work is also presented for a 128-cell surface-channel device and a 130 cell peristaltic CCD shift register. The radiation effects phenomena discussed herein, include transient-ionizing-radiation responses, permanent ionizing- radiation damage to transfer efficiency, charge-carrying capacity and input transfer gate bias, and neutron damage to storage time--determined from dark current and charge-up time measurements

Applications of the energy differentiation type radiation line sensor to such as inspection for the plumbing corrosion

International Nuclear Information System (INIS)

Tomita, Yasuhiro; Shirayanagi, Yuji; Matsui, Shinjiro; Kamiya, Yosuke; Kobayashi, Akira

2015-01-01

The authors have engaged in development of the next-generation radiation detectors that can give information on energy such as X-rays and γ-rays, and commercialized an energy discrimination type radiation line sensor capable of discriminating the energy of photons using a CdTe radiation detector element. This paper introduces the structure and principles of this energy discrimination type radiation line sensor. As the basic application, it also introduces the material identification, energy discrimination type X-ray CT imaging, and the quantitative determination of iron plate thickness using X-ray. In addition, it introduces the radiation line sensor we have developed for inspecting the reduced amount of wall thickness of piping with insulation materials. This radiation line sensor for pipe thinning inspection combined with radiation sources (X-rays, γ-rays) and a transport system is capable of accurately and efficiently inspecting reduced wall thickness, while moving the censor on the covered pipe with heat insulating materials through remote control, without removing piping insulation materials and without stopping the use of piping. (A.O.)

Safety assessment plans for authorization and inspection of radiation sources

International Nuclear Information System (INIS)

2002-05-01

The objective of this TECDOC is to enhance the efficacy, quality and efficiency of the whole regulatory process. It provides advice on good practice administrative procedures for the regulatory process for preparation of applications, granting of authorizations, inspection, and enforcement. It also provides information on the development and use of standard safety assessment plans for authorization and inspection. The plans are intended to be used in conjunction with more detailed advice related to specific practices. In this sense, this TECDOC provides advice on a systematic approach to evaluations of protection and safety while other IAEA Safety Guides assist the user to distinguish between the acceptable and the unacceptable. This TECDOC covers administrative advice to facilitate the regulatory process governing authorization and inspection. It also covers the use of standard assessment and inspection plans and provides simplified plans for the more common, well established uses of radiation sources in medicine and industry, i.e. sources for irradiation facilities, industrial radiography, well logging, industrial gauging, unsealed sources in industry, X ray diagnosis, nuclear medicine, teletherapy and brachytherapy

Safety assessment plans for authorization and inspection of radiation sources

International Nuclear Information System (INIS)

1999-09-01

The objective of this TECDOC is to enhance the efficacy, quality and efficiency of the whole regulatory process. It provides advice on good practice administrative procedures for the regulatory process for preparation of applications, granting of authorizations, inspection, and enforcement. It also provides information on the development and use of standard safety assessment plans for authorization and inspection. The plans are intended to be used in conjunction with more detailed advice related to specific practices. In this sense, this TECDOC provides advice on a systematic approach to evaluations of protection and safety while other IAEA Safety Guides assist the user to distinguish between the acceptable and the unacceptable. This TECDOC covers administrative advice to facilitate the regulatory process governing authorization and inspection. It also covers the use of standard assessment and inspection plans and provides simplified plans for the more common, well established uses of radiation sources in medicine and industry, i.e. sources for irradiation facilities, industrial radiography, well logging, industrial gauging, unsealed sources in industry, X ray diagnosis, nuclear medicine, teletherapy and brachytherapy

Counterbalanced radiation detection device

International Nuclear Information System (INIS)

Platz, W.

1986-01-01

A counterbalanced radiation detection device is described which consists of: (a) a base; (b) a radiation detector having a known weight; (c) means connected with the radiation detector and the base for positioning the radiation detector in different heights with respect to the base; (d) electronic component means movably mounted on the base for counterbalancing the weight of the radiation detector; (e) means connected with the electronic component means and the radiation detector positioning means for positioning the electronic component means in different heights with respect to the base opposite to the heights of the radiation detector; (f) means connected with the radiation detector and the base for shifting the radiation detector horizontally with respect to the base; and (g) means connected with the electronic component means and the radiation detector shifting means for shifting the electronic component means horizontally with respect to the base in opposite direction to shifting of the radiation detector

Using CID for internals visual inspection and measurement

International Nuclear Information System (INIS)

Anon.

1991-01-01

Solid state sensors for video camera applications, notably the CCD (charge coupled device), tend to be much more compact than conventional tubes and therefore offer advantages in remote viewing applications. A major drawback in the nuclear context, however, is their low tolerance to radiation. Recently, however, Electricite de France and the French company Image Technologie have been working on a solid state vision system using CID (Charge injection device) technology, which is radiation resistant up to 10 5 gamma absorbed dose. The particular application is inspection and measurement of clearances in PWR core guide tubes. The system promises to save outage time by combining metrology with visual inspection - effectively two tools in one. Clearance measurements are made via the screen on the operator's computerized control system using an electronic grid system. Images can then be stored on magnetic tape. The CID camera is located at the lower end of a system of linked rods. The rods connect to a special head at the upper end, which provides fine height adjustment of the tool assembly. (author)

Prospects of radiation sterilization of medical devices

International Nuclear Information System (INIS)

Hosobuchi, Kazunari

1992-01-01

Since radiation sterilization was first introduced in the United States in 1956 in the field of disposable medical devices, it has become an indispensable technique for sterilization because of the following reasons: (1) introduction into dialyzers, (2) introduction in medical device makers, (3) development of disposable medical devices associated with developing both high molecular chemistry and cool sterilization, (4) rationality of sterilization process, and (5) problems of sterilization with ethylene oxide gas. To promote the further development of radiation sterilization, the following items are considered necessary: (1) an increase in the number of facilities for radiation sterilization, (2) recommendation of the international standardization of sterilization method, (3) decrease in radiation doses associated with sterilization, (4) development of electron accelerators and bremsstrahlung equipments for radiation sources, and (5) simplification of sterilization process management. Factors precluding the development of radiation sterilization are: (1) development of other methods than radiation sterilization, (2) development of technique for sterile products, (3) high facility cost, (4) high irradiation cost, (5) benefits and limits of sterilization markets, and (6) influences of materials. (N.K.)

Radiation hardening of MOS devices by boron

International Nuclear Information System (INIS)

Danchenko, V.

1975-01-01

A novel technique is disclosed for radiation hardening of MOS devices and specifically for stabilizing the gate threshold potential at room temperature of a radiation subjected MOS field-effect device of the type having a semiconductor substrate, an insulating layer of oxide on the substrate, and a gate electrode disposed on the insulating layer. In the preferred embodiment, the novel inventive technique contemplates the introduction of boron into the insulating oxide, the boron being introduced within a layer of the oxide of about 100A to 300A thickness immediately adjacent the semiconductor-insulator interface. The concentration of boron in the oxide layer is preferably maintained on the order of 10 atoms/ cm 3 . The novel technique serves to reduce and substantially annihilate radiation induced positive gate charge accumulations, which accumulations, if not eliminated, would cause shifting of the gate threshold potential of a radiation subjected MOS device, and thus render the device unstable and/or inoperative. (auth)

Inspection of radiation sources and regulatory enforcement (supplement to IAEA Safety Standards Series No. GS-G-1.5)

International Nuclear Information System (INIS)

2010-08-01

The achievement and maintenance of a high level of safety in the use of radiation sources depends on there being a sound legal and governmental infrastructure, including a national regulatory body with well-defined responsibilities and functions. These responsibilities and functions include establishing and implementing a system for carrying out regulatory inspections, and taking necessary enforcement actions. The Safety Requirements publication entitled Legal and Governmental Infrastructure for Nuclear, Radiation, Radioactive Waste and Transport Safety establishes the requirements for legal and governmental infrastructure. The term 'infrastructure' refers to the underlying structure of systems and organizations. This includes requirements concerning the establishment of a regulatory body for radiation sources and the responsibilities and functions assigned to it. The International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources (the Basic Safety Standards or the BSS) establish basic requirements for protection against risks associated with exposure to ionizing radiation and for the safety of radiation sources. The application of the BSS is based on the presumption that national infrastructures are in place to enable governments to discharge their responsibilities to for radiation protection and safety. This TECDOC provides practical guidance on the processes for carrying out regulatory inspections and taking enforcement actions. It includes information on the development and use of procedures and standard review plans (i.e. checklists) for inspection. Specific procedures for inspection of radiation practices and sources are provided in the Appendices

Inspection of radiation sources and regulatory enforcement (supplement to IAEA Safety Standards Series No. GS-G-1.5)

International Nuclear Information System (INIS)

2007-04-01

The achievement and maintenance of a high level of safety in the use of radiation sources depends on there being a sound legal and governmental infrastructure, including a national regulatory body with well-defined responsibilities and functions. These responsibilities and functions include establishing and implementing a system for carrying out regulatory inspections, and taking necessary enforcement actions. The Safety Requirements publication entitled Legal and Governmental Infrastructure for Nuclear, Radiation, Radioactive Waste and Transport Safety establishes the requirements for legal and governmental infrastructure. The term 'infrastructure' refers to the underlying structure of systems and organizations. This includes requirements concerning the establishment of a regulatory body for radiation sources and the responsibilities and functions assigned to it. The International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources (the Basic Safety Standards or the BSS) establish basic requirements for protection against risks associated with exposure to ionizing radiation and for the safety of radiation sources. The application of the BSS is based on the presumption that national infrastructures are in place to enable governments to discharge their responsibilities to for radiation protection and safety. This TECDOC provides practical guidance on the processes for carrying out regulatory inspections and taking enforcement actions. It includes information on the development and use of procedures and standard review plans (i.e. checklists) for inspection. Specific procedures for inspection of radiation practices and sources are provided in the Appendices

Radiation detection device and a radiation detection method

International Nuclear Information System (INIS)

Blum, A.

1975-01-01

A radiation detection device is described including at least one scintillator in the path of radiation emissions from a distributed radiation source; a plurality of photodetectors for viewing each scintillator; a signal processing means, a storage means, and a data processing means that are interconnected with one another and connected to said photodetectors; and display means connected to the data processing means to locate a plurality of radiation sources in said distributed radiation source and to provide an image of the distributed radiation sources. The storage means includes radiation emission response data and location data from a plurality of known locations for use by the data processing means to derive a more accurate image by comparison of radiation responses from known locations with radiation responses from unknown locations. (auth)

Radiation practices. Annual report 2011

Energy Technology Data Exchange (ETDEWEB)

Rantanen, E. (ed.)

2012-09-15

1791 safety licences for the use of radiation were current at the end of 2011. 1702 responsible parties were engaged in notifiable licence-exempt dental X-ray activities. Use of radiation was controlled through regular inspections performed at places of use, test packages sent by post to dental X-ray facilities and maintenance of the Dose Register. Radiation safety guides were also published and research was conducted in support of regulatory control. The Radiation and Nuclear Safety Authority (STUK) conducted 575 inspections of licensed practices in 2011. 633 repair orders and recommendations were issued in the course of inspections. A total of nearly 11 700 workers were subject to individual monitoring in 2011 and about 143 000 dose entries were made in the Dose Register maintained by STUK. Regulatory control of natural radiation focused on radon at workplaces and exposure of aircrews to cosmic radiation. 166 workplaces including a total of 288 work areas were subject to radon monitoring during 2011. Just over 3600 cockpit and cabin crew members were monitored for exposure to cosmic radiation. STUK was involved in four ionizing radiation research projects, and also took part in an international expert group evaluation of STUK research activities. New alpha and beta sources were procured for metrological activities and a Co-60 irradiation device procured in 2010 was installed and taken into use. Calibration and testing services continued as in previous years. Regulatory control of the use of non-ionizing radiation in 2011 focused particularly on mobile phones, sunbeds and lasers. Orders were issued to 5 responsible parties to discontinue the use of tattoo removal lasers. 7 sunbed facilities were inspected and 10 on-site laser display inspections were performed. Five mobile phone types were tested in market surveillance of wireless communication devices. Non-ionizing radiation research activities were also subjected to the evaluation of STUK research activities

The effects of cosmic radiation on implantable medical devices

International Nuclear Information System (INIS)

Bradley, P.

1996-01-01

Metal oxide semiconductor (MOS) integrated circuits, with the benefits of low power consumption, represent the state of the art technology for implantable medical devices. Three significant sources of radiation are classified as having the ability to damage or alter the behavior of implantable electronics; Secondary neutron cosmic radiation, alpha particle radiation from the device packaging and therapeutic doses(up to 70 Gγ) of high energy radiation used in radiation oncology. The effects of alpha particle radiation from the packaging may be eliminated by the use of polyimide or silicone rubber die coatings. The relatively low incidence of therapeutic radiation incident on an implantable device and the use of die coating leaves cosmic radiation induced secondary neutron single event upset (SEU) as the main pervasive ionising radiation threat to the reliability of implantable devices. A theoretical model which predicts the susceptibility of a RAM cell to secondary neutron cosmic radiation induced SEU is presented. The model correlates well within the statistical uncertainty associated with both the theoretical and field estimate. The predicted Soft Error Rate (SER) is 4.8 x l0 -12 upsets/(bit hr) compared to an observed upset rate of 8.5 x 10 -12 upsets/(bit hr) from 20 upsets collected over a total of 284672 device days. The predicted upset rate may increase by up to 20% when consideration is given to patients flying in aircraft The upset rate is also consistent with the expected geographical variations of the secondary cosmic ray neutron flux, although insufficient upsets precluded a statistically significant test. This is the first clinical data set obtained indicating the effects of cosmic radiation on implantable devices. Importantly, it may be used to predict the susceptibility of future to the implantable device designs to the effects of cosmic radiation

Medical Devices; General Hospital and Personal Use Devices; Classification of the Ultraviolet Radiation Chamber Disinfection Device. Final order.

Science.gov (United States)

2015-11-20

The Food and Drug Administration (FDA or the Agency) is classifying the ultraviolet (UV) radiation chamber disinfection device into class II (special controls). The special controls that will apply to the device are identified in this order and will be part of the codified language for the UV radiation chamber disinfection device classification. The Agency is classifying the device into class II (special controls) in order to provide a reasonable assurance of safety and effectiveness of the device.

Design and application of radiation apparatus for sup 6 sup 0 Co cargo train on-line inspection system

CERN Document Server

Wu Zhi Fang; Zhang Yuai

2002-01-01

Based on the special requirement for radiation apparatus of sup 6 sup 0 Co cargo train on-line inspection system, a radiation apparatus including two-level shutter, working container, storing container and electromagnetism are designed. The makeup, working mode and functional realization of the radiation apparatus are introduced. The system is used in Manzhouli customs cargo train on-line inspection system. The practice shows that the radiation apparatus is reliable to work steadily and the operating speed of the main shutter can reach 0.1 s open and 0.15 s close

Effects of radiation on MOS structures and silicon devices

International Nuclear Information System (INIS)

Braeunig, D.; Fahrner, W.

1983-02-01

A comprehensive view of radiation effects on MOS structures and silicon devices is given. In the introduction, the interaction of radiation with semiconductor material is presented. In the next section, the electrical degradation of semiconductor devices due to this interaction is discussed. The commonly used hardening techniques are shown. The last section deals with testing of radiation hardness of devices. (orig.) [de

Advanced Small Animal Conformal Radiation Therapy Device.

Science.gov (United States)

Sharma, Sunil; Narayanasamy, Ganesh; Przybyla, Beata; Webber, Jessica; Boerma, Marjan; Clarkson, Richard; Moros, Eduardo G; Corry, Peter M; Griffin, Robert J

2017-02-01

We have developed a small animal conformal radiation therapy device that provides a degree of geometrical/anatomical targeting comparable to what is achievable in a commercial animal irradiator. small animal conformal radiation therapy device is capable of producing precise and accurate conformal delivery of radiation to target as well as for imaging small animals. The small animal conformal radiation therapy device uses an X-ray tube, a robotic animal position system, and a digital imager. The system is in a steel enclosure with adequate lead shielding following National Council on Radiation Protection and Measurements 49 guidelines and verified with Geiger-Mueller survey meter. The X-ray source is calibrated following AAPM TG-61 specifications and mounted at 101.6 cm from the floor, which is a primary barrier. The X-ray tube is mounted on a custom-made "gantry" and has a special collimating assembly system that allows field size between 0.5 mm and 20 cm at isocenter. Three-dimensional imaging can be performed to aid target localization using the same X-ray source at custom settings and an in-house reconstruction software. The small animal conformal radiation therapy device thus provides an excellent integrated system to promote translational research in radiation oncology in an academic laboratory. The purpose of this article is to review shielding and dosimetric measurement and highlight a few successful studies that have been performed to date with our system. In addition, an example of new data from an in vivo rat model of breast cancer is presented in which spatially fractionated radiation alone and in combination with thermal ablation was applied and the therapeutic benefit examined.

Development of wall ranging radiation inspection robot

International Nuclear Information System (INIS)

Lee, B. J.; Yoon, J. S.; Park, Y. S.; Hong, D. H.; Oh, S. C.; Jung, J. H.; Chae, K. S.

1999-03-01

With the aging of nation's nuclear facilities, the target of this project is to develop an under water wall ranging robotic vehicle which inspects the contamination level of the research reactor (TRIGA MARK III) as a preliminary process to dismantling. The developed vehicle is driven by five thrusters and consists of small sized control boards, and absolute position detector, and a radiation detector. Also, the algorithm for autonomous navigation is developed and its performance is tested through under water experiments. Also, the test result at the research reactor shows that the vehicle firmly attached the wall while measuring the contamination level of the wall

Development of wall ranging radiation inspection robot

Energy Technology Data Exchange (ETDEWEB)

Lee, B. J.; Yoon, J. S.; Park, Y. S.; Hong, D. H.; Oh, S. C.; Jung, J. H.; Chae, K. S

1999-03-01

With the aging of nation's nuclear facilities, the target of this project is to develop an under water wall ranging robotic vehicle which inspects the contamination level of the research reactor (TRIGA MARK III) as a preliminary process to dismantling. The developed vehicle is driven by five thrusters and consists of small sized control boards, and absolute position detector, and a radiation detector. Also, the algorithm for autonomous navigation is developed and its performance is tested through under water experiments. Also, the test result at the research reactor shows that the vehicle firmly attached the wall while measuring the contamination level of the wall.

Stereo imaging and random array stratified imaging for cargo radiation inspecting

International Nuclear Information System (INIS)

Wang Jingjin; Zeng Yu

2003-01-01

This paper presents a Stereo Imaging and Random Array Stratified Imaging for cargo container radiation Inspecting. By using dual-line vertical detector array scan, a stereo image of inspected cargo can be obtained and watched with virtual reality view. The random detector array has only one-row of detectors but distributed in a certain horizontal dimension randomly. To scan a cargo container with this random array detector, a 'defocused' image is obtained. By using 'anti-random focusing', one layer of the image can be focused on the background of all defocused images from other layers. A stratified X-ray image of overlapped bike wheels is presented

Guiding device for a manipulator mast for internal inspection of a reactor pressure vessel

International Nuclear Information System (INIS)

Seifert, W.; Schlueter, H.

1977-01-01

A remote-controlled supporting device centering a manipulator mast is described which is mounted and operated above a reactor pressure vessel under water in such a way that rotations and vertical movements necessary for the internal inspection of the pressure vessel remain possible. (RW) [de

Inspection and repairing method and device for inside of nuclear reactor

International Nuclear Information System (INIS)

Ito, Shin; Yuguchi, Yasuhiro; Sato, Katsuhiko

1996-01-01

A swimming robot handling device is disposed on a floor of a reactor pit floor or a reactor floor. A swimming robot is connected to a winding device of a composite cable incorporating optical fibers. The swimming robot comprises a robot propulsion device for propelling the robot itself, a laser beam irradiating optical device for irradiating pulsative laser beams introduced by an optical fiber and an antenna mechanism having ultrasonic probe in an antenna-like shape. The swimming robot is lowered in a reactor filled with water and caused to swim to a portion to be welded, and pulsative laser beams are irradiated to the portion to be welded in a state where the antenna mechanism is brought into contact with the portion to be welded to improve the state of stresses on the surface. Further, the ultrasonic oscillations generated upon irradiation of the laser beams are measured using the ultrasonic probe to perform physical inspection. The surface of the portion to be welded can be modified or repaired stably and efficiently by remote control. (N.H.)

Detection device of dangerous radiation for the living beings

International Nuclear Information System (INIS)

Lacoste, F.

1991-01-01

This invention is about a portable device able to measure dose rates or doses of gamma, ultraviolet and X radiation or charged particles. This device is composed of a radiation detector, a calculator of the accumulate dose and a memory to store the data. This device has a credit card format

Radiation sensitive devices and systems for detection of radioactive materials and related methods

Science.gov (United States)

Kotter, Dale K

2014-12-02

Radiation sensitive devices include a substrate comprising a radiation sensitive material and a plurality of resonance elements coupled to the substrate. Each resonance element is configured to resonate responsive to non-ionizing incident radiation. Systems for detecting radiation from a special nuclear material include a radiation sensitive device and a sensor located remotely from the radiation sensitive device and configured to measure an output signal from the radiation sensitive device. In such systems, the radiation sensitive device includes a radiation sensitive material and a plurality of resonance elements positioned on the radiation sensitive material. Methods for detecting a presence of a special nuclear material include positioning a radiation sensitive device in a location where special nuclear materials are to be detected and remotely interrogating the radiation sensitive device with a sensor.

40 CFR 63.7927 - What are my inspection and monitoring requirements for closed vent systems and control devices?

Science.gov (United States)

2010-07-01

... 40 Protection of Environment 13 2010-07-01 2010-07-01 false What are my inspection and monitoring... Pollutants: Site Remediation Closed Vent Systems and Control Devices § 63.7927 What are my inspection and... temperature at the inlet of the catalyst bed, the hourly average temperature at the outlet of the catalyst bed...

Measuring ionizing radiation with a mobile device

Science.gov (United States)

Michelsburg, Matthias; Fehrenbach, Thomas; Puente León, Fernando

2012-02-01

In cases of nuclear disasters it is desirable to know one's personal exposure to radioactivity and the related health risk. Usually, Geiger-Mueller tubes are used to assess the situation. Equipping everyone with such a device in a short period of time is very expensive. We propose a method to detect ionizing radiation using the integrated camera of a mobile consumer device, e.g., a cell phone. In emergency cases, millions of existing mobile devices could then be used to monitor the exposure of its owners. In combination with internet access and GPS, measured data can be collected by a central server to get an overview of the situation. During a measurement, the CMOS sensor of a mobile device is shielded from surrounding light by an attachment in front of the lens or an internal shutter. The high-energy radiation produces free electrons on the sensor chip resulting in an image signal. By image analysis by means of the mobile device, signal components due to incident ionizing radiation are separated from the sensor noise. With radioactive sources present significant increases in detected pixels can be seen. Furthermore, the cell phone application can make a preliminary estimate on the collected dose of an individual and the associated health risks.

Dose inspection and risk assessment on radiation safety for the use of non-medical X-ray machines in Taiwan

Science.gov (United States)

Hsu, Fang-Yuh; Hsu, Shih-Ming; Chao, Jiunn-Hsing

2017-11-01

The subject of this study is the on-site visits and inspections of facilities commissioned by the Atomic Energy Council (AEC) in Taiwan. This research was conducted to evaluate the possible dose and dose rate of cabinet-type X-ray equipment with nominal voltages of 30-150 kV and open-beam (portable or handheld) equipment, taking both normal operation and possibly abnormal operation conditions into account. Doses and dose rates were measured using a plastic scintillation survey meter and an electronic personal dosimeter. In total, 401 X-ray machines were inspected, including 139 units with nominal voltages of 30-50 kV X-ray equipment, 140 units with nominal voltages of 50-150 kV, and 122 open-beam (portable or handheld) X-ray equipment. The investigated doses for radiation workers and non-radiation workers operating cabinet-type X-ray equipment under normal safety conditions were all at the background dose level. Several investigated dose rates at the position of 10 cm away from the surface of open-beam (portable or handheld) X-ray equipment were very high, such X-ray machines are used by aeronautical police for the detection of suspected explosives, radiation workers are far away (at least 10 m away) from the X-ray machine during its operation. The doses per operation in X-ray equipment with a 30-50 kV nominal voltage were less than 1 mSv in all cases of abnormal use. Some doses were higher than 1 mSv per operation for X-ray equipment of 50-150 kV nominal voltage X-ray. The maximum dose rates at the beam exit have a very wide range, mostly less than 100 μSv/s and the largest value is about 3.92 mSv/s for open-beam (portable or handheld) X-ray devices. The risk induced by operating X-ray devices with nominal voltages of 30-50 kV is extremely low. The 11.5 mSv dose due to one operation at nominal voltage of 50-150 kV X-ray device is equivalent to the exposure of taking 575 chest X-rays. In the abnormal use of open-beam (portable or handheld) X-ray equipment, the

Devices for obtaining information about radiation sources

International Nuclear Information System (INIS)

Tosswill, C.H.

1981-01-01

The invention provides a sensitive, fast high-resolution device for obtaining information about the distribution of gamma and X-radiation sources and provides a radiation detector useful in such a device. It comprises a slit collimator with a multiplicity of slits each with slit-defining walls of material and thickness to absorb beam components impinging on them. The slits extend further in one direction than the other. The detector for separately detecting beam components passing through the slits also provides data output signals. It comprises a plurality of radiation transducing portions which are not photoconductor elements each at the end of a slit. A positioner operates to change the transverse position of the slits and radiation transducing portions relative to the source, wherein each radiation transducing element is positioned within its respective slit between the slit defining walls. Full details and preferred embodiments are given. (U.K.)

Radiation safety for baggage x-ray inspection systems

Energy Technology Data Exchange (ETDEWEB)

NONE

1994-05-01

This book is an outgrowth of a course on radiation safety aimed at technicians responsible for conducting maintenance on baggage x-ray inspection systems used in federally operated facilities. The need for a single reference book became apparent to the instructor in 1984. In an effort to provide a cohesive development of the subject, a set of lecture notes was prepared and revised annually since 1984, from which this book has evolved. This book is intended to present concepts necessary for an elementary but comprehensive knowledge of radiation safety. While some material coverage may appear somewhat detailed, it is a deliberate attempt to strengthen areas of demonstrated weaknesses observed in course attenders and to provide guidance on the numerous questions about man-made radiation asked by course attenders over the years. Numerical examples are included in most chapters for clarity and ease of understanding. The problems given at the end of most chapters provide the reader with the opportunity of applying the material presented in the chapters to situations of practical interest. It is important that these problems be considered an integral part of the course and students attempt to solve them. 36 refs., 9 tabs., 17 figs.

Radiation safety for baggage x-ray inspection systems

International Nuclear Information System (INIS)

1994-05-01

This book is an outgrowth of a course on radiation safety aimed at technicians responsible for conducting maintenance on baggage x-ray inspection systems used in federally operated facilities. The need for a single reference book became apparent to the instructor in 1984. In an effort to provide a cohesive development of the subject, a set of lecture notes was prepared and revised annually since 1984, from which this book has evolved. This book is intended to present concepts necessary for an elementary but comprehensive knowledge of radiation safety. While some material coverage may appear somewhat detailed, it is a deliberate attempt to strengthen areas of demonstrated weaknesses observed in course attenders and to provide guidance on the numerous questions about man-made radiation asked by course attenders over the years. Numerical examples are included in most chapters for clarity and ease of understanding. The problems given at the end of most chapters provide the reader with the opportunity of applying the material presented in the chapters to situations of practical interest. It is important that these problems be considered an integral part of the course and students attempt to solve them. 36 refs., 9 tabs., 17 figs

Devices for obtaining information about radiation sources

International Nuclear Information System (INIS)

Tosswill, C.H.

1981-01-01

The invention provides a sensitive, fast, high-resolution device for obtaining information about the distribution of gamma and X-radiation sources and provides a radiation detector useful in such a device. It comprises a slit collimator with a multiplicity of slits each with slit-defining walls of material and thickness to absorb beam components impinging on them. The slits extend further in one transverse direction than the other. The detector for separately detecting beam components passing through the slits also provides data output signals. It comprises a plurality of radiation transducing portions, each at the end of a slit. A positioner changes the transverse position of the slits and radiation transducer (a photoconductor) relative to the source. Applications are in nuclear medicine and industry. Full details and preferred embodiments are given. (U.K.)

Electrical and electronic subsystems of a nuclear waste tank annulus inspection system

International Nuclear Information System (INIS)

Evenson, R.J.

1981-06-01

The nuclear waste tank annulus inspection system is designed specifically for use at the Nuclear Regulatory Commission's Nuclear Fuel Services Facility at West Valley, New York. This system sends a television and photographic camera into the space between the walls of a double-shell nuclear waste tank to obtain images of the inner and outer walls at precisely known locations. The system is capable of inspecting a wall section 14 ft wide by 27 ft high. Due to the high temperature and radiation of the annulus environment, the operating life for the inspection device is uncertain, but is expected to be at least 100 h, with 1000 R/h at 82 0 C. The film camera is shielded with 1/2 in. of lead to minimize radiation fogging of the film during a 25-min picture taking excursion. The operation of the inspection system is semiautomated with remote manual prepositioning of the camera, followed by a computer controlled wall scan. This apparatus is currently set up to take an array of contiguous pictures, but is adaptable to other modes of operation

Radiation sensitive area detection device and method

Science.gov (United States)

Carter, Daniel C. (Inventor); Hecht, Diana L. (Inventor); Witherow, William K. (Inventor)

1991-01-01

A radiation sensitive area detection device for use in conjunction with an X ray, ultraviolet or other radiation source is provided which comprises a phosphor containing film which releases a stored diffraction pattern image in response to incoming light or other electromagnetic wave. A light source such as a helium-neon laser, an optical fiber capable of directing light from the laser source onto the phosphor film and also capable of channelling the fluoresced light from the phosphor film to an integrating sphere which directs the light to a signal processing means including a light receiving means such as a photomultiplier tube. The signal processing means allows translation of the fluoresced light in order to detect the original pattern caused by the diffraction of the radiation by the original sample. The optical fiber is retained directly in front of the phosphor screen by a thin metal holder which moves up and down across the phosphor screen and which features a replaceable pinhole which allows easy adjustment of the resolution of the light projected onto the phosphor film. The device produces near real time images with high spatial resolution and without the distortion that accompanies prior art devices employing photomultiplier tubes. A method is also provided for carrying out radiation area detection using the device of the invention.

10 CFR 34.31 - Inspection and maintenance of radiographic exposure devices, transport and storage containers...

Science.gov (United States)

2010-01-01

.... 34.31 Section 34.31 Energy NUCLEAR REGULATORY COMMISSION LICENSES FOR INDUSTRIAL RADIOGRAPHY AND RADIATION SAFETY REQUIREMENTS FOR INDUSTRIAL RADIOGRAPHIC OPERATIONS Equipment § 34.31 Inspection and... maintenance program must include procedures to assure that Type B packages are shipped and maintained in...

A wall-crawling robot for reactor vessel inspection in advanced reactors

International Nuclear Information System (INIS)

Spelt, P.F.; Crane, C.; Feng, L.; Abidi, M.; Tosunoglu, S.

1994-01-01

A consortium of four universities and the Center for Engineering Systems Advanced Research of the Oak Ridge National Laboratory has designed a prototype wall-crawling robot to perform weld inspection in advanced nuclear reactors. Design efforts for the reactor vessel inspection robot (RVIR) concentrated on the Advanced Liquid Metal Reactor because it presents the most demanding environment in which such a robot must operate. The RVIR consists of a chassis containing two sets of suction cups that can alternately grasp the side of the vessel being inspected, providing both locomotion and steering functions. Sensors include three CCD cameras and a weld inspection device based on new shear-wave technology. The restrictions of the inspection environment presented major challenges to the team. These challenges were met in the prototype, which has been tested in a non-radiation, room-temperature mockup of the robot work environment and shown to perform as expected. (author)

A wall-crawling robot for reactor vessel inspection in advanced reactors

International Nuclear Information System (INIS)

Spelt, P.F.; Crane, C.; Feng, L.; Abidi, M.; Tosunoglu, S.

1994-01-01

A consortium of four universities and the Center for Engineering Systems Advanced Research of the Oak Ridge National Laboratory has designed a prototype wall-crawling robot to perform weld inspection in advanced nuclear reactors. Design efforts for the reactor vessel inspection robot (RVIR) concentrated on the Advanced Liquid Metal Reactor because it presents the most demanding environment in which such a robot must operate. The RVIR consists of a chassis containing two sets of suction cups that can alternately grasp the side of the vessel being inspected, providing both locomotion and steering functions. Sensors include three CCD cameras and a weld inspection device based on new shear-wave technology. The restrictions of the inspection environment presented major challenges to the team. These challenges were met in the prototype, which has been tested in a non-radiation, room-temperature mockup of the robot work environment and shown to perform as expected

Method and device for controlling radiation

International Nuclear Information System (INIS)

Wilhelm, G.M.

1979-01-01

A device which will control radiation emanating from colour television sets is described. It consists of two transparent plates the same size as a television screen, with a thin layer of transparent mineral oil sealed between them. The device may be installed by the manufacturer or bought separately and installed by the user. (LL)

Radiation dose rate measuring device

International Nuclear Information System (INIS)

Sorber, R.

1987-01-01

A portable device is described for in-field usage for measuring the dose rate of an ambient beta radiation field, comprising: a housing, substantially impervious to beta radiation, defining an ionization chamber and having an opening into the ionization chamber; beta radiation pervious electrically-conductive window means covering the opening and entrapping, within the ionization chamber, a quantity of gaseous molecules adapted to ionize upon impact with beta radiation particles; electrode means disposed within the ionization chamber and having a generally shallow concave surface terminating in a generally annular rim disposed at a substantially close spacing to the window means. It is configured to substantially conform to the window means to define a known beta radiation sensitive volume generally between the window means and the concave surface of the electrode means. The concave surface is effective to substantially fully expose the beta radiation sensitive volume to the radiation field over substantially the full ambient area faced by the window means

Terrestrial radiation effects in ULSI devices and electronic systems

CERN Document Server

Ibe, Eishi H

2014-01-01

A practical guide on how mathematical approaches can be used to analyze and control radiation effects in semiconductor devices within various environments Covers faults in ULSI devices to failures in electronic systems caused by a wide variety of radiation fields, including electrons, alpha -rays, muons, gamma rays, neutrons and heavy ions. Readers will learn the environmental radiation features at the ground or avionics altitude. Readers will also learn how to make numerical models from physical insight and what kind of mathematical approaches should be implemented to analyze the radiation effects. A wide variety of mitigation techniques against soft-errors are reviewed and discussed. The author shows how to model sophisticated radiation effects in condensed matter in order to quantify and control them. The book provides the reader with the knowledge on a wide variety of radiation fields and their effects on the electronic devices and systems. It explains how electronic systems including servers and rout...

Radiation practices. Annual report 2008

International Nuclear Information System (INIS)

Rantanen, E.

2009-09-01

1775 safety licences for the use of radiation were current at the end of 2008. 1831 responsible parties were engaged in notifiable licence-exempt dental X-ray activities. Use of radiation was controlled through regular inspections performed at places of use, test packages sent by post to dental X-ray facilities and maintenance of the Dose Register. Radiation safety guides were also published and research was conducted in support of regulatory control. STUK conducted 424 inspections of licensed practices and 18 inspections of notifiable licence-exempt dental X-ray practices in 2008. 209 repair orders and recommendations were issued. Use of one appliance was prohibited. A total of just over 11 500 workers were subject to individual monitoring in 2008, and about 140 000 dose entries were made in the Dose Register maintained by STUK. Regulatory control of natural radiation focused on radon at workplaces and exposure of aircrews to cosmic radiation. 89 workplaces including a total of 201 work areas were subject to radon monitoring during 2008. Some 3700 pilots and cabin crew members were monitored for exposure to cosmic radiation. Metrological activities continued with calibration and development work as in previous years. Regulatory control of the use of non-ionizing radiation in 2008 focused particularly on mobile phones, sunbeds and lasers. Ten mobile phone types and five baby monitors were tested in market surveillance of wireless communication devices. 25 sunbed facilities were inspected and nine laser display inspections were performed. There were 22 abnormal incidents involving the use of radiation in 2008. Seventeen of these incidents concerned the use of radiation in industry, research or transportation, four concerned the use of radiation in health care, and one concerned the use of non-ionizing radiation. None of these incidents had serious consequences. (orig.)

Radiation detection device

International Nuclear Information System (INIS)

Peschmann, Kristian.

1982-01-01

A radiation detector suitable for use in computer tomography device has an ionization chamber which comprises a high voltage electrode, a collector electrode, a high voltage source having two terminals, one connected to the high voltage electrode, current measuring means having two terminals, one connected to the high voltage source and the other to the collector electrode, and an auxilliary electrode near and parallel to the entrance window of the device, having one adjacent to the high voltage electrode and the other adjacent but not connected to the collector electrode. The auxilliary electrode is connected to the high voltage source. In this way the electric field between the high voltage and collector electrodes is made homogeneous in the vicinity of the auxilliary electrode, improving the measuring speed of the detector

Tunable radiation emitting semiconductor device

NARCIS (Netherlands)

2009-01-01

A tunable radiation emitting semiconductor device includes at least one elongated structure at least partially fabricated from one or more semiconductor materials exhibiting a bandgap characteristic including one or more energy transitions whose energies correspond to photon energies of light

Radiation sensitive solid state devices

International Nuclear Information System (INIS)

Shannon, J.M.; Ralph, J.E.

1975-01-01

A solid state radiation sensitive device is described employing JFETs as the sensitive elements. Two terminal construction is achieved by using a common conductor to capacitively couple to the JFET gate and to one of the source and drain connections. (auth)

International Standards for Radiation Sterilization of Medical Devices

International Nuclear Information System (INIS)

Miller, A.

2007-01-01

For a terminally sterilized medical device to be designated '' STERILE '', probability of finding the viable micro-organisms in the device shall be equal to or less than 1 x 10 -6 (EN 556-1:2001: Sterilization of medical devices - Requirements for medical devices to be designated '' STERILE '' - Part 1: Requirements for terminally sterilized medical devices). Author presents the main legal aspects of the international standards for radiation sterilization of medical devices

Space and military radiation effects in silicon-on-insulator devices

International Nuclear Information System (INIS)

Schwank, J.R.

1996-09-01

Advantages in transient ionizing and single-event upset (SEU) radiation hardness of silicon-on-insulator (SOI) technology spurred much of its early development. Both of these advantages are a direct result of the reduced charge collection volume inherent to SOI technology. The fact that SOI transistor structures do not include parasitic n-p-n-p paths makes them immune to latchup. Even though considerable improvement in transient and single-event radiation hardness can be obtained by using SOI technology, there are some attributes of SOI devices and circuits that tend to limit their overall hardness. These attributes include the bipolar effect that can ultimately reduce the hardness of SOI ICs to SEU and transient ionizing radiation, and charge buildup in buried and sidewall oxides that can degrade the total-dose hardness of SOI devices. Nevertheless, high-performance SOI circuits can be fabricated that are hardened to both space and nuclear radiation environments, and radiation-hardened systems remain an active market for SOI devices. The effects of radiation on SOI MOS devices are reviewed

FDA (Food and Drug Administration) Compliance Program Guidance Manual (FY 88). Section 4. Medical and radiological devices

International Nuclear Information System (INIS)

1988-01-01

The FDA Compliance Program Guidance Manual provides a system for issuing and filing program plans and instructions directed to Food and Drug Administration Field operations for project implementation. Section IV provides those chapters of the Compliance Program Guidance Manual which pertain to the areas of medical and radiological devices. Some of the areas of coverage include laser and sunlamp standards inspections, compliance testing of various radiation-emitting products such as television receivers and microwave ovens, emergency response planning and policy, premarket approval and device manufacturers inspections, device problem reporting, sterilization of devices, and consumer education programs on medical and radiological devices

Review of design principles for ITER VV remote inspection in magnetic field

International Nuclear Information System (INIS)

Izard, Jean-Baptiste; Perrot, Yann; Friconneau, Jean-Pierre

2009-01-01

Because ITER magnet system has a limited number of mechanical and thermal stress cycles, shut down number of the toroidal field is limited during lifetime of ITER. Any inspection device able to withstand the toroidal field between two plasma shots will enhance the inspection frequency capacity of ITER during operation phase. In addition to the high magnetic field the system should also cope with high temperature, ultra-high vacuum and high radiation, in order to keep the reactor availability high. Radiation, ultra-high vacuum and temperature constraints already addressed by on going R and D activities within Europe-considering the required level of radiation is to date the highest encountered in remote handling, and that facing all these constraints at once is an additional issue to overcome. Whereas, operating remote handling systems in high magnetic field is quite new field of investigation. This paper aims to be a guideline for future designers to help them choose among options the adequate solution for an ITER relevant inspection device. It provides the designer an objective view of the different effects that stem from technical choices and help them deciding whether a technology is relevant or not depending on the task's requirements. We have selected a set of technologies and products available for structural design, actuation, sensing and data transmission in order to design inspection remote handling equipment for ITER in the given constraints. These different solutions are commented with specific considerations and directions to have them fit in the specifications. Different design strategies to cope with magnetic field are then discussed, which imply either insensitive design or using the magnetic field as a potential energy source and as a positioning help. This analysis is the first result of one of the projects in the PREFIT partnership, part of the European Fusion Training Scheme.

Inspection device for external examination of pressure vessels, preferably for ultrasonic testing of reactor vessels

International Nuclear Information System (INIS)

Figlhuber, D.; Gallwas, J.; Weber, R.; Weber, J.

1978-01-01

The inspection device is placed in the annular gap between pressure vessel and biological shield of the BWR. In the annulus there is arranged at least one longitudinal rail which has got vertical guideways. Along it there can be moved on testing paths a manipulator with the ultrasonic search unit. The manipulator drive is outside of the inspection annulus. It is coupled to the manipulator by means of a tension member being guided over a reversing unit mounted at the upper end of the longitudinal rail. As a tension member there may be used a drag chain; the drive and the reversing unit are provided with corresponding chain wheels. (DG) [de

Radiation detector device for measuring ionizing radiation

International Nuclear Information System (INIS)

Brake, D. von der.

1983-01-01

The device contains a compensating filter circuit, which guarantees measurement of the radiation dose independent of the energy or independent of the energy and direction. The compensating filter circuit contains a carrier tube of a slightly absorbing metal with an order number not higher than 35, which surrounds a tubular detector and which carries several annular filter parts on its surface. (orig./HP) [de

Acoustic inspection device

Energy Technology Data Exchange (ETDEWEB)

Diaz, Aaron A.; Burghard, Brion J.; Skorpik, James R.; Pappas, Richard A.; Mullen, O. Dennis; Samuel, Todd J.; Reid, Larry D.; Harris, Joe C.; Valencia, Juan D.; Smalley, Jonathan T.; Shepard, Chester L.; Taylor, Theodore T.

2005-09-06

An ultrasound inspection apparatus particularly adapted to examine containers (sealed or unsealed) containing a liquid or solid bulk material. The apparatus has an overall configuration of a hand held pistol with a front transducer contact surface that is positioned against a front wall of the container. An ultrasound pulse is transmitted from the apparatus to be reflected from a back wall of a container being investigated. The received echo pulse is converted to a digital waveform. The waveform is analyzed relative to temperature, travel distance of the pulse(s), and time of travel to ascertain characteristics of the liquid or other materials and to provide identification of the same.

Particle interaction and displacement damage in silicon devices operated in radiation environments

International Nuclear Information System (INIS)

Leroy, Claude; Rancoita, Pier-Giorgio

2007-01-01

Silicon is used in radiation detectors and electronic devices. Nowadays, these devices achieving submicron technology are parts of integrated circuits of large to very large scale integration (VLSI). Silicon and silicon-based devices are commonly operated in many fields including particle physics experiments, nuclear medicine and space. Some of these fields present adverse radiation environments that may affect the operation of the devices. The particle energy deposition mechanisms by ionization and non-ionization processes are reviewed as well as the radiation-induced damage and its effect on device parameters evolution, depending on particle type, energy and fluence. The temporary or permanent damage inflicted by a single particle (single event effect) to electronic devices or integrated circuits is treated separately from the total ionizing dose (TID) effect for which the accumulated fluence causes degradation and from the displacement damage induced by the non-ionizing energy-loss (NIEL) deposition. Understanding of radiation effects on silicon devices has an impact on their design and allows the prediction of a specific device behaviour when exposed to a radiation field of interest

Transient radiation effects in GaAs semiconductor devices

International Nuclear Information System (INIS)

Chang, J.Y.; Stauber, M.; Ezzeddine, A.; Howard, J.W.; Constantine, A.G.; Becker, M.; Block, R.C.

1988-01-01

This paper describes an ongoing program to identify the response of GaAs devices to intense pulses of ionizing radiation. The program consists of experimental measurements at the Rensselaer Polytechnic Institute's RPI electron linear accelerator (Linac) on generic GaAs devices built by Grumman Tachonics Corporation and the analysis of these results through computer simulation with the circuit model code SPICE (including radiation effects incorporated in the variations TRISPICE and TRIGSPICE and the device model code PISCES IIB). The objective of this program is the observation of the basic response phenomena and the development of accurate simulation tools so that results of Linac irradiations tests can be understood and predicted

National system of notification, authorization and inspection for the control of radiation sources in Ghana

International Nuclear Information System (INIS)

Schandorf, C.; Darko, E.O.; Yeboah, J.; Asiamah, S.D.

2001-01-01

The Radiation Protection Board (RPB) was established in 1993 in Ghana as the regulatory authority for radiation protection and safety of radiation sources; its functions are prescribed in the 1993 national radiation protection regulation. The report describes how the country's radiation protection and safety infrastructure have been established, including the RPB's organizational structure, with reference in particular to the main activities carried out by both the Regulatory Control Department and the Radiation and Waste Safety Department. It also briefly mentions the existing RPB human resources; the national system of notification, authorization and inspection of radiation sources; the inventory of radiation sources; and the management of disused radiation sources. Finally, the report identifies the two main problem areas regarding the regulatory control of radiation sources in the country. (author)

Evaluation of radiation leaks from an installation of baggage inspection using X-ray

International Nuclear Information System (INIS)

RAZAFINDRAMIANDRA, H.A.

2007-01-01

This work wase done in the framework of the collaboration between the Madagascar-INSTN and the Civil Aviation of Madagascar (ACM). Due to the importance of the use of the scanner with X-rays for detection of baggages at the International Airport of Ivato, the protection of the workers using these HI-SCAN scanners has to be studied. The work deals with evaluating the dose rate emitted by the detector of baggages (HI SCAN 6040i and HI-SCAN 100100V) with dose rate meters (Graetz and Radiagem). These dosimeters were calibrated at the Secondary Standard Dosimetry Laboratory (SSDL) of Madagascar-INSTN before carrying out the inspection. By applying the calibration factor of the dosimeters used during the inspection, it is noted that the evaluated doses during the radiation exposure with the measuring instrument are very variable for low dose, and less than the dose limit according to the regulation on radiation protection in Madagascar. The radiations emitted by the machine with x-rays can involve dangerous effects for health, in order to protect itself, the effectiveness of the means of protection must be kept or taken into account by respecting strictly the time, the distance, and the screen. [fr

Radiation dose distributions due to sudden ejection of cobalt device.

Science.gov (United States)

Abdelhady, Amr

2016-09-01

The evaluation of the radiation dose during accident in a nuclear reactor is of great concern from the viewpoint of safety. One of important accident must be analyzed and may be occurred in open pool type reactor is the rejection of cobalt device. The study is evaluating the dose rate levels resulting from upset withdrawal of co device especially the radiation dose received by the operator in the control room. Study of indirect radiation exposure to the environment due to skyshine effect is also taken into consideration in order to evaluate the radiation dose levels around the reactor during the ejection trip. Microshield, SHLDUTIL, and MCSky codes were used in this study to calculate the radiation dose profiles during cobalt device ejection trip inside and outside the reactor building. Copyright © 2016 Elsevier Ltd. All rights reserved.

The transient radiation effects and hardness of programmed device

International Nuclear Information System (INIS)

Du Chuanhua; Xu Xianguo; Zhao Hailin

2014-01-01

A review and summary of research and development in the investigation of transient ionizing radiation effects in device and cirviut is presented. The transient ionizing radiation effects in two type of programmed device, that's 32 bit Microcontroller and antifuse FPGA, were studied. The expeiment test data indicate: The transient ionizing radiation effects of 32 bit Microcontroller manifested self-motion restart and Latchup, the Latchup threshold was 5 × 10"7 Gy (Si)/s. The transient ionizing radiation effects of FPGA was reset, no Latchup. The relationship of circuit effects to physical mechanisms was analized. A new method of hardness in circiut design was put forward. (authors)

Radiation dose distributions due to sudden ejection of cobalt device

International Nuclear Information System (INIS)

Abdelhady, Amr

2016-01-01

The evaluation of the radiation dose during accident in a nuclear reactor is of great concern from the viewpoint of safety. One of important accident must be analyzed and may be occurred in open pool type reactor is the rejection of cobalt device. The study is evaluating the dose rate levels resulting from upset withdrawal of co device especially the radiation dose received by the operator in the control room. Study of indirect radiation exposure to the environment due to skyshine effect is also taken into consideration in order to evaluate the radiation dose levels around the reactor during the ejection trip. Microshield, SHLDUTIL, and MCSky codes were used in this study to calculate the radiation dose profiles during cobalt device ejection trip inside and outside the reactor building. - Highlights: • This study aims to calculate the dose rate profiles after cobalt device ejection from open-pool-type reactor core. • MicroShield code was used to evaluate the dose rates inside the reactor control room. • McSKY code was used to evaluate the dose rates outside the reactor building. • The calculated dose rates for workers are higher than the permissible limits after 18 s from device ejection.

Tm2+ luminescent materials for solar radiation conversion devices

NARCIS (Netherlands)

Van der Kolk, E.

2015-01-01

A solar radiation conversion device is described that comprises a luminescent Tm 2+ inorganic material for converting solar radiation of at least part of the UV and/or visible and/or infra red solar spectrum into infrared solar radiation, preferably said infrared solar radiation having a wavelength

Radiation effects on custom MOS devices

International Nuclear Information System (INIS)

Harris, R.

1999-05-01

This Thesis consists of four chapters: The first is primarily for background information on the effects of radiation on MOS devices and the theory of wafer bonding; the second gives a full discussion of all practical work carried out for manufacture of Field Effect test Capacitors, the third discusses manufacture of vacuum insulator Field Effect Transistors (FET's) and the fourth discusses the testing of these devices. Using a thermally bonded field effect capacitor structure, a vacuum dielectric was studied for use in high radiation environments with a view to manufacturing a CMOS compatible, micro machined transistor. Results are given in the form of high frequency C-V curves before and after a 120 kGy(Si), 12 MRad(Si), dose from a Co 60 source showing a 1 Volt shift. The work is then extended to the design and manufacture of a micro machined, under-etch technique, Field Effect Transistor for use in high radiation areas. Results are shown for Threshold, Subthreshold and Transfer characteristics before and after irradiation up to a total dose of 100kGy or 10MRad. The conclusion from this work is that it should be possible to commercially manufacture practical vacuum dielectric field effect transistors which are radiation hard to at least 120 kGy(Si). (author)

Application of neutron radiation inspection at the Pantex Plant

International Nuclear Information System (INIS)

Cassidy, J.P.

1983-01-01

A neutron radiographic capability has been established at the Pantex Plant in Amarillo, Texas, which is operated for the Department of Energy by Mason and Hanger-Silas Mason Co. A 3 MeV Van de Graaf accelerator is employed as the neutron source. Neutron radiation inspection techniques have been developed to detect and observe discontinuities in explosive materials encased in aluminum, lead, steel and combinations of these casement materials. These data demonstrate that the capability exists for obtaining satisfactory neutron radiographs of many explosive-loaded components. Additional work will be performed in order to further determine applicable capabilities of the 3 MeV Van de Graaf accelerator. (Auth.)

Development of Quantum Devices and Algorithms for Radiation Detection and Radiation Signal Processing

International Nuclear Information System (INIS)

El Tokhy, M.E.S.M.E.S.

2012-01-01

The main functions of spectroscopy system are signal detection, filtering and amplification, pileup detection and recovery, dead time correction, amplitude analysis and energy spectrum analysis. Safeguards isotopic measurements require the best spectrometer systems with excellent resolution, stability, efficiency and throughput. However, the resolution and throughput, which depend mainly on the detector, amplifier and the analog-to-digital converter (ADC), can still be improved. These modules have been in continuous development and improvement. For this reason we are interested with both the development of quantum detectors and efficient algorithms of the digital processing measurement. Therefore, the main objective of this thesis is concentrated on both 1. Study quantum dot (QD) devices behaviors under gamma radiation 2. Development of efficient algorithms for handling problems of gamma-ray spectroscopy For gamma radiation detection, a detailed study of nanotechnology QD sources and infrared photodetectors (QDIP) for gamma radiation detection is introduced. There are two different types of quantum scintillator detectors, which dominate the area of ionizing radiation measurements. These detectors are QD scintillator detectors and QDIP scintillator detectors. By comparison with traditional systems, quantum systems have less mass, require less volume, and consume less power. These factors are increasing the need for efficient detector for gamma-ray applications such as gamma-ray spectroscopy. Consequently, the nanocomposite materials based on semiconductor quantum dots has potential for radiation detection via scintillation was demonstrated in the literature. Therefore, this thesis presents a theoretical analysis for the characteristics of QD sources and infrared photodetectors (QDIPs). A model of QD sources under incident gamma radiation detection is developed. A novel methodology is introduced to characterize the effect of gamma radiation on QD devices. The rate

Inquiry about the uses of special equipment (CT equipment, angiography systems, mammography devices, screens)

International Nuclear Information System (INIS)

Schwager, P.; Stieve, F.E.

1986-01-01

There are at least 1100 special devices in medical establishment in Bavaria which require special inspection and surveillance with regard to quality of equipment and radiation protection. In addition, there are at least 53 tomographs available for operation, and at least 120 installed X-ray screens. These devices need special approval testing and quality control services as they contribute a very significant amount of the medically indicated radiation exposure of the population. Appropriate measures are explained that can be applied in order to reduce the medical radiation exposure to an optimum. (orig.) [de

Status of radiation detector and neutron monitor technology

CERN Document Server

Kim, Y K; Ha, J H; Han, S H; Hong, S B; Hwang, I K; Lee, W G; Moon, B S; Park, S H; Song, M H

2002-01-01

In this report, we describe the current states of the radiation detection technology, detectors for industrial application, and neutron monitors. We also survey the new technologies being applied to this field. The method to detect radiation is the measurement of the observable secondary effect from the interaction between incident radiation and detector material, such as ionization, excitation, fluorescence, and chemical reaction. The radiation detectors can be categorized into gas detectors, scintillation detectors, and semiconductor detectors according to major effects and main applications. This report contains the current status and operational principles of these detectors. The application fields of radiation detectors are industrial measurement system, in-core neutron monitor, medical radiation diagnostic device, nondestructive inspection device, environmental radiation monitoring, cosmic-ray measurement, security system, fundamental science experiment, and radiation measurement standardization. The st...

Evaluation of an enclosed ultraviolet-C radiation device for decontamination of mobile handheld devices.

Science.gov (United States)

Mathew, J Itty; Cadnum, Jennifer L; Sankar, Thriveen; Jencson, Annette L; Kundrapu, Sirisha; Donskey, Curtis J

2016-06-01

Mobile handheld devices used in health care settings may become contaminated with health care-associated pathogens. We demonstrated that an enclosed ultraviolet-C radiation device was effective in rapidly reducing methicillin-resistant Staphylococcus aureus, and with longer exposure times, Clostridium difficile spores, on glass slides and reducing contamination on in-use mobile handheld devices. Published by Elsevier Inc.

Using a Commercial Ethernet PHY Device in a Radiation Environment

Science.gov (United States)

Parks, Jeremy; Arani, Michael; Arroyo, Roberto

2014-01-01

This work involved placing a commercial Ethernet PHY on its own power boundary, with limited current supply, and providing detection methods to determine when the device is not operating and when it needs either a reset or power-cycle. The device must be radiation-tested and free of destructive latchup errors. The commercial Ethernet PHY's own power boundary must be supplied by a current-limited power regulator that must have an enable (for power cycling), and its maximum power output must not exceed the PHY's input requirements, thus preventing damage to the device. A regulator with configurable output limits and short-circuit protection (such as the RHFL4913, rad hard positive voltage regulator family) is ideal. This will prevent a catastrophic failure due to radiation (such as a short between the commercial device's power and ground) from taking down the board's main power. Logic provided on the board will detect errors in the PHY. An FPGA (field-programmable gate array) with embedded Ethernet MAC (Media Access Control) will work well. The error detection includes monitoring the PHY's interrupt line, and the status of the Ethernet's switched power. When the PHY is determined to be non-functional, the logic device resets the PHY, which will often clear radiation induced errors. If this doesn't work, the logic device power-cycles the FPGA by toggling the regulator's enable input. This should clear almost all radiation induced errors provided the device is not latched up.

Regulation and inspection support radiation protection in nuclear and other installations

International Nuclear Information System (INIS)

Williams, M.K.; Potter, C.; Harbison, S.A.

1996-01-01

Over the past fifty years, radiation protection legislation in the UK has developed from a narrow industry-specific base to a comprehensive package of regulations and supporting Approved Code of Practice, with additional provisions for nuclear installations. Development of this legislation mirrors progress in international understanding about the risks from exposure to ionising radiation. The current Ionising Radiations Regulations 1985 largely implement the Euratom 1980 Basic Safety Standards Directive and place particular emphasis on the need to keep exposure as low as reasonably practicable. The regulations have been underpinned by the development of the concept of the Tolerability of Risk and the application of the ALARP/ALARA principle, particularly at nuclear installations. Analysis of dose data on HSE's Central Index of Dose Information has shown the general success of this approach in the UK; the data have also allowed targeting of inspection effort. Currently, the Health and Safety Commission and Executive are developing plans for implementing the revised EU Basic Safety Standards Directive. (author)

Radiation detection and measurement concepts, methods and devices

CERN Document Server

McGregor, Douglas

2019-01-01

This text on radiation detection and measurement is a response to numerous requests expressed by students at various universities, in which the most popularly used books do not provide adequate background material, nor explain matters in understandable terms. This work provides a modern overview of radiation detection devices and radiation measurement methods. The topics selected in the book have been selected on the basis of the author’s many years of experience designing radiation detectors and teaching radiation detection and measurement in a classroom environment.

In service inspection of superphenix 1 vessels: MIR

International Nuclear Information System (INIS)

Asty, M.; Viard, J.; Lerat, B.; Saglio, R.

1985-02-01

Presentation of the in-service inspection device, MIR, which has been specially developed for the visual and ultrasonic examination of Super Phenix 1 vessels (surface and internal defects). The inspections take place during fuel handling operations. The inspection device is a robot with a four-wheel drive vehicle which guidance along the welds is achieved by eddy-current devices; visual examination is performed by a television camera and ultrasonic probes are specially resistent to high temperatures

FDA (Food and Drug Administration) compliance program guidance manual and updates (FY 86). Section 4. Medical and radiological devices. Irregular report

International Nuclear Information System (INIS)

1986-01-01

The FDA Compliance Program Guidance Manual provides a system for issuing and filing program plans and instructions directed to Food and Drug Administration Field operations for project implementation. Section IV provides those chapters of the Compliance Program Guidance Manual which pertain to the areas of medical and radiological devices. Some of the areas of coverage include laser and sunlamp standards inspections, compliance testing of various radiation-emitting products such as television receivers and microwave ovens, emergency response planning and policy, premarket approval and device manufacturers inspections, device problem reporting, sterilization of devices, and consumer education programs on medical and radiological devices

Improvement of a device for region radiation survey

International Nuclear Information System (INIS)

Poltinnikov, S.A.

1978-01-01

The electromechnanical device based on coding the turning angle of an automobile wheel by the number of electric pulses controlling the step motor of a film gate of gamma radiometer is proposed. The device is intended for automatizing recordings of gamma-radiation levels depending on a certain distance in a given terrain. The device has been tested at car speeds from 10 to 80 km/hr

Shielding device for control rod in nuclear reactor

International Nuclear Information System (INIS)

Sakamaki, Kazuo; Tomatsu, Tsutomu.

1995-01-01

The device of the present invention shields radiation emitted from control rods to greatly reduce an operator's radiation exposure even if reactor water level is lowered and the upper portion of the control rod is exposed upon inspection of a BWR type reactor. Namely, a shield assembly has a structure comprising a set of four columnar shields in a two-row and two-column arrangement, which can be inserted into a control rod guide tube. Upon conducting inspection, the control rod is lowered into the control rod guide tube, and in this state, the columnar shields of the shield assembly are inserted to the control rod in the control rod guide tube. With such procedures, the upper portion of the control rod protruded from the control rod guide tube is covered with the shield assembly. As a result, radiation leaked from the control rod is shielded. Accordingly, irradiation in the reactor due to leaked radiation can be prevented thereby enabling to reduce an operator's radiation exposure. (I.S.)

Tire inspection system with shielded x-ray source

International Nuclear Information System (INIS)

Heisner, D.N.; Palermo, A. Jr.; Loyer, P.K.

1976-01-01

An automated tire inspection system is described which employs a penetrative radiation, such as x-radiation, to inspect the integrity of portions of tires fed sequentially along a feed path through a centering station and into a shielded enclosure where an inspection station is defined. Features of the system include a continuously operating x-ray source movable between inspection and retracted positions, and an x-ray shield for covering the source when it is retracted to permit the doors of the shielded enclosure to be opened without danger from escaping radiation. 19 Claims, 38 Drawing Figures

Radiation practices. Annual report 2010

Energy Technology Data Exchange (ETDEWEB)

Rantanen, E. (ed.)

2011-07-01

1760 safety licences for the use of radiation were current at the end of 2010. 1789 responsible parties were engaged in notifiable licence-exempt dental X-ray activities. Use of radiation was controlled through regular inspections performed at places of use, test packages sent by post to dental X-ray facilities and maintenance of the Dose Register. Radiation safety guides were also published and research was conducted in support of regulatory control. The Radiation and Nuclear Safety Authority (STUK) conducted 384 inspections of licensed practices in 2010. 447 repair orders and recommendations were issued in the course of inspections. A total of nearly 12 100 workers were subject to individual monitoring in 2010. Just under 160 000 dose entries were made in the Dose Register maintained by STUK. Regulatory control of natural radiation focused on radon at workplaces and exposure of aircrews to cosmic radiation. 140 workplaces including a total of 348 work areas were subject to radon monitoring during 2010. 3428 cockpit and cabin crew members were monitored for exposure to cosmic radiation. STUK took part in three major ionizing radiation research projects. An IAEA research project tested diagnostic dosimetry guidelines. The accuracy and reliability of internal and external radiotherapy dosimetric methods in modern radiotherapy technology were studied as part of a European metrology research programme. In metrological activities the dosemeter calibration procedure for radiotherapy accelerator electron beams was modified by changing from meter calibrations in hospitals to laboratory calibrations. Some irradiation appliances were also replaced. Calibration services continued as in previous years. Regulatory control of the use of non-ionizing radiation in 2010 focused particularly on mobile phones, sunbeds and lasers. 16 sunbed facilities were inspected and 8 on-site laser display inspections were performed. Ten mobile phone types were tested in market surveillance of

Radiation effects on semiconductor devices in high energy heavy ion accelerators

Energy Technology Data Exchange (ETDEWEB)

Belousov, Anton

2014-10-20

Radiation effects on semiconductor devices in GSI Helmholtz Center for Heavy Ion Research are becoming more and more significant with the increase of beam intensity due to upgrades. Moreover a new accelerator is being constructed on the basis of GSI within the project of facility for antiproton and ion research (FAIR). Beam intensities will be increased by factor of 100 and energies by factor of 10. Radiation fields in the vicinity of beam lines will increase more than 2 orders of magnitude and so will the effects on semiconductor devices. It is necessary to carry out a study of radiation effects on semiconductor devices considering specific properties of radiation typical for high energy heavy ion accelerators. Radiation effects on electronics in accelerator environment may be divided into two categories: short-term temporary effects and long-term permanent degradation. Both may become critical for proper operation of some electronic devices. This study is focused on radiation damage to CCD cameras in radiation environment of heavy ion accelerator. Series of experiments with irradiation of devices under test (DUTs) by secondary particles produced during ion beam losses were done for this study. Monte Carlo calculations were performed to simulate the experiment conditions and conditions expected in future accelerator. Corresponding comparisons and conclusions were done. Another device typical for accelerator facilities - industrial Ethernet switch was tested in similar conditions during this study. Series of direct irradiations of CCD and MOS transistors with heavy ion beams were done as well. Typical energies of the primary ion beams were 0.5-1 GeV/u. Ion species: from Na to U. Intensities of the beam up to 10{sup 9} ions/spill with spill length of 200-300 ns. Criteria of reliability and lifetime of DUTs in specific radiation conditions were formulated, basing on experimental results of the study. Predictions of electronic device reliability and lifetime were

Radiation damage assessment of Nb tunnel junction devices

International Nuclear Information System (INIS)

King, S.E.; Magno, R.; Maisch, W.G.

1991-01-01

This paper reports on the radiation hardness of a new technology using Josephson junctions that was explored by an irradiation using a fluence of 7.6 x 10 14 protons/cm 2 at an energy of 63 MeV from the U.C. Davis cyclotron. In what the authors believe is the first radiation assessment of Nb/Al 2 O 3 /Nb devices, the permanent damage in these devices was investigated. No permanent changes in the I-V characteristics of the junctions were observed indicating no significant level of material defects have occurred at this level of irradiation

Characteristics of withstanding radiation damage of InP crystals and devices

International Nuclear Information System (INIS)

Yamaguchi, Masafumi; Ando, Koshi

1988-01-01

Recently, the authors discovered that the characteristics of with standing radiation damage of InP crystals and devices (solar cells) are superior to those of Si and GaAs crystals and devices. Also the restoration phenomena at room temperature of radiation deterioration and the accelerated anneal phenomena by light irradiation and the injection of other minority, carriers in InP system devices were found. Such excellent characteristics suggested that InP devices are promising for the use in space. In this paper, taking an example of solar cells, the radiation resistance characteristics and their mechanism of InP crystals and devices are reported, based on the results of analysis by deep level transient spectroscopy and others. In InP solar cells, the high efficiency of photoelectric conversion was maintained even in the high dose irradiation of 1 MeV electron beam. As the carrier concentration in InP crystals is higher, they are stronger against radiation. With the increase of carrier concentration, the rate of anneal of radiation deterioration at room temperature increased. The accelerated anneal effect by minority carrier injection was remarkable in n + -p junction cells. The excellent characteristics of InP crystals are due to the formation of Frenkel defects of P and their instability. (K.I.)

Two new NDT techniques for inspection of containment welds beneath coatings

International Nuclear Information System (INIS)

Fitzpatrick, G.L.; Thome, D.K.

1991-06-01

Two new nondestructive testing methods were evaluated for inspection of containment welds beneath coatings, including magneto-optic imaging and Hall effect measurements. Traditional inspection methods, including magnetic particle inspection, are unsatisfactory in the nuclear containment environment coatings must be removed to provide reliable results. This creates radioactive waste, potential airborne contamination, and prolonged radiation exposure to inspection personnel. The new methods offer great improvement because of increased sensitivity and rapid scanning capability. Results obtained during Phase 1 demonstrated that magneto-optic imaging methods offered good detection of cracking in welded carbon steel samples, even through paint. Direct, real-time images were obtained with this technique in a video format ideal for complete documentation of the full inspection. A new method for rapidly inducing the required magnetic fields for inspection was also demonstrated and offers the potential for eliminating bulky, high current power supplies or magnetic yokes. Results obtained with the Hall effect were not as promising as they were on aluminum, due to electrical interference problems and variables biasing caused by residual magnetic fields in the parts. The technique may still be useful for inspecting tight spaces not accessible with magneto-optic imaging devices, but will require significant development. 13 refs., 18 figs

Performance of a written radiation protection inspection of nonstationary gamma radiography users

International Nuclear Information System (INIS)

Hoehne, M.

1986-01-01

A questionare has been developed for controlling users of nonstationary gamma radiography devices. It is aimed at obtaining information about the weak points according to radiation protection and to give guidance in performing such controls by the respective radiation protection officers. The questionare is included

Remote controlled stud bolt handling device for reactor pressure vessel

International Nuclear Information System (INIS)

Shindo, Takenori; Shigehiro, Katsuya; Ito, Morio; Okada, Kenji

1988-01-01

In nuclear power stations, at the time of regular inspection, the works of opening and fixing the upper covers of reactor pressure vessels are carried out for inspecting the inside of reactor pressure vessels and exchanging fuel rods. These upper covers are fastened with many stud bolts, therefore, the works of opening and fixing require a large amount of labor, and are done under the restricted condition of wearing protective clothings and masks. Babcock Hitachi K.K. has completed the development of a remotely controlled automatic bolt tightenig device for this purpose, therefore, its outline is reported. The conventional method of these works and the problems in it are described. The design of the new device aimed at the parallel execution of cleaning screw threads, loosening and tightening nuts, and taking off and putting on nuts and washers, thus contributing to the shortening of regular inspection period, the reduction of the radiation exposure of workers, and the decrease of the number of workers. The function, reliability and endurance of the new device were confirmed by the verifying test using a device made for trial. The device is composed of a stand, a rail and four stations each with a cleaning unit, a stud tensioner and a nut handling unit. (K.I.)

Radiation practices. Annual report 2002

International Nuclear Information System (INIS)

Rantanen, E.

2003-06-01

A total of 1820 safety licences granted for the use of radiation in Finland were current at the end of 2002. There were also 2037 undertakings for dental X-ray diagnostics (licencefree). The Safety Licence Register of the Radiation and Nuclear Safety Authority (STUK) listed 14 120 radiation devices and 262 radionuclide laboratories. In 2002, STUK performed 401 inspections of licensed practices and 25 inspections of licence-free dental X-ray practices. Restrictions were ordered on the use of one device. Repairs were ordered in 116 cases and recommended in 55 cases. No remarks were given in 254 cases. Imports of radioactive substances amounted to 110 157 GBq and exports totalled 22 359 GBq. Short-lived radionuclides produced in Finland amounted to 42 487 GBq. The STUK interim storage for radioactive wastes received 65 batches of low-level wastes. A total of 11 190 workers were individually monitored for radiation exposure at 1176 workplaces. Of these workers, some 32% were category A workers and 67% category B workers. In no case were annual dose limits exceeded. The total dose in the use of radiation and nuclear energy recorded in the STUK Dose Register was 6.35 Sv. The mean doses in typical diagnostic X-ray procedures based on phantom measurements were below the reference levels issued by the European Community, the IAEA and STUK. Accuracy of the therapeutic doses underlying good therapeutic results in radiotherapy has remained within acceptable limits, and no excessive doses jeopardizing the safety of therapy have occurred. In the regulatory control of natural radiation, inspection reports requesting performance of radon repairs or measurements of radon concentrations were sent to 145 enterprises. Underground radon inspections were performed in 4 mines and 7 excavation sites. The mean effective dose to aircraft crew caused by cosmic radiation was 1.6 mSv. Ministry of Social Affairs and Health Decree on the Limitation of Public Exposure to Non-Ionizing Radiation

Medical device for applying therapeutic radiation

International Nuclear Information System (INIS)

Tokita, K.M.; Haller, B.L.

1986-01-01

A device is described for applying therapeutic radiation from a preselected radiation source to a predetermined portion of a body comprising, in combination: a body member having: an external peripheral surface; a first end surface; and a second end surface spaced from the first end surface; the body member further comprising: at least first internal walls defining a first radiation source receiving channel means spaced a preselected distance from the peripheral surface, and having: a first portion extending from the second end surface to regions adjacent the first end surface; and a second portion extending from the first portion at the first end surface to the second end surface; and, the channel means communicating with regions external the body member at the second surface whereby the radiation source of a preselected intensity inserted at least along a preselected portion of the channel means is applied to the predetermined area of the body requiring therapeutic radiation treatment

Apparatus for minimizing radiation exposure and improving resolution in radiation imaging devices

International Nuclear Information System (INIS)

Ashe, J.B.; Williams, G.H.; Sypal, K.L.

1978-01-01

A collimator is disclosed for minimizing radiation exposure and improving resolution in radiation imaging devices. The collimator provides a penetrating beam of radiation from a source thereof, which beam is substantially non-diverging in at least one direction. In the preferred embodiment, the collimator comprises an elongated sandwich assembly of a plurality of layers of material exhibiting relatively high radiation attenuation characteristics, which attenuating layers are spaced apart and separated from one another by interleaved layers of material exhibiting relatively low radiation attenuation characteristics. The sandwich assembly is adapted for lengthwise disposition and orientation between a radiation source and a target or receiver such that the attenuating layers are parallel to the desired direction of the beam with the interleaved spacing layers providing direct paths for the radiation

Container Inspection Utilizing 14 MeV Neutrons

Science.gov (United States)

Valkovic, Vladivoj; Sudac, Davorin; Nad, Karlo; Obhodas, Jasmina

2016-06-01

A proposal for an autonomous and flexible ship container inspection system is presented. This could be accomplished by the incorporation of an inspection system on various container transportation devices (straddle carriers, yard gentry cranes, automated guided vehicles, trailers). The configuration is terminal specific and it should be defined by the container terminal operator. This enables that no part of the port operational area is used for inspection. The inspection scenario includes container transfer from ship to transportation device with the inspection unit mounted on it. The inspection is performed during actual container movement to the container location. A neutron generator without associated alpha particle detection is used. This allows the use of higher neutron intensities (5 × 109 - 1010 n/s in 4π). The inspected container is stationary in the “inspection position” on the transportation device while the “inspection unit” moves along its side. The 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. The neutron techniques will utilize “smart collimators” for neutrons and gamma rays, both emitted and detected. The inspected voxel is defined by the intersection of the neutron generator and the detectors solid angles. The container inspection protocol is based on identification of discrepancies between the cargo manifest, elemental “fingerprint” and radiography profiles. In addition, the information on container weight is obtained during the container transport and screening by measuring of density of material in the container.

Control device intended for a gamma radiation measuring instrument

International Nuclear Information System (INIS)

1976-01-01

This invention concerns a monitoring device for a gamma radiation measuring instrument or radiation meter, in which the radiation to be measured brings about, inter alia, the ionisation of a gas and the generation of current pulses. The dial of this meter is generally calibrated in roentgens per hour, i.e. in radiation rate units. This instrument of very simple design is remarkable for its operating reliability. Preferably placed at the inlet to a radioactive area, it enables every user of a ratemeter to check, over the entire measuring range of this instrument, its proper operation prior to entering the area. To this effect, the monitoring device in question has a thick wall lead castle, having an internal cavity in which is mounted a radioactive source delivering a gamma radiation with given constant characteristics, through a measurement window closed by a calibrated plug. Lead doors articulated on the castle can be superimposed on this window to bring about a given attenuation of the radiation coming from the source and delivered to the exterior of the castle [fr

Visual beam tube inspection at the TRIGA reactor Vienna

International Nuclear Information System (INIS)

Boeck, H.; Musilek, A.; Villa, M.

2006-01-01

Of the four TRIGA beam tubes two have been visually inspected in 1985. Prior to the inspection the reactor was shut down for 3 weeks. The fuel elements around the beam tubes were removed. Stainless steel dummy elements were inserted in the fuel positions to shield the core radiation. The active part of the Fast Rabbit Tube was removed into the beam tube loading device and transferred to an interim storage: Front dose rate was ∼ 50 mSv/h. Generally the beam tube was very clean, after the last inspection about 30 years ago. A1 cm cut was observed at the beam tube front end. A rigid endoscope was used to check the beam tube's inner surface using a 90 degree deflection objective and photo- and video equipment. The direct dose rate in front of the beam tube was about 30 mSv/h. The beam tube was vacuum cleaned. A corroded shielding tank containing boric acid has leaked. A wooden collimator partially disintegrating due to extreme temperature was removed from beam tube D. Documentation of the inspection for visible defects is produced for later comparison

Radiation Characterization of Commercial GaN Devices

Science.gov (United States)

Harris, Richard D.; Scheick, Leif Z.; Hoffman, James P.; Thrivikraman, Tushar; Jenabi, Masud; Gim, Yonggyu; Miyahira, Tetsuo

2011-01-01

Radiative feedback from primordial protostars and final mass of the first star Commercially available devices fabricated from GaN are beginning to appear from a number of different suppliers. Based on previous materials and prototype device studies, it is expected that these commercial devices will be quite tolerant to the types of radiation encountered in space. This expectation needs to be verified and the study described herein was undertaken for that purpose. All of the parts discussed in this report are readily available commercially. The parts chosen for study are all targeted for RF applications. Three different studies were performed: 1) a preliminary DDD/TID test of a variety of part types was performed by irradiating with 50 MeV protons, 2) a detailed DDD/TID study of one particular part type was performed by irradiating with 50 MeV protons, and 3) a SEB/SEGR test was performed on a variety of part types by irradiating with heavy ions. No significant degradation was observed in the tests performed in this study.

Targeted In-service Inspections Using Risk Insights

International Nuclear Information System (INIS)

Kulat, S.; Montgomery, B.; Robin Graybeal, M.

2012-01-01

This paper includes a discussion of the historical background and rationale for development of a targeted In-service Inspection (ISI) program using risk insights, known as Risk-Informed In-service Inspection (RI-ISI). RI-ISI programs are optimized inspection programs which target specific welds for inspection based upon potential degradation mechanisms and consequences of failure. Inspections are performed on those welds that are the highest contributors to plant risk. Additionally the inspections are tailored to detect the specific postulated degradation mechanisms. As a result, the numbers of inspections are reduced along with the associated cost and radiation exposure, while maintaining or improving the level of quality and safety. Provided in this paper are the basic principles of RI-ISI program development, and a summary of the impact of the implementation of such programs. For example, implementation of a Risk-Informed In-service Inspection program results in a reduction of both cost and radiation exposure. Cost savings are estimated at between USD 1,000,000 and USD 2,300,000 per unit per ten year interval for a Class 1 and2 RI-ISI application. Cost savings are estimated based on average cost per weld of USD 7600 for examination, including the following activities: erection and removal of scaffolding, removal and replacement of insulation, removal and replacement of interferences, weld preparation, examination, documentation, craft support. Reduction in radiation exposure is estimated at 75% to 90% for a Class 1 and2 RI-ISI application. Reduction in radiation exposure is due to the following factors: number of welds selected for examination decreases by 60% to 75%, surface examinations essentially eliminated, within a given risk category, welds can be selected for examination based on additional factors such as the minimization of radiation exposure.(author).

Modern equipment of radiation intrascopie for inspection of welding

International Nuclear Information System (INIS)

Sosnin, F.R.

1976-01-01

The systems are described of radiation intrascopy of controlled objects studied by x-raying and the effective transformation of the shadow x-ray image into light-shadow one. In order to increase the range of controlled thicknesses and to improve the flaw detector sensitivity of the control, the electron-optical devices and telesivion technology are applied. So it becomes possible, through the amplification of the image, to use the high resolving power of the eye. Four types of modern equipment with amplification of the image have been defined, depending on x-rays and light converters. The main technical characteristics of some devices are given. The motion mechanisms of the controlled objects are considered. All kinds of radiation intrascopy systems developed up to the present time have the sensitivity of control of steel welded objects with thickness 5-50 mm which is 2 to 4 times greater than the sensitivity of the radiographic control method. The x-ray-television control is 2 to 4 times more efficient than radiographic one and is preferable from the safety point of view

Internal inspection devices

International Nuclear Information System (INIS)

1982-01-01

In order to evaluate the possibilities and limits of using specific endoscopes, the design and performance of rigid and flexible endoscopes are studied. The results show on the one hand the physical conditions setting a limit to the applicability of a certain device, and on the other indicate possible ways of improving and modifying given devices so as to adapt them to the special requirements of current testing standards. Based on theoretical and practical experience, proposals for improvements are made. For rigid endoscopes, e.g., additional equipment has been developed and is described in detail, allowing hitherto existing problems to be solved, thus enlarging the range of employment and enhancing and improving the information to be gained by testing using endoscopes. (orig./RW) [de

EMERGENCY RADIATION SURVEY DEVICE ONBOARD THE UAV

Directory of Open Access Journals (Sweden)

S. Bogatov

2013-08-01

Full Text Available Radiation survey device (RSD on the base of unmanned aerial vehicle (UAV was developed as an equipment of rescue forces for radiation situation reconnaissance in case of emergency. RSD is multi range radiometer with spectrometer functions capable to work within gamma ray fields of dose rate 10–7 – 10–1 Sievert per hour. UAV md4-1000 (Microdrones GmbH, Germany was selected as the RSD carrier as a reliable vehicle with appropriate properties. Short description of RSD, UAV and developed software features as well as sensitivity assessments for different radiation sources are presented.

Problems of optimization of activities of sanitary and epidemiological stations on radiation protection

International Nuclear Information System (INIS)

Poplavskij, K.K.

1989-01-01

Problems of activity optimization of the sanitary and epidemiologic stations (SES) concerning state inspection of for radiation source application are considered to improve the effort efficiency of the radiological subdivisions. The necessity to specify the inspection objects is shown. Inspection of all the stages of creation, introduction and application of radioactive substances and other sources, as well as, of radioactive waste utilization remains urgent problem. Determination of internal and external radiation doses to population in different regions as well as, radiation protection of personnel and patients in nuclear medicine are vital problems as well. Justification of the necessity to enlist specialists in different fields, to determine rationally their functional duties presents sufficient component of the SES activity optimization. Usage optimization of dosimetric and radiometric devices, laboratory equipment and instruments is a vital problem

An analysis of radiation effects on electronics and soi-mos devices as an alternative

International Nuclear Information System (INIS)

Ikraiam, F. A.

2013-01-01

The effects of radiation on semiconductors and electronic components are analyzed. The performance of such circuitry depends upon the reliability of electronic devices where electronic components will be unavoidably exposed to radiation. This exposure can be detrimental or even fatal to the expected function of the devices. Single event effects (SEE), in particular, which lead to sudden device or system failure and total dose effects can reduce the lifetime of electronic devices in such systems are discussed. Silicon-on-insulator (SOI) technology is introduced as an alternative for radiation-hardened devices. I-V Characteristics Curves for SOI-MOS devices subjected to a different total radiation doses are illustrated. In addition, properties of some semiconductor materials such as diamond, diamond-like carbon films, SiC, GaP, and AlGaN/GaN are compared with those of SOI devices. The recognition of the potential usefulness of SOI-MOS semiconductor materials for harsh environments is discussed. A summary of radiation effects, impacts and mitigation techniques is also presented. (authors)

In-situ inspection of grooves in reactor tube sheet using a remotely operated cast impression taking device

International Nuclear Information System (INIS)

Rajendran, S.; Ramakumar, M.S.

1996-01-01

Utmost importance is given to the in-service inspection of critical components of a reactor to ensure its reliable performance during the reactor operation. This paper describes a cast taking device using cold setting resin to take impression of the grooves being made in the tube sheet for sparger tube installation in pressurised heavy water reactor. (author)

Complex licences: a decade of experience with internal inspections

International Nuclear Information System (INIS)

Boersma, Hielke Freerk; Bunskoeke, Erik J.

2008-01-01

Full text: In 2008 the University of Groningen has ten years of experience with the system of complex broad licences. This system was introduced on a larger scale in the Netherlands in the last decade of the twentieth century. Its main characteristics are an internal radiation protection organization and a system of internal permits or licences for all applications of ionizing radiation along with periodical inspections. Since 1998/9 we yearly conduct inspections of all users of ionizing radiation within the University of Groningen. In our presentation we will discuss the general scheme for these inspections as well as the development of its results over the past decade. Following a period of habituation the last few years show a adequate and continuous level of radiation protection. It is also concluded that continuation of the inspection projects is a prerequisite to preserve this situation. Combined with the inspection project of 2007 an informal study of the 'customer'-satisfaction with respect to various aspects of the radiation protection organization was performed. Our data were collected using a questionnaire filled out by local radiation safety officers. In this contribution detailed results of this investigation will be presented. Preliminary results show that the overall appreciation of the radiation protection organization is qualified as 'good'. (author)

Decontamination method and device for radiation contaminated product

International Nuclear Information System (INIS)

Morikawa, Kenji; Ohinata, Hiroshi; Omata, Kazuo; Sato, Toshihiko; Nakajima, Yoshihiko; Ichikawa, Seigo.

1996-01-01

In the present invention, radiation contaminated products generated during shot peening are decontaminated by a chelating agent, and the chelating agent is removed from the radiation contaminated products. Then the temperature of the radiation contaminated products is elevated by hot blowing at a temperature higher than a boiling point of the solvent. Then, a solvent is added to the radiation contaminated products and the solvent is evaporated abruptly. The solution of the chelating agent remained while being deposited thereto is removed by evaporation to remove it from the radiation contaminated products together with the solvent. With such procedures, all of the decontamination steps can be completed in one device without requiring a large space or not moving the radiation contaminated products on every step. (T.M.)

Radiation effects and soft errors in integrated circuits and electronic devices

CERN Document Server

Fleetwood, D M

2004-01-01

This book provides a detailed treatment of radiation effects in electronic devices, including effects at the material, device, and circuit levels. The emphasis is on transient effects caused by single ionizing particles (single-event effects and soft errors) and effects produced by the cumulative energy deposited by the radiation (total ionizing dose effects). Bipolar (Si and SiGe), metal-oxide-semiconductor (MOS), and compound semiconductor technologies are discussed. In addition to considering the specific issues associated with high-performance devices and technologies, the book includes th

Adjustable radiation protection device of the fluoroscope DG 10

International Nuclear Information System (INIS)

Hoermann, D.

1980-01-01

In cooperation with the 'VEB Transformatoren- und Roentgenwerk Hermann Matern', Dresden, an adjustable radiation protection device has been developed. This supplementary equipment for fluoroscopes ensures a sufficient protection of the gonads against undesirable X radiation, can be handled easily and does not annoy patients, esp. children

Development of data acquisition and processing system for In-service inspection of nuclear power plants

International Nuclear Information System (INIS)

Takama, Shinkichi; Kobayashi, Koji; Satoh, Yoshio; Koga, Yoshihiro; Shimizu, Takakazu

1981-01-01

In-service inspection (ISI) is required during the plant outage to assure the reliability of the components of a nuclear power plant. IHI has developed the advanced ISI system which consists of remote controlled and mechanized ultrasonic inspection devices for reactor pressure vessel examination, semi-automatic inspection instruments for piping examination with manual scan and automatic recording, data acquisition and processing system with microprocessor and mini-computer. By this system, ISI can be performed fully satisfying the requirement of ASME Code Sec. XI and minimizing operation in the high radioactive areas. All ultrasonic information is processed by the computer and the examination results such as size and location of ultrasonic indication are printed out in the form of sectional and plan view of the part examined, reproduced screen image and polar plot, etc. as well as the evaluation sheet. This system saves the elaborate work of inspection personnel and is expected to contribute to the improvement of inspection quality and to the reduction of radiation exposure of inspection personnel. (author)

Reading device of a radiation image contained in a radioluminescent screen and tomography device containing it

International Nuclear Information System (INIS)

Allemand, R.; Cuzin, M.; Parot, P.

1984-01-01

The present invention is aimed at improving the random access time to a stimulable radioluminescent screen point (and consequently the reading time of the screen image); it is noticeably useful for longitudinal tomography. The reading device contains a source emitting a stimulation radiation beam towards the stimulable radioluminescent screen, a control mean of the stimulation radiation beam and a deflection mean which allows the beam to scan the screen surface. The device is characterized by the use of a very fast acousto-optical type deflection mean [fr

Evolution in the design and development of the in-service inspection device for the Indian 500 MWe Fast Breeder Reactor

International Nuclear Information System (INIS)

Singh, Ashutosh Pratap; Rajagopalan, C.; Rakesh, V.; Rajendran, S.; Venugopal, S.; Kasiviswanathan, K.V.; Jayakumar, T.

2011-01-01

Highlights: → Conceptual study on the configuration of an ISI device for FBR interspace environment has been carried out. → Prototyping of the concept has been experimentally validated in a mock up. → High temperature version of the ISI device has been made and tested in mock-up. Further experimentation is underway. → Simulation of different configurations of the device has been carried out with respect to reduced gap between main vessel and safety vessel for future FBRs. → Studies on wheel lining for the device have been carried out at 150 o C for better traction and payload capability. - Abstract: In-service inspection (ISI) plays a major role in monitoring the condition of nuclear power plant structures and components. Based on the information gathered during inspection and the studies carried out, it is possible to assess the extent of damage and take corrective measures to keep effects of ageing under control. In nuclear power plants comprehensive ISI is dictated by issues of increased safety to personnel and equipment, and efficiently enhances the plant life. A special emphasis has been laid on the development of robotic devices for the ISI of the indigenous Indian 500 MWe Prototype Fast Breeder Reactor (FBR) components. This paper traces the experiments and simulations in the key developments of a robotic device, for the ISI of main vessel and safety vessel of FBRs, carried out at Indira Gandhi Centre for Atomic Research, India.

Charge-coupled devices as positron sensitive detectors of x-radiation

International Nuclear Information System (INIS)

Volkov, G.S.; Zazhivikhin, V.V.; Zajtsev, V.I.; Mishevskij, V.O.

1996-01-01

Results of theoretical and experimental studies on the sensitivity and spatial resolution of devices with a charge link (CLD) within the X-radiation energy range are described. The areas of the device application are considered

Allegheny County Weights and Measures Inspections

Data.gov (United States)

Allegheny County / City of Pittsburgh / Western PA Regional Data Center — Inspections conducted by the Allegheny County Bureau of Weights and Measures. The Bureau inspects weighing and timing devices such as gas pumps, laundromat timers,...

Review of radiation effects on ReRAM devices and technology

Science.gov (United States)

Gonzalez-Velo, Yago; Barnaby, Hugh J.; Kozicki, Michael N.

2017-08-01

A review of the ionizing radiation effects on resistive random access memory (ReRAM) technology and devices is presented in this article. The review focuses on vertical devices exhibiting bipolar resistance switching, devices that have already exhibited interesting properties and characteristics for memory applications and, in particular, for non-volatile memory applications. Non-volatile memories are important devices for any type of electronic and embedded system, as they are for space applications. In such applications, specific environmental issues related to the existence of cosmic rays and Van Allen radiation belts around the Earth contribute to specific failure mechanisms related to the energy deposition induced by such ionizing radiation. Such effects are important in non-volatile memory as the current leading technology, i.e. flash-based technology, is sensitive to the total ionizing dose (TID) and single-event effects. New technologies such as ReRAM, if competing with or complementing the existing non-volatile area of memories from the point of view of performance, also have to exhibit great reliability for use in radiation environments such as space. This has driven research on the radiation effects of such ReRAM technology, on both the conductive-bridge RAM as well as the valence-change memories, or OxRAM variants of the technology. Initial characterizations of ReRAM technology showed a high degree of resilience to TID, developing researchers’ interest in characterizing such resilience as well as investigating the cause of such behavior. The state of the art of such research is reviewed in this article.

Radiation as a microbiological contamination control of drugs, cosmetics and medical devices

International Nuclear Information System (INIS)

Ishizeki, Chuichi

1985-01-01

This paper deals with current status of radiation sterilization or disinfection of drugs, cosmetics, their materials, and medical devices, and with quality control as a tool for securing microbiological safety, especially current status of sterilization tests. Ointment containing tetracyclin, steroid hormones, gelatin, and enzymes are presented as drug samples to be irradiated, and explanations for radiation sterilization of these drugs are provided. An outline of the application of radiation in cosmetics and medical devices is given. Issues are also provided from the viewpoint of safey and effectiveness of radiation sterilization. (Namekawa, K.)

Radiation practices. Annual report 2009

International Nuclear Information System (INIS)

Rantanen, E.

2010-08-01

1 742 safety licences for the use of radiation were current at the end of 2009. 1 820 responsible parties were engaged in notifiable licence-exempt dental X-ray activities. Use of radiation was controlled through regular inspections performed at places of use, test packages sent by post to dental X-ray facilities and maintenance of the Dose Register. Radiation safety guides were also published and research was conducted in support of regulatory control. The Radiation and Nuclear Safety Authority (STUK) conducted 414 inspections of licensed practices in 2009. 392 repair orders and recommendations were issued. A total of nearly 11 600 workers were subject to individual monitoring in 2009. Just under 160 000 dose entries were made in the Dose Register maintained by STUK. Regulatory control of natural radiation focused on radon at workplaces and exposure of aircrews to cosmic radiation. 108 workplaces including a total of 219 work areas were subject to radon monitoring during 2009. 3655 cockpit and cabin crew members were monitored for exposure to cosmic radiation. STUK took part in three major ionizing radiation research projects. An IAEA research project tested IAEA/WHO diagnostic dosimetry guidelines. The accuracy and reliability of internal and external radiotherapy dosimetric methods in modern radiotherapy technology was studied as part of a European metrology research programme. In metrological activities the calibration procedure for radiotherapy accelerator electron beam dosemeters was modified by changing from meter calibration in hospitals to laboratory calibration. Some irradiation appliances were also replaced. Calibration services continued as in previous years. Regulatory control of the use of non-ionizing radiation in 2009 focused particularly on mobile phones, sunbeds and lasers. Fifteen mobile phone types were tested in market surveillance of wireless communication devices. 19 sunbed facilities were inspected and ten laser display inspections were

Evaluation of stray radiofrequency radiation emitted by electrosurgical devices

International Nuclear Information System (INIS)

De Marco, M; Maggi, S

2006-01-01

Electrosurgery refers to the passage of a high-frequency, high-voltage electrical current through the body to achieve the desired surgical effects. At the same time, these procedures are accompanied by a general increase of the electromagnetic field in an operating room that may expose both patients and personnel to relatively high levels of radiofrequency radiation. In the first part of this study, we have taken into account the radiation emitted by different monopolar electrosurgical devices, evaluating the electromagnetic field strength delivered by an electrosurgical handle and straying from units and other electrosurgical accessories. As a summary, in the worst case a surgeon's hands are exposed to a continuous and pulsed RF wave whose magnetic field strength is 0.75 A m -1 (E-field 400 V m -1 ). Occasionally stray radiation may exceed ICNIRP's occupational exposure guidelines, especially close to the patient return plate. In the second part of this paper, we have analysed areas of particular concern to prevent electromagnetic interference with some life-support devices (ventilators and electrocardiographic devices), which have failed to operate correctly. Most clinically relevant interference occurred when an electrosurgery device was used within 0.3 m of medical equipment. In the appendix, we suggest some practical recommendations intended to minimize the potential for electromagnetic hazards due to therapeutic application of RF energy

RADIATION PERFORMANCE OF GAN AND INAS/GAAS QUANTUM DOT BASED DEVICES SUBJECTED TO NEUTRON RADIATION

Directory of Open Access Journals (Sweden)

Dhiyauddin Ahmad Fauzi

2017-05-01

Full Text Available In addition to their useful optoelectronics functions, gallium nitride (GaN and quantum dots (QDs based structures are also known for their radiation hardness properties. With demands on such semiconductor material structures, it is important to investigate the differences in reliability and radiation hardness properties of these two devices. For this purpose, three sets of GaN light-emitting diode (LED and InAs/GaAs dot-in-a well (DWELL samples were irradiated with thermal neutron of fluence ranging from 3×1013 to 6×1014 neutron/cm2 in PUSPATI TRIGA research reactor. The radiation performances for each device were evaluated based on the current-voltage (I-V and capacitance-voltage (C-V electrical characterisation method. Results suggested that the GaN based sample is less susceptible to electrical changes due to the thermal neutron radiation effects compared to the QD based sample.

Radiation effects in LDD MOS devices

International Nuclear Information System (INIS)

Woodruff, R.L.; Adams, J.R.

1987-01-01

The purpose of this work is to investigate the response of lightly doped drain (LDD) n-channel transistors to ionizing radiation. Transistors were fabricated with conventional (non-LDD) and lightly doped drain (LDD) structures using both standard (non-hardened) and radiation hardened gate oxides. Characterization of the transistors began with a correlation of the total-dose effects due to 10 keV x-rays with Co-60 gamma rays. The authors find that for the gate oxides and transistor structures investigated in this work, 10 keV x-rays produce more fixed-charge guild-up in the gate oxide, and more interface charge than do Co-60 gamma rays. They determined that the radiation response of LDD transistors is similar to that of conventional (non-LDD) transistors. In addition, both standard and radiation-hardened transistors subjected to hot carrier stress before irradiation show a similar radiation response. After exposure to 1.0 x 10 6 rads(Si), non-hardened transistors show increased susceptibility to hot-carrier graduation, while the radiation-hardened transistors exhibit similar hot-carrier degradation to non-irradiated devices. The authors have demonstrated a fully-integrated radiation hardened process tht is solid to 1.0 x 10 6 rads(Si), and shows promise for achieving 1.0 x 10 7 rad(Si) total-dose capability

A compliant mechanism for inspecting extremely confined spaces

Science.gov (United States)

Mascareñas, David; Moreu, Fernando; Cantu, Precious; Shields, Daniel; Wadden, Jack; El Hadedy, Mohamed; Farrar, Charles

2017-11-01

We present a novel, compliant mechanism that provides the capability to navigate extremely confined spaces for the purpose of infrastructure inspection. Extremely confined spaces are commonly encountered during infrastructure inspection. Examples of such spaces can include pipes, conduits, and ventilation ducts. Often these infrastructure features go uninspected simply because there is no viable way to access their interior. In addition, it is not uncommon for extremely confined spaces to possess a maze-like architecture that must be selectively navigated in order to properly perform an inspection. Efforts by the imaging sensor community have resulted in the development of imaging sensors on the millimeter length scale. Due to their compact size, they are able to inspect many extremely confined spaces of interest, however, the means to deliver these sensors to the proper location to obtain the desired images are lacking. To address this problem, we draw inspiration from the field of endoscopic surgery. Specifically we consider the work that has already been done to create long flexible needles that are capable of being steered through the human body. These devices are typically referred to as ‘steerable needles.’ Steerable needle technology is not directly applicable to the problem of navigating maze-like arrangements of extremely confined spaces, but it does provide guidance on how this problem should be approached. Specifically, the super-elastic nitinol tubing material that allows steerable needles to operate is also appropriate for the problem of navigating maze-like arrangements of extremely confined spaces. Furthermore, the portion of the mechanism that enters the extremely confined space is completely mechanical in nature. The mechanical nature of the device is an advantage when the extremely confined space features environmental hazards such as radiation that could degrade an electromechanically operated mechanism. Here, we present a compliant mechanism

Evaluation of radiological safety in industrial gammagraphy services during the construction of Bolivia-Brazil gas transmission lines (GASBOL), by regulatory inspections from brazilian CNEN

International Nuclear Information System (INIS)

Aquino, Josilto O. de; Silva, Francisco Cesar A. da; Leocadio, Joao Carlos; Pinho, Adaugoberto S. de; Souza, Luiz Antonio C. de; Lourenco, Manoel J.; Nicola, Marcello S.; Melo, Ivan F.

2001-01-01

This paper presents a brief description of the Brazilian Regulatory Authority's (National Commission of Nuclear Energy - CNEN) action about safety control on industrial radioactive installations. It shows some specific radiation safety inspections that were done during the construction of the Bolivia-Brazil Gas Transmission Line (GASBOL). In this GASBOL work, it was used industrial radiography sources for weld quality control. During two years were done thirty regulatory safety inspections in these movable installations that use gamma radiography devices. As final result, it was noticed that the national system of inspection to control the safe use of radioactive sources in industrial activities is really efficient because none overexposure was detect and every CNEN's recommendations were applied by the operators. Some result about the gamma devices and violations are also showed. (author)

Device for converting electromagnetic radiation energy into electrical energy and method of manufacturing such a device

NARCIS (Netherlands)

2007-01-01

Device (10) for converting electromagnetic radiation energy into electrical energy, comprising at least a photovoltaic element (11) with a radiation-sensitive surface, wherein a covering layer (12) of a material comprising a silicon compound, to which a rare earth element has been added, is present

Experience on inspection at PFPF

International Nuclear Information System (INIS)

Aoki, I.; Yamamoto, Y.; Takahashi, Saburo; Ooshima, Hirofumi; Kuniyasu, Kazufusa.

1993-01-01

In order to reduce a personal radiation exposure, Plutonium Fuel Production Facility (PFPF) introduced an automated MOX fabrication technology. Safeguards system for the PFPF was designed and installed so as to be compatible with automated process operation as much as possible. Introduction of these system in PFPF made possible to do the inspection measurements with unattended mode and Near Real Time Material Accountancy (NRTA), consequently inspection has been carrying out effectively and efficiently. This paper describes the new Inspection activities as a comparison with old Inspection activities based on our experience. (author)

Radioactivity concentration measuring device for radiation waste containing vessel

International Nuclear Information System (INIS)

Goto, Tetsuo.

1994-01-01

The device of the present invention can precisely and accurately measure a radioactive concentration of radioactive wastes irrespective of the radioactivity concentration distribution. Namely, a Ge detector having a collimator and a plurality of radiation detectors are placed at the outside of the radioactive waste containing vessel in such a way that it can rotate and move vertically relative to the vessel. The plurality of radiation detectors detect radiation coefficient signals at an assumed segment unit of a predetermined length in vertical direction and for every predetermined angle unit in the rotational direction. A weight measuring device determines the weight of the vessel. A computer calculates an average density of radioactivity for the region filled with radioactivity based on the determined net weight and radiation coefficient signals assuming that the volume of the radioactivity is constant. In addition, the computer calculates the amount of radioactivity in the assumed segment by conducting γ -ray absorption compensation calculation for the material in the vessel. Each of the amount of radioactivity is integrated to determine the amount of radioactivity in the vessel. (I.S.)

How Agencies Inspect. A Comparative Study of Inspection Policies in Eight Swedish Government Agencies

International Nuclear Information System (INIS)

Lindblom, Lars; Clausen, Jonas; Edvardsson, Karin; Hayenhielm, Madeleine; Hermansson, Helene; Nihlen, Jessica; Palm, Elin; Ruden, Christina; Wikman, Per; Hansson, Sven Ove

2003-04-01

Eight Swedish authorities with inspection tasks in the areas of health, safety, and environmental protection have been compared, namely the authorities responsible for nuclear safety, radiation protection, railway, marine and aviation safety, environmental protection, chemicals control, and health and safety on workplaces. Significant differences in inspection policies and practices between the authorities were found, such as: diverging definitions of supervision and inspection that complicate comparisons, different priority-setting principles for inspections, variations in inspection frequencies (between 13 and 0.03 inspections per company and year), different practices with respect to notifying companies before inspection visits, and in particular, large differences in the extent to which non-compliance with regulations is reported to legal authorities. It was concluded that these agencies have much to gain from increasing their cooperation in methods development, evaluation studies, and education of inspectors

The radiation protective devices for interventional procedures using computed tomography

International Nuclear Information System (INIS)

Iida, Hiroji; Chabatake, Mitsuhiro; Shimizu, Mitsuru; Tamura, Sakio

2002-01-01

A scattered dose and a surface dose from phantom measurements during interventional procedures with computed tomography (IVR-CT) were evaluated. To reduce the personnel exposure in IVR-CT, the new protective devices were developed and its effect evaluated. Two radiation protection devices were experimentally made using a lead vinyl sheet with lead equivalent 0.125 mmPb. The first device is a lead curtain which shields the space of CT-gantry and phantom for the CT examination. The second device is a lead drape which shields on the phantom surface adjacent to the scanning plane for the CT-fluoroscopy. Scattered dose and phantom surface dose were measured with an abdominal phantom during Cine-CT (130 kV, 150 mA, 5 seconds, 10 mm section thickness). They were measured by using ionization chamber dosimeter. They were measured with and without a lead curtain and a lead drape. Scattered dose rate was measured at distance of 50-150 cm from the scanning plane. And, surface dose was measured at distance of 4-21 cm from the scanning plane on the phantom. On operator's standing position, scattered dose rates were from 8.4 to 11.6 μGy/sec at CT examination. The lead curtain and the lead drape reduced scattered dose rate at distance of 50 cm from the scanning plane by 66% and 58.3% respectively. Surface dose rate were 118 μGy/sec at distance of 5 cm from the scanning plane at CT-fluoroscopy. The lead drape reduced the surface dose by 60.5%. High scattered exposure to personnel may occur during interventional procedures using CT. They were considerably reduced during CT-arteriography by attaching the lead curtain in CT equipment. And they were substantially reduced during CT-fluoroscopy by placing the lead drape adjacent to the scanning plane, in addition, operator's hand would be protected from unnecessary radiation scattered by phantom. It was suggested that the scattered exposure to personnel could be sufficiently reduced by using radiation protection devices in IVR-CT. The

In-service inspection of nuclear power plants

International Nuclear Information System (INIS)

Asty, M.; Saglio, R.

1984-10-01

The French Commissariat a l'Energie Atomique (Atomic Energy Commission) developed two new non destructive control techniques, focused ultrasonics and multi-frequency eddy currents, which have been shown to allow a better detection and characterization of defects. We present here some of the in-service inspection devices which have been designed for field application of these techniques on the PWR reactors built by EDF, inspection devices of the PWR steam generator tubing and the now developing specific device for main tank and helicoidal tubing steam generator of Super-Phenix 1 [fr

Remote-automation of nuclear power plant equipment inspection and maintenance

International Nuclear Information System (INIS)

Sasaki, Masayoshi; Kawamura, Hironobu; Nakano, Yoshiyuki; Izumi, Shigeru.

1984-01-01

The remotely operated automation of the checkup and maintenance of nuclear power generation facilities has largely contributed to the rise of capacity ratio of plants due to the shortening of regular inspection period and to the reduction of radiation exposure dose during working, the labor saving in working and so on. In this paper, the new technologies adopted in an automatic fuel exchanger, a remotely operated automatic CRD exchanger, a new type channel handling machine, pressure-withstanding main steam line plugs and so on for No.2 plant in the Fukushima No.2 Nuclear Power Station, Tokyo Electric Power Co., Inc., are reported. Besides, the state of development of new remotely operated automatic machines for nuclear power use, such as CRD disassembling and cleaning device, volume reduction equipment for spent fuel channel boxes and control rods, multi-functional robots for use under high radiation and so on is described. Also the trend of development of latest robot technology which will be put in practical use in near future is outlined, such as a running manipulator for checkup and inspection, a variable form crawler vehicle and a five-leg movable manipulator. (Kako, I.)

Response of asymmetric carbon nanotube network devices to sub-terahertz and terahertz radiation

International Nuclear Information System (INIS)

Gayduchenko, I.; Kardakova, A.; Voronov, B.; Finkel, M.; Fedorov, G.; Jiménez, D.; Morozov, S.; Presniakov, M.; Goltsman, G.

2015-01-01

Demand for efficient terahertz radiation detectors resulted in intensive study of the asymmetric carbon nanostructures as a possible solution for that problem. It was maintained that photothermoelectric effect under certain conditions results in strong response of such devices to terahertz radiation even at room temperature. In this work, we investigate different mechanisms underlying the response of asymmetric carbon nanotube (CNT) based devices to sub-terahertz and terahertz radiation. Our structures are formed with CNT networks instead of individual CNTs so that effects probed are more generic and not caused by peculiarities of an individual nanoscale object. We conclude that the DC voltage response observed in our structures is not only thermal in origin. So called diode-type response caused by asymmetry of the device IV characteristic turns out to be dominant at room temperature. Quantitative analysis provides further routes for the optimization of the device configuration, which may result in appearance of novel terahertz radiation detectors

In-service inspection of nuclear power-plant pressure components

International Nuclear Information System (INIS)

Lautzenheiser, C.E.

1976-01-01

The early light-water-reactor systems for production of commercial power were designed and fabricated in accordance with the codes then being used for fossil-fired power-generating stations with some design changes for increased inspectability during fabrication. Over the past few years, major strides have been made in in-service inspection technology. Work has been under way to determine the reliability of nondestructive testing methods and to develop formal inspection programs throughout the world. The major problems associated with in-service inspection are the scarcity of qualified personnel, the variability in procedures and data recording between inspection agencies, and exposure of inspection personnel to radiation. Further work will be required to more completely mechanize piping inspections to reduce radiation exposure and to standardize inspection procedures, equipment, and certification of personnel. Worldwide attention to the requirements of the American Society of Mechanical Engineers' Boiler and Pressure Vessel Code, the size and integrity of inspection agencies, and efforts such as the development of personnel qualification and certification guides emphasize the importance of in-service inspection to nuclear safety

Study of radiation effects on semiconductor devices

International Nuclear Information System (INIS)

Kuboyama, Satoshi; Shindou, Hiroyuki; Ikeda, Naomi; Iwata, Yoshiyuki; Murakami, Takeshi

2004-01-01

Fine structure of the recent semiconductor devices has made them more sensitive to the space radiation environment with trapped high-energy protons and heavy ions. A new failure mode caused by bulk damage had been reported on such devices with small structure, and its effect on commercial synchronous dynamic random access memory (SDRAMs) was analyzed from the irradiation test results performed at Heavy ion Medical Accelerator in Chiba (HIMAC). Single event upset (SEU) data of static random access memory (SRAMs) were also collected to establish the method of estimating the proton-induced SEU rate from the results of heavy ion irradiation tests. (authors)

Findings of the inspection grading system on industrial radiography

International Nuclear Information System (INIS)

Gloria Doloressa

2011-01-01

The use of industrial radiography techniques evolve rapidly and widely. Various jobs in industry require the examination of welding techniques / connecting pipes and metal construction. The use of industrial radiography is one type of utilization of nuclear energy must get control so that its use does not cause harmful impacts to worker safety, community, and environment. Regulations is done through inspections, in order to supervise the observance of the terms in the licensing and legislation in the field of nuclear safety. The main purpose of inspection is to ensure the utilization of radiation sources of radiation have been used with. Findings of the inspection is a decline in the performance of licensees in meeting safety requirements. The Grading System to the findings of the inspection needs to be done to improve the effectiveness and efficiency of inspection, and it is expected that the company can improve the management of radiation safety. (author)

In-service inspection of pressurized water reactors

International Nuclear Information System (INIS)

Rapin, M.; Saglio, R.

1983-01-01

French legislation, which is more demanding than in other countries, had led Electricite de France, the State-owned utility, to acquire better performance in-service inspection facilities than those which existed previously. This fact has spurred the industrial development of the new technical facilities which are used worldwide today. This article presents the ''in-service inspection machine'' (MIS) for the inspection of the welds of a PWR vessel, and the inspection device of steam generator tubes; the MIS allow a remote-viewing, ultrasonic and gamma-graphic inspection; Foucault currents are the only one method adapted to the inspection steam generator tubes [fr

Radiation from ingested wireless devices in bio-medical telemetry bands

OpenAIRE

Chirwa, L.C.; Roy, S.; Cumming, D.R.S.

2003-01-01

The performance of wireless devices, using electrically small antennae, in the human intestine is investigated using the finite difference time domain method in recommended biomedical device telemetry bands. The radiation field intensity was found to depend on position but more strongly on frequency, with a transmission peak at 650 MHz.

Waste Calcining Facility remote inspection report

International Nuclear Information System (INIS)

Patterson, M.W.; Ison, W.M.

1994-08-01

The purpose of the Waste Calcining Facility (WCF) remote inspections was to evaluate areas in the facility which are difficult to access due to high radiation fields. The areas inspected were the ventilation exhaust duct, waste hold cell, adsorber manifold cell, off-gas cell, calciner cell and calciner vessel. The WCF solidified acidic, high-level mixed waste generated during nuclear fuel reprocessing. Solidification was accomplished through high temperature oxidation and evaporation. Since its shutdown in 1981, the WCFs vessels, piping systems, pumps, off-gas blowers and process cells have remained contaminated. Access to the below-grade areas is limited due to contamination and high radiation fields. Each inspection technique was tested with a mock-up in a radiologically clean area before the equipment was taken to the WCF for the actual inspection. During the inspections, essential information was obtained regarding the cleanliness, structural integrity, in-leakage of ground water, indications of process leaks, indications of corrosion, radiation levels and the general condition of the cells and equipment. In general, the cells contain a great deal of dust and debris, as well as hand tools, piping and miscellaneous equipment. Although the building appears to be structurally sound, the paint is peeling to some degree in all of the cells. Cracking and spalling of the concrete walls is evident in every cell, although the east wall of the off-gas cell is the worst. The results of the completed inspections and lessons learned will be used to plan future activities for stabilization and deactivation of the facility. Remote clean-up of loose piping, hand tools, and miscellaneous debris can start immediately while information from the inspections is factored into the conceptual design for deactivating the facility

Radiography inspection of weld for nuclear fuel rod

International Nuclear Information System (INIS)

Zhang Kai; Zhang Xichang

1995-05-01

The survey of radiography inspection, advantages, disadvantages and applications of main kinds of radiography inspection methods are presented. Emphasis is put upon the structure and functions of X-ray flaw detecting device for nuclear fuel rod welds, the actuating program of the device, as well as the structure of some key mechanism and the functions of them. The analysis is made upon the actuating principles. Finally, the test of long-term operation proves the device to be stable in operation, reliable in action, to possess high level of automation and high sensitivity and it can simultaneously perform on-line X-ray inspection of 25 nuclear fuel rods with a diameter less than 10 mm, and meet the requirements of large-scale production of nuclear fuel rods (5 figs.)

Effect on the insulation material of a MOSFET device submitted to a standard diagnostic radiation beam

International Nuclear Information System (INIS)

De Magalhaes, C M S; Dos Santos, L A P; Souza, D do N; Maia, A F

2010-01-01

MOSFET electronic devices have been used for dosimetry in radiology and radiotherapy. Several communications show that due to the radiation exposure defects appear on the semiconductor crystal lattice. Actually, the structure of a MOSFET consists of three materials: a semiconductor, a metal and an insulator between them. The MOSFET is a quadripolar device with a common terminal: gate-source is the input; drain-source is the output. The gate controls the electrical current passing through semiconductor medium by the field effect because the silicon oxide acts as insulating material. The proposal of this work is to show some radiation effects on the insulator of a MOSFET device. A 6430 Keithley sub-femtoamp SourceMeter was used to verify how the insulating material layer in the structure of the device varies with the radiation exposure. We have used the IEC 61267 standard radiation X-ray beams generated from a Pantak industrial unit in the radiation energy range of computed tomography. This range was chosen because we are using the MOSFET device as radiation detector for dosimetry in computed tomography. The results showed that the behaviour of the electrical current of the device is different in the insulator and semiconductor structures.

Development of radioactive materials inspection system

International Nuclear Information System (INIS)

Yang Lu; Wang Guobao; Chen Yuhua; Li Latu; Zhang Sujing

2005-01-01

Radioactive materials inspection system which is applied to inspect the horror activities of radioactive materials and its illegal transfer. The detector sections are made of highly stable and credible material. It has high sensitivity to radioactive materials. The inspect lowest limit of inspection is the 2-3 times to the background, the energy range is 30 keV-2.5 MeV and the response time is 0.5 s. Inspection message can be transmitted through wired or wireless web to implement remote control. The structure of the system is small, light and convenient. It is ideal for protecting society and public from the harm of the radiation. (authors)

Device for the integral measurement of ionizing radiations

International Nuclear Information System (INIS)

Micheron, Francois.

1980-01-01

This invention relates to devices for the integral determination of ionizing radiations, particularly to the construction of a portable dosemeter. Portable measuring instruments have been suggested in the past, particularly dosemeters in which the discharge of a capacitor under the action of ionizing radiations is measured. Since the charge of a capacitor is not stable owing to dielectric imperfections, these measuring instruments have to be recalibrated at frequent intervals. To overcome this drawback, the invention suggests using the discharge of an electret, electrically charged to a pre-set initial value, under the action of ionizing radiations, as the transducer means of a dosemeter used in conjunction with display or warning systems [fr

Radiation hardness and qualification of semiconductor electronic devices for nuclear reactors

International Nuclear Information System (INIS)

Friant, A.; Payat, R.

1984-05-01

After a brief review of radiation effects in semiconductors and radiation damage in semiconductor devices, the problems of qualification of electronic equipment to be used in nuclear reactors are compared to those relative to nuclear weapons or space experiments. The conclusion is that data obtained at very high dose rates or under pulsed irradiation in weapons and space programs should not be directly applied to nuclear plant instrumentation. The need for a specific qualification of semiconductor devices appropriate for nuclear reactors is emphasized. Some irradiation studies at IRDI/DEIN (CEN-Saclay) are related [fr

Problematic radiation protective devices for X-ray diagnostics

International Nuclear Information System (INIS)

Beck, A.; Nanko, N.; Bruggmoser, G.; Eble, M.

1988-01-01

The authors report experimental test results of radiation safety glasses with a lead equivalence of 0.5 mm Pb. The glasses were tested on a phantom, with various radiation projections, for their shielding effect with regard to the eye lens. The protective effect at AP projection was 90%, which corresponds to the data given by the manufacturer. But in most cases of interventional radiology, the examiner's eyes are exposed to lateral radiation, due to the positioning of the monitor. In these cases, reflected radiation at the side of the glasses facing the eye may induce a dose to the lens that can be fourfold the dose received without wearing the glasses, so that wearing these glasses may enhance the hazard. Another protective device tested was lead-coated gloves. The manufacturer promises a protective effect of 50% at 100 kV. The experimental test data, obtained by taking into account technical characteristics of angiographic components, confirm a radiation shielding of about 20%. (orig./HP) [de

Radiation dose measurements of the insertion devices using radiachromic film dosimeters

International Nuclear Information System (INIS)

Alderman, J.; Semones, E.; Job, P. K.

2004-01-01

The Advanced Photon Source (APS) uses Nd-Fe-B permanent magnets in the insertion devices to produce x-rays for scientific research [1,2]. Earlier investigations have exhibited varying degrees of demagnetization of these magnets [3] due to irradiation from electron beams [4,5,6], 60 Co γ-rays [5], and high-energy neutrons [7,8]. Radiation-induced demagnetization has been observed in the APS insertion devices [9] and was first measured in December of 2001. Partial demagnetization has also been observed in insertion devices at the European Synchrotron Radiation Facility (ESRF) [4,6], where Nd-Fe-B permanent magnets are also used. Growing concern for the lifetime of APS insertion devices, as well as the permanent magnets that will be used in next-generation, high-power light sources, like the FEL [10,11], resulted from the partial demagnetization observations made at both facilities. This concern in relation to radiation-induced demagnetization spurred a long-term project to measure and analyze the absorbed doses received by the APS insertion devices. The project required a reliable photon high-dose dosimetry technique capable of measuring absorbed doses greater than 10 6 rad, which was not readily available at the APS. Through a collaboration with the National Institute of Standards and Technology (NIST), one such technique using radiachromic films was considered, tested, and calibrated at the APS. This consequently led to the implementation of radiachromic film dosimetry for measuring the absorbed doses received by the insertion devices for each of the APS runs

Electromagnetic Radiation Efficiency of Body-Implanted Devices

Science.gov (United States)

Nikolayev, Denys; Zhadobov, Maxim; Karban, Pavel; Sauleau, Ronan

2018-02-01

Autonomous wireless body-implanted devices for biotelemetry, telemedicine, and neural interfacing constitute an emerging technology providing powerful capabilities for medicine and clinical research. We study the through-tissue electromagnetic propagation mechanisms, derive the optimal frequency range, and obtain the maximum achievable efficiency for radiative energy transfer from inside a body to free space. We analyze how polarization affects the efficiency by exciting TM and TE modes using a magnetic dipole and a magnetic current source, respectively. Four problem formulations are considered with increasing complexity and realism of anatomy. The results indicate that the optimal operating frequency f for deep implantation (with a depth d ≳3 cm ) lies in the (108- 109 )-Hz range and can be approximated as f =2.2 ×107/d . For a subcutaneous case (d ≲3 cm ), the surface-wave-induced interference is significant: within the range of peak radiation efficiency (about 2 ×108 to 3 ×109 Hz ), the max-to-min ratio can reach a value of 6.5. For the studied frequency range, 80%-99% of radiation efficiency is lost due to the tissue-air wave-impedance mismatch. Parallel polarization reduces the losses by a few percent; this effect is inversely proportional to the frequency and depth. Considering the implantation depth, the operating frequency, the polarization, and the directivity, we show that about an order-of-magnitude efficiency improvement is achievable compared to existing devices.

Effects of cosmic radiation on devices and embedded systems in aircrafts

Energy Technology Data Exchange (ETDEWEB)

Prado, Adriane C.M.; Federico, Claudio A.; Pereira Junior, Evaldo C.F.; Goncalez, Odair L., E-mail: claudiofederico@ieav.cta.br, E-mail: odairlelisgoncalez@gmail.com, E-mail: adriane.acm@hotmail.com, E-mail: evaldocarlosjr@gmail.com [Instituto de Estudos Avancados (IEAV/DCTA), Sao Jose dos Campos, SP (Brazil)

2013-07-01

Modern avionics systems use new electronic technologies devices that, due to their high degree of sophistication and miniaturization, are more susceptible to the effects of ionizing radiation, particularly the effect called 'Single Event Effect' (SEE) produced by neutron. Studies regarding the effects of radiation on electronic systems for space applications, such as satellites and orbital stations, have already been in progress for several years. However, tolerance requirements and specific studies, focusing on testing dedicated to avionics, have caused concern and gained importance in the last decade as a result of the accidents attributed to SEE in aircraft. Due to the development of a higher ceiling, an increase in airflow and a greater autonomy of certain aircrafts, the problem regarding the control of ionizing radiation dose received by the pilots, the crew and sensitive equipment became important in the areas of occupational health, radiation protection and flight safety. This paper presents an overview of the effects of ionizing radiation on devices and embedded systems in aircrafts, identifying and classifying these effects in relation to their potential risks in each device class. The assessment of these effects in avionics is a very important and emerging issue nowadays, which is being discussed by groups of the international scientific community; however, in South America, groups working in this area are still unknown. Consequently, this work is a great contribution and significantly valuable to the area of aeronautical engineering and flight safety associated to the effects of radiation on electronic components embedded in aircraft. (author)

Effects of cosmic radiation on devices and embedded systems in aircrafts

International Nuclear Information System (INIS)

Prado, Adriane C.M.; Federico, Claudio A.; Pereira Junior, Evaldo C.F.; Goncalez, Odair L.

2013-01-01

Modern avionics systems use new electronic technologies devices that, due to their high degree of sophistication and miniaturization, are more susceptible to the effects of ionizing radiation, particularly the effect called 'Single Event Effect' (SEE) produced by neutron. Studies regarding the effects of radiation on electronic systems for space applications, such as satellites and orbital stations, have already been in progress for several years. However, tolerance requirements and specific studies, focusing on testing dedicated to avionics, have caused concern and gained importance in the last decade as a result of the accidents attributed to SEE in aircraft. Due to the development of a higher ceiling, an increase in airflow and a greater autonomy of certain aircrafts, the problem regarding the control of ionizing radiation dose received by the pilots, the crew and sensitive equipment became important in the areas of occupational health, radiation protection and flight safety. This paper presents an overview of the effects of ionizing radiation on devices and embedded systems in aircrafts, identifying and classifying these effects in relation to their potential risks in each device class. The assessment of these effects in avionics is a very important and emerging issue nowadays, which is being discussed by groups of the international scientific community; however, in South America, groups working in this area are still unknown. Consequently, this work is a great contribution and significantly valuable to the area of aeronautical engineering and flight safety associated to the effects of radiation on electronic components embedded in aircraft. (author)

In service inspection of SUPERPHENIX 1 vessels: MIR

International Nuclear Information System (INIS)

Asty, M.; Viard, J.; Lerat, B.; Saglio, R.

1985-01-01

Although no in-service inspection constraints were imposed on the Phenix vessels, the Safety Authorities asked that the design of SUPERPHENIX 1 makes it possible to monitor throughout the lifetime of the reactor, surface and internal defects on the main vessel. A pool design and the presence of heat baffles inside the main vessel make access from the inside of the vessel impossible. Thus, an inspection can only be performed from the outside of the main vessel: the distance between the walls of the main and safety vessels is such that an inspection device can be introduced into the corresponding space. As the design of the reactor precludes radiographic inspection, the method which was selected for monitoring internal defects in the main vessel is ultrasonics. However, the anisotropic structure of austenitic stainless steel welds limits the performance of this technique. The authors present the in-service inspection device, MIR, which has been specially developed for the visual and ultrasonic examination of SUPERPHENIX 1 vessels

Radiation protection code of practice in academic and research institutes

International Nuclear Information System (INIS)

Abdalla, A. A. M.

2010-05-01

The main aim of this study was to establish a code of practice on radiation protection for safe control of radiation sources used in academic and research institutes, another aim of this study was to assess the current situation of radiation protection in some of the academic and research institutes.To achieve the aims of this study, a draft of a code of practice has been developed which is based on international and local relevant recommendation. The developed code includes the following main issues: regulatory responsibilities, radiation protection program and design of radiation installations. The second aim had been accomplished by conducting inspection visits to five (A, B, C, D and E) academic and to four (F, G, H and I ) research institutes. Eight of such institutes are located in Khartoum State and the ninth one is in Madani city (Aljazeera State). The inspection activities have been carried out using a standard inspection check list developed by the regulatory authority of the Sudan. The inspection missions to the above mentioned institutes involved also evaluation of radiation levels around the premises and storage areas of radiation sources. The dose rate measurement around radiation sources locations were found to be quite low. This mainly is due to the fact that the activities of most radionuclides that are used in these institutes are quite low ( in the range of micro curies). Also ,most the x-ray machines that were found in use for scientific academic and research purposes work at low k Vp of maximum 60 k Vp. None of the radiation workers in the inspected institutes has a personal radiation monitoring device, therefor staff dose levels have not been assessed. However it was noted that in most of the academic/ research studies radiation workers are only exposed to very low levels of radiation and for a very short time that dose not exceed 1 minute, therefore the expected occupational exposure of the staff is very low. Radiation measurement in public

Response of GaAs charge storage devices to transient ionizing radiation

Science.gov (United States)

Hetherington, D. L.; Klem, J. F.; Hughes, R. C.; Weaver, H. T.

Charge storage devices in which non-equilibrium depletion regions represent stored charge are sensitive to ionizing radiation. This results since the radiation generates electron-hole pairs that neutralize excess ionized dopant charge. Silicon structures, such as dynamic RAM or CCD cells are particularly sensitive to radiation since carrier diffusion lengths in this material are often much longer than the depletion width, allowing collection of significant quantities of charge from quasi-neutral sections of the device. For GaAs the situation is somewhat different in that minority carrier diffusion lengths are shorter than in silicon, and although mobilities are higher, we expect a reduction of radiation sensitivity as suggested by observations of reduced quantum efficiency in GaAs solar cells. Dynamic memory cells in GaAs have potential increased retention times. In this paper, we report the response of a novel GaAs dynamic memory element to transient ionizing radiation. The charge readout technique is nondestructive over a reasonable applied voltage range and is more sensitive to stored charge than a simple capacitor.

Periodic inspections of the primary system

International Nuclear Information System (INIS)

Dufour, L.B.

1978-01-01

An impression is given of the inspection techniques, preparations and background for periodic examinations of the primary system of the Dodewaard Nuclear Reactor over the past 10 years. Unfortunately reliable integral inspection techniques to enable 'listening-in' to developing faults, are not yet available. Until they are, inspections will continue to be executed from a distance using different continuous methods, often under water and with a shortage of space and in the presence of ionising radiations. (C.F.)

Gentilly 2 steam generators Spring 2000 outage: tubesheet waterlance cleaning and inspection; upper bundle inspection

International Nuclear Information System (INIS)

Akeroyd, J.K.; Plante, S.

2000-01-01

A review of the secondary side maintenance activities recently completed during the Gentilly 2 Annual Spring 2000 Maintenance Outage. Activities included: 1) Tubesheet intertube waterlance cleaning and visual inspection, 2) First tube support plate, in-bundle visual inspection of the hot leg, and 3) Upper bundle tube support plate visual inspection. A description of the waterlancing and inspection equipment and setup in the RB at Gentilly 2 is provided. Several innovative techniques were successfully employed and yielded savings in critical path duration, labour and personnel radiation dose. These included accessing the SG tubesheet region through one handhole only and sludge removal utilizing the SG blowdown system. Plant personnel judged tubesheet sludge removal successful. Before and after results of the cleaning process along with samples of the visual inspection results are provided. Inspection of the first support plate, which was a repeat of an inspection done in 1997, was conducted along with an in-bundle inspection of the upper tube supports. Results are presented along with a discussion of the implications for future steam generator maintenance. (author)

Methods and apparatus for multi-parameter acoustic signature inspection

Energy Technology Data Exchange (ETDEWEB)

Diaz, Aaron A [Richland, WA; Samuel, Todd J [Pasco, WA; Valencia, Juan D [Kennewick, WA; Gervais, Kevin L [Richland, WA; Tucker, Brian J [Pasco, WA; Kirihara, Leslie J [Richland, WA; Skorpik, James R [Kennewick, WA; Reid, Larry D [Benton City, WA; Munley, John T [Benton City, WA; Pappas, Richard A [Richland, WA; Wright, Bob W [West Richland, WA; Panetta, Paul D [Richland, WA; Thompson, Jason S [Richland, WA

2007-07-24

A multiparameter acoustic signature inspection device and method are described for non-invasive inspection of containers. Dual acoustic signatures discriminate between various fluids and materials for identification of the same.

Safety guidance and inspection program for particle accelerator

Energy Technology Data Exchange (ETDEWEB)

Lee, Do Whey [Korea Institute of Nuclear Safety, Taejon (Korea, Republic of); Lee, Hee Seock; Yeo, In Whan [Pohang Accelerator Laboratory, Pohang (Korea, Republic of)] (and others)

2001-03-15

The inspection program and the safety guidance were developed to enhance the radiation protection for the use of particle accelerators. First the classification of particle accelerators was conducted to develop the safety inspection protocol efficiently. The status of particle accelerators which were operated at the inside and outside of the country, and their safety programs were surveyed. The characteristics of radiation production was researched for each type of particle accelerators. Two research teams were launched for industrial and research accelerators and for medical accelerators, respectively. In each stages of a design, a fabrication, an installation, a commissioning, and normal operation of accelerators, those safety inspection protocols were developed. Because all protocols resulted from employing safety experts, doing the questionnaire, and direct facility surveys, it can be applicable to present safety problem directly. The detail improvement concepts were proposed to revise the domestic safety rule. This results might also be useful as a practical guidance for the radiation safety officer of an accelerator facility, and as the detail standard for the governmental inspection authorities.

Development of Reactor Vessel Bottom Mount Instrumentation Nozzle Routine Inspection Device

Energy Technology Data Exchange (ETDEWEB)

Khaled, Atya Ahmed Abdallah; Ihn, Namgung [KEPCO International Nuclear Graduate School, Ulsan (Korea, Republic of)

2015-10-15

The primary coolant water of pressurized water reactors has created cracks in j-weld of penetrations with Alloy 600 through a process called primary water stress corrosion cracking. On October 6, 2013, BMI nozzle number 3 at Palo Verde Unit 3 (PVNGS-3) exhibited small white de-posits around the annulus. Nozzle attachment to the RV lower head is by J-groove weld to the inside penetration of the nozzle and the weld material is of Alloy 600 material. Above two cases clearly show the necessity of routine inspection of RV lower head penetration during refueling outage. Nondestructive inspection is generally performed to detect fine cracks or defects that may develop during operation. Defects usually occur at weld regions, hence most non-destructive inspection is to scan and check any defects or crack in the weld region. BMI nozzles at the bottom head of a nuclear reactor vessel (RV) are one of such area for inspection. But BMI nozzles have not been inspected during regular refuel outage due to the relative small size of BMI nozzle and limited impact of the consequences of BMI leak. However, there is growing concern since there have been leaks at nuclear power plants (NPPs) as well as recent operating experience. In this study, we propose a system that is conveniently used for nondestructive inspection of BMI nozzles during regular refueling outage without removing all the reactor internals. A 3D model of the inspection system was also developed along with the RV and internals which permits a virtual 3D simulation to check the design concept and usability of the system.

Enhanced InService Inspection system for BWR plant

International Nuclear Information System (INIS)

Shouji, Hajime; Kobayashi, Teruo; Nagao, Tetsuya

1993-01-01

An enhanced InService Inspection system (ISI) has been developed, consisting of newly designed automated scanners, automated pipe inspection system and a high speed data acquisition/analysis station. This system uses a trackless magnetic crawler type nozzle inspection scanner attached to the nozzle shoulder by magnetic wheels. The automated pipe inspection system consists of an automated scanner, controller and high speed data acquisition station. These advanced automatic inspection systems are very useful for ISI, especially in reducing the radiation exposure and time required. (author)

In-service inspection of electronics components, circuits and nuclear radiation detectors

International Nuclear Information System (INIS)

Darbhe, M.D.

2002-01-01

A nuclear reactor is a complex process plant. Like a nuclear power plant, the research reactors also employ various nuclear and process systems, the scope and number of such systems being plant-specific. In-service inspection of these systems is an important requirement and is applied at various levels of their constituent units such as detectors, electronics components, circuits and integrated systems. The sensors used cover a wide range such as neutronic, radiation, process (pressure, temperature, flow, level) and many others. The present discussion is limited to neutronic and radiation detectors. The electronic components used normally consist of passive components like resistors, capacitors, semiconductor components like diodes, transistors, analog integrated circuits and digital integrated circuits and electromagnetic relays, to name a few. In order to have a comprehensive surveillance and ISI plan, over the entire plant life, it is necessary to understand various mechanisms, which degrade the performance of these systems. These are discussed initially and later various ISI methods that are used on component-circuit or system level, to ensure optimum system performance, are discussed. The computerised systems, because of hardware and software considerations, have to be given special attention, and the same are discussed briefly

X-ray radiography for container inspection

Science.gov (United States)

Katz, Jonathan I [Clayton, MO; Morris, Christopher L [Los Alamos, NM

2011-06-07

Arrangements of X-ray inspection systems are described for inspecting high-z materials in voluminous objects such as containers. Inspection methods may involve generating a radiographic image based on detected attenuation corresponding to a pulsed beams of radiation transmitted through a voluminous object. The pulsed beams of radiation are generated by a high-energy source and transmitted substantially downward along an incident angle, of approximately 1.degree. to 30.degree., to a vertical axis extending through the voluminous object. The generated radiographic image may be analyzed to detect on localized high attenuation representative of high-z materials and to discriminate high-z materials from lower and intermediate-z materials on the basis of the high density and greater attenuation of high-z material for higher energy (3-10 MeV) X-rays, and the compact nature of threatening masses of fissionable materials.

Sensor device for X-ray beam to evaluate the radiation focal spot

International Nuclear Information System (INIS)

Santos, Lara H.E. dos; Schiabel, Homero; Silva, Aderbal A.B. da; Marques, Paulo M.A.; Campos, Marcelo; Slaets, Annie F.F.

1996-01-01

A new electronic device to determine the position of the central ray of the radiation beam is proposed. The device aims to provide a perfect alignment of test objects used for evaluating focal spots with this reference axis

Localization of a Robotic Crawler for CANDU Fuel Channel Inspection

Science.gov (United States)

Manning, Mark

This thesis discusses the design and development of a pipe crawling robot for the purpose of CANDU fuel channel inspection. The pipe crawling robot shall be capable of deploying the existing CIGAR (Channel Inspection and Gauging Apparatus for Reactors) sensor head. The main focus of this thesis is the design of the localization system for this robot and the many tests that were completed to demonstrate its accuracy. The proposed localization system consists of three redundant resolver wheels mounted to the robot's frame and two resolvers that are mounted inside a custom made cable drum. This cable drum shall be referred to in this thesis as the emergency retrieval device. This device serves the dual-purpose of providing absolute position measurements (via the cable that is tethered to the robot) as well as retrieving the robot if it is inoperable. The estimated accuracy of the proposed design is demonstrated with the use of a proof-of-concept prototype and a custom made test bench that uses a vision system to provide a more accurate estimate of the robot's position. The only major difference between the proof-of-concept prototype and the proposed solution is that the more expensive radiation hardened components were not used in the proof-of-concept prototype design. For example, the proposed solution shall use radiation hardened resolver wheels, whereas the proof-of-concept prototype used encoder wheels. These encoder wheels provide the same specified accuracy as the radiation hardened resolvers for the most realistic results possible. The rationale behind the design of the proof-of-concept prototype, the proposed final design, the design of the localization system test bench, and the test plan for developing all of the components of the design related to the robot's localization system are discussed in the thesis. The test plan provides a step by step guide to the configuration and optimization of an Unscented Kalman Filter (UKF). The UKF was selected as the ideal

Radiation applications in NDT in space program

International Nuclear Information System (INIS)

Viswanathan, K.

1994-01-01

Non-destructive testing (NDT) and evaluation play an important role in the qualification of sub-systems and components in space programme. NDT is carried out at various stages of manufacturing of components and also prior to end use to ensure a high degree of reliability. Penetrating radiations such as X-rays, γ-rays and neutrons are extensively used for the radiographic inspection of components, sub-systems and assemblies in both the launch vehicles and satellites. Both low and high energy radiations are employed for the evaluation of the above components depending on their size and nature. Real time radiography (RTR) and computed tomography (CT) are also used in certain specific applications where more detailed information is needed. Neutron radiography is employed for the inspection of pyro-devices used in separation, destruct and satellite deployment systems. Besides their use for non-destructive testing purposes, the radiation sources are also used for various special applications like solid propellant slurry flow measurement simulation of radiation environment on components used in the satellites and also for studying migration of ingredients in solid rocket motor. (author). 12 refs., 6 figs

Research on the method of establishing the total radiation meter calibration device

Science.gov (United States)

Gao, Jianqiang; Xia, Ming; Xia, Junwen; Zhang, Dong

2015-10-01

Pyranometer is an instrument used to measure the solar radiation, according to pyranometer differs as installation state, can be respectively measured total solar radiation, reflected radiation, or with the help of shading device for measuring scattering radiation. Pyranometer uses the principle of thermoelectric effect, inductive element adopts winding plating type multi junction thermopile, its surface is coated with black coating with high absorption rate. Hot junction in the induction surface, while the cold junction is located in the body, the cold and hot junction produce thermoelectric potential. In the linear range, the output signal is proportional to the solar irradiance. Traceability to national meteorological station, as the unit of the national legal metrology organizations, the responsibility is to transfer value of the sun and the earth radiation value about the national meteorological industry. Using the method of comparison, with indoor calibration of solar simulator, at the same location, standard pyranometer and measured pyranometer were alternately measured radiation irradiance, depending on the irradiation sensitivity standard pyranometer were calculated the radiation sensitivity of measured pyranometer. This paper is mainly about the design and calibration method of the pyranometer indoor device. The uncertainty of the calibration result is also evaluated.

Radiation damage and rate limitations in tracking devices

International Nuclear Information System (INIS)

Gilchriese, M.G.D.

1984-01-01

In this note the author briefly discusses radiation damage to wire chambers and silicon strip devices and the electronics that may be associated with each of these. Scintillating fibers and CCD's are not discussed although the former appears to be a potentially radiation-resistant detector. In order to calculate radiation levels and rates the author assumed the following: an inelastic cross section of 100 mb at the SSC - six charged particles per unit of rapidity - photons and neutrons do not contribute to the background (photon conversions are negligible with a thin Be beam pipe) - beam gas interactions and beam losses (except during injection when I assume that the detector is ''off'') are negligible. This is discussed in a later section. - 1 Rad = 3.5 x 10 7 minimum ionizing particlescm 2

60Co gamma radiation effect on AlGaN//AlN/GaN HEMT devices

International Nuclear Information System (INIS)

Wang Yanping; Luo Yinhong; Wang Wei; Zhang Keying; Guo Hongxia; Guo Xiaoqiang; Wang Yuanming

2013-01-01

The testing techniques and experimental methods of the 60 Co gamma irradiation effect on AlGaN/AlN/GaN high electron mobility transistors (HEMTs) are established. The degradation of the electrical properties of the device under the actual radiation environment are analyzed theoretically, and studies of the total dose effects of gamma radiation on AlGaN/AlN/GaN HEMTs at three different radiation bias conditions are carried out. The degradation patterns of the main parameters of the AlGaN/AlN/GaN HEMTs at different doses are then investigated, and the device parameters that were sensitive to the gamma radiation induced damage and the total dose level induced device damage are obtained. (authors)

Device for imaging an object by means of masks of spatially modulable electromagnetic radiation or corpuscular radiation of high energy

International Nuclear Information System (INIS)

Barrett, H.H.

1979-01-01

The radiogram of the thyroid is produced by means of a detector device operating similar to a scintillation camera. Between thyroid and detector device there is placed a mask having modulating areas, permeable and impermeable to radiation succeeding each other with decreasing extension. The scanning signal has got the shape of a radar signal with chirp modulation. The filtering unit used for it is a pulse compression filter. The image of the radiation energy distribution on the recording surface of the detector device is thus decoded and compressed to a number of image points giving the picture of the thyroid. (RW) [de

Reference neutron radiations. Part 2: Calibration fundamentals of radiation protection devices related to the basic quantities characterizing the radiation field

International Nuclear Information System (INIS)

2000-01-01

ISO 8529 consists of the following parts, under the general title Reference neutron radiations: Part 1: Characteristics and methods of production; Part 2: Calibration fundamentals of radiation protection devices related to the basic quantities characterizing the radiation field; Part 3: Calibration of area and personal dosimeters and determination of response as a function of energy and angle of incidence. This Part 2. of ISO 8529 takes as its starting point the neutron sources described in ISO 8529-1. It specifies the procedures to be used for realizing the calibration conditions of radiation protection devices in neutron fields produced by these calibration sources, with particular emphasis on the corrections for extraneous effects (e.g., the neutrons scattered from the walls of the calibration room). In this part of ISO 8529, particular emphasis is placed on calibrations using radionuclide sources (clauses 4 to 6) due to their widespread application, with less details given on the use of accelerator and reactor sources (8.2 and 8.3). This part of ISO 8529 then leads to ISO 8529-3 which gives conversion coefficients and the general rules and procedures for calibration

Damage estimation of sewer pipe using subtitles of CCTV inspection video

Science.gov (United States)

Park, Kitae; Kim, Byeongcheol; Kim, Taeheon; Seo, Dongwoo

2017-04-01

Recent frequent occurrence of urban sinkhole serves as a momentum of the periodic inspection of sewer pipelines. Sewer inspection using a CCTV device needs a lot of time and efforts. Many of previous studies which reduce the laborious tasks are mainly interested in the developments of image processing S/W and exploring H/W. And there has been no attempt to find meaningful information from the existing CCTV images stored by the sewer maintenance manager. This study adopts a cross-correlation based image processing method and extracts sewer inspection device's location data from CCTV images. As a result of the analysis of location-time relation, it show strong correlation between device stand time and the sewer damages. In case of using this method to investigate sewer inspection CCTV images, it will save the investigator's efforts and improve sewer maintenance efficiency and reliability.

Commercial power silicon devices as possible routine dosimeters for radiation processing

International Nuclear Information System (INIS)

Fuochi, P.G.; Lavalle, M.; Gombia, E.; Mosca, R.; Kovacs, A.V.; Hargittai, P.; Vitanza, A.; Patti, A.

2001-01-01

The use of silicon devices as possible radiation dosimeters has been investigated in this study. A bipolar power transistor in TO126 plastic packaging has been selected. Irradiations, with doses in the range from 50 Gy up to 5 kGy, have been performed at room temperature using different radiation sources ( 60 Co g source, 2.5, 4 and 12 MeV electron accelerators). Few irradiations with g rays were also done at different temperatures. A physical parameter, T, related to the charge carrier lifetime, has been found to change as a function of irradiation dose. This change is radiation energy dependent. Long term stability of the electron irradiated transistors has been checked by means of a reliability test ('high temperature reverse bias', HTRB) at 150 deg. C for 1000 h. Deep level transient spectroscopy (DLTS) measurements have been performed on the irradiated devices to identify the recombination centres introduced by the radiation treatment. The results obtained confirm that these transistors could be used as routine radiation dosimeters in a certain dose range. More work needs to be done particularly with g rays in the low dose region (50-200 Gy) and with low energy electrons. (author)

Radiation dermatitis caused by a bolus effect from an abdominal compression device

International Nuclear Information System (INIS)

Connor, Michael; Wei, Randy L.; Yu, Suhong; Sehgal, Varun; Klempner, Samuel J.; Daroui, Parima

2016-01-01

American Association of Physicists in Medicine (AAPM) Task Group 176 evaluated the dosimetric effects caused by couch tops and immobilization devices. The report analyzed the extensive physics-based literature on couch tops, stereotactic body radiation therapy (SBRT) frames, and body immobilization bags, while noting the scarcity of clinical reports of skin toxicity because of external devices. Here, we present a clinical case report of grade 1 abdominal skin toxicity owing to an abdominal compression device. We discuss the dosimetric implications of the utilized treatment plan as well as post hoc alternative plans and quantify differences in attenuation and skin dose/build-up between the device, a lower-density alternative device, and an open field. The description of the case includes a 66-year-old male with HER2 amplified poorly differentiated distal esophageal adenocarcinoma treated with neoadjuvant chemo-radiation and the use of an abdominal compression device. Radiation was delivered using volumetric modulated arc therapy (VMAT) with 2 arcs using abdominal compression and image guidance. The total dose was 50.4 Gy delivered over 40 elapsed days. With 2 fractions remaining, the patient developed dermatitis in the area of the compression device. The original treatment plan did not include a contour of the device. Alternative post hoc treatment plans were generated, one to contour the device and a second with anterior avoidance. In conclusion, replanning with the device contoured revealed the bolus effect. The skin dose increased from 27 to 36 Gy. planned target volume (PTV) coverage at 45 Gy was reduced to 76.5% from 95.8%. The second VMAT treatment plan with an anterior avoidance sector and more oblique beam angles maintained PTV coverage and spared the anterior wall, however at the expense of substantially increased dose to lung. This case report provides an important reminder of the bolus effect from external devices such as abdominal compression. Special

Radiation dermatitis caused by a bolus effect from an abdominal compression device

Energy Technology Data Exchange (ETDEWEB)

Connor, Michael; Wei, Randy L.; Yu, Suhong; Sehgal, Varun [Department of Radiation Oncology, University of California, Irvine Medical Center, Orange, CA (United States); Klempner, Samuel J. [Department of Medicine, Division of Hematology/Oncology, University of California, Orange, CA (United States); Daroui, Parima, E-mail: pdaroui@uci.edu [Department of Radiation Oncology, University of California, Irvine Medical Center, Orange, CA (United States)

2016-10-01

American Association of Physicists in Medicine (AAPM) Task Group 176 evaluated the dosimetric effects caused by couch tops and immobilization devices. The report analyzed the extensive physics-based literature on couch tops, stereotactic body radiation therapy (SBRT) frames, and body immobilization bags, while noting the scarcity of clinical reports of skin toxicity because of external devices. Here, we present a clinical case report of grade 1 abdominal skin toxicity owing to an abdominal compression device. We discuss the dosimetric implications of the utilized treatment plan as well as post hoc alternative plans and quantify differences in attenuation and skin dose/build-up between the device, a lower-density alternative device, and an open field. The description of the case includes a 66-year-old male with HER2 amplified poorly differentiated distal esophageal adenocarcinoma treated with neoadjuvant chemo-radiation and the use of an abdominal compression device. Radiation was delivered using volumetric modulated arc therapy (VMAT) with 2 arcs using abdominal compression and image guidance. The total dose was 50.4 Gy delivered over 40 elapsed days. With 2 fractions remaining, the patient developed dermatitis in the area of the compression device. The original treatment plan did not include a contour of the device. Alternative post hoc treatment plans were generated, one to contour the device and a second with anterior avoidance. In conclusion, replanning with the device contoured revealed the bolus effect. The skin dose increased from 27 to 36 Gy. planned target volume (PTV) coverage at 45 Gy was reduced to 76.5% from 95.8%. The second VMAT treatment plan with an anterior avoidance sector and more oblique beam angles maintained PTV coverage and spared the anterior wall, however at the expense of substantially increased dose to lung. This case report provides an important reminder of the bolus effect from external devices such as abdominal compression. Special

Transient photoconductive gain in a-Si:H devices and its applications in radiation detection

International Nuclear Information System (INIS)

Lee, H.K.; Suh, T.S.; Choe, B.Y.; Shinn, K.S.; Perez-Mendez, V.

1997-01-01

Using the transient behavior of the photoconductive-gain mechanism, a signal gain in radiation detection with a-Si:H devices may be possible. The photoconductive gain mechanism in two types of hydrogenated amorphous silicon devices, p-i-n and n-i-n configurations, was investigated in connection with applications to radiation detection. Photoconductive gain was measured in two time scales: one for short pulses of visible light ( 2 . Various gain results are discussed in terms of the device structure, applied bias and dark-current density. (orig.)

RIMACS, Reactor Inspection Main Control System

International Nuclear Information System (INIS)

2008-01-01

1 - Description of program or function: RIMACS prepares for automatic inspection files on each inspection item for the reactor. These automatic inspection files provide the data to move RIROB (Reactor Inspection Robot) with laser by interpreting the coordinates of LASPO (Laser Positioner) and the laser detecting device of RIROB in three dimensional space. In addition, when RIROB arrives at the inspecting location, the files provide all values of the manipulator's motions to acquire the ultrasonic data. RIMACS provides various modules in order to perform these complex functions, and the functions are programmed on graphic user interface for the convenience of the user. RIMACS provides various functions, such as insertion of reactor production data, selection of the reactor for inspection, the creation of automatic inspection file, the selection of the inspection item, inspection simulation, and automatic inspection procedures. It also provides all other functions, which are necessary for the inspection, such as operating program download and manual control of LASPO and RIROB, the inspection simulation and the inspection status display by means of the graphic screen, and SODAS (ultra-Sonic Data Acquisition System) drive verification. 2 - Methods: Moving path and operation procedures for inspection robot are generated automatically with Kinematics algorithm. 3 - Restrictions on the complexity of the problem: A graphics display with MS-Window capability is required

The research of nuclear experiment radiation environment wireless alarm device

International Nuclear Information System (INIS)

Wang Xiaoqiong; Wang Pan; Fang Fang

2009-01-01

This article introduces based on monolithic integrated circuit's nuclear experiment radiation environment wireless alarm device's software and hardware design. The system by G-M tube, high-pressured module, signal conditioning circuit, power source module, monolithic integrated circuit and wireless transmission module is composed. The device has low power consumption, high performance, high accuracy detection, easy maintenance, small size, simple operation, and other features, and has a broad application prospects. (authors)

Control of radioactive sources in industry through regulatory inspections

International Nuclear Information System (INIS)

Leocadio, J.C.; Ramalho, A.T.; Pinho, A.S.; Lourenco, M.M.J.; Nicola, M.S.; D'Avila, R.L.; Melo, I.F.; Cucco, A.C.S.

2005-01-01

In Brazil, the applications of ionizing radiation in industry are accomplished about 900 radioactive facilities, which handle approximately 3.000 radiation sources. The control of radioactive sources used in industrial installations authorized by the Brazilian Nuclear Energy Commission (CNEN) is accomplished by Servico de Radioprotecao na Industria Radiativa (SERIR) of the Instituto de Radioprotecao e Dosimetria (IRD), Rio de Janeiro, RJ, Brazil. This service carries out regulatory inspections in the practices of industrial radiography, nuclear gauges, industrial irradiators and oil wells logging. The frequency of inspections depends on the type of practice, ranging from a year to 5 years, depending on the risk involved. This paper presents a brief description of the situation of radiation safety in the use of radioactive sources in the industries of the country. The results obtained with regulatory inspections at industrial installations demonstrate that the conditions of safety and radiation protection in these facilities are satisfactory when compared with the technical regulations, both national and international

Radiation-resistant requirements analysis of device and control component for advanced spent fuel management process

Energy Technology Data Exchange (ETDEWEB)

Song, Tai Gil; Park, G. Y.; Kim, S. Y.; Lee, J. Y.; Kim, S. H.; Yoon, J. S. [Korea Atomic Energy Research Institute, Taejeon (Korea)

2002-02-01

It is known that high levels of radiation can cause significant damage by altering the properties of materials. A practical understanding of the effects of radiation - how radiation affects various types of materials and components - is required to design equipment to operate reliably in a gamma radiation environment. When designing equipment to operate in a high gamma radiation environment, such as will be present in a nuclear spent fuel handling facility, several important steps should be followed. In order to active test of the advanced spent fuel management process, the radiation-resistant analysis of the device and control component for active test which is concerned about the radiation environment is conducted. Also the system design process is analysis and reviewed. In the foreign literature, 'threshold' values are generally reported. the threshold values are normally the dose required to begin degradation in a particular material property. The radiation effect analysis for the device of vol-oxidation and metalization, which are main device for the advanced spent fuel management process, is performed by the SCALE 4.4 code. 5 refs., 4 figs., 13 tabs. (Author)

Ultrasonic inspection of inpile tubes

International Nuclear Information System (INIS)

Boyd, D.M.; Bossi, H.

1985-01-01

The in-service inspection (ISI) of inpile tubes can be performed accurately and safely with a semiautomatic ultrasonic inspection system. The ultrasonic technique uses a set of multiple transducers to detect and size cracks, voids, and laminations radially and circumferentially. Welds are also inspected for defects. The system is designed to inspect stainless steel and Inconel tubes ranging from 53.8 mm (2.12 in.) to 101.6 mm (4 in.) inner diameter with wall thickness on the order of 5 mm. The inspection head contains seven transducers mounted in a surface-following device. Six angle-beam transducers generate shear waves in the tubes. Two of the six are oriented to detect circumferential cracks, and two detect axial cracks. Although each of these four transducers is used in the pulse-echo mode, they are oriented in aligned sets so pitch-catch operation is possible if desired. The remaining angle-beam transducers are angulated to detect flaws that are off axial or circumferential orientation. The seventh transducer is used for longitudinal inspection and detects and sizes laminar-type defects

Signal Processing Device (SPD) for networked radiation monitoring system

International Nuclear Information System (INIS)

Dharmapurikar, A.; Bhattacharya, S.; Mukhopadhyay, P.K.; Sawhney, A.; Patil, R.K.

2010-01-01

A networked radiation and parameter monitoring system with three tier architecture is being developed. Signal Processing Device (SPD) is a second level sub-system node in the network. SPD is an embedded system which has multiple input channels and output communication interfaces. It acquires and processes data from first level parametric sensor devices, and sends to third level devices in response to request commands received from host. It also performs scheduled diagnostic operations and passes on the information to host. It supports inputs in the form of differential digital signals and analog voltage signals. SPD communicates with higher level devices over RS232/RS422/USB channels. The system has been designed with main requirements of minimal power consumption and harsh environment in radioactive plants. This paper discusses the hardware and software design details of SPD. (author)

Developing equipment for AGR remote visual inspection

International Nuclear Information System (INIS)

James, P.W.; Walton, P.J.

1985-01-01

The Remote Inspection Group is part of the CEGB's Generation Development and Construction Division, and has responsibility for the design, development, procurement, testing and setting to work of the equipment provided to carry out routine remote visual inspections of its AGRs. This equipment includes both the viewing devices and the necessary placement equipment. (author)

Development of inspection safety evaluation technology

Energy Technology Data Exchange (ETDEWEB)

Yoon, Seok Chul; Yoon, Yeo Chang; Kim, Jong Soo; Lee, Tae Young; Kim, Chang Ryol; Lee, Hyung Sub; Kim, Jong Soo

1995-12-01

The purpose of this project is to protection nation inspector`s over exposure from radiation that can be occurred by inspection activity at nuclear facilities and its environment, and to ensure the safety of inspection activity at the nuclear facilities. To effectively carry out the domestic inspection task to be enforced from 1996, the evaluation for special radiation exposure rate of nuclear facilities, air and surface contamination level, and measurement and monitoring of water contamination level were made to determine whether these measured values exceeded permissible limitations, and to protect the inspector`s over exposure from radiation at domestic nuclear facilities. Management of inspector`s exposure was carried out under assistance of the Department of Health Physics. Performance tests of two gamma detectors, one neutron detector, alpha and beta detector, and gamma spectroscopy analyzer were carried out to control dose on extremity, the characteristic test for extremity dosimeter was carried out and the theoretical calculation of gamma dose conversion factors based on ANSI N13.32 standard was performed. Under the 93+2 program, IAEA began to recognize the necessity of environmental observation technology development of air-borne particulates travelled from long distance location. Associated with the necessity of this technology development, a proposal of international joint research for development of the special radiation measurement and analysis has been prepared. (author). 21 tabs., 24 figs., 20 refs.

Radiation Protection, Safety and Security Issues in Ghana

International Nuclear Information System (INIS)

Boadu, M. B.; Emi-Reynolds, G.; Amoako, J. K.; Hasford, F.; Akrobortu, E.

2015-01-01

The Radiation Protection Board was established in 1993 by PNDC Law 308 as the National Competent Authority for the regulation of radiation sources and radioactive materials in Ghana. The mandate and responsibilities of RPB are prescribed in the legislative instrument, LI 1559 issued in 1993. The operational functions of the Board are carried out by the Radiation Protection Institute, which was established to provide technical support for the enforcement of the legislative instrument. The regulatory activities include among others: – Issuance permits for the import/export of any radiation producing device and radioactive materials into/out of the country. It therefore certifies the radioactivity levels in food and the environmental samples. – Authorization and Inspection of practices using radiation sources and radioactive materials in Ghana. – Undertakes safety assessment services and enforcement actions on practices using radiation sources and radioactive materials in line with regulations. – Provides guidance and technical support in fulfilling regulatory requirement to users of radiation producing devices and radioactive materials nationwide by monitoring of monthly radiation absorbed doses for personnel working at radiation facilities. – Provides support to the management of practices in respect of nuclear and radioactive waste programme. – Calibrates radiation emitting equipment and nuclear instrumentation to ensure the safety of patients, workers and the general public. – Establish guidelines for the mounting (non-ionizing) communication masts. – Environmental monitoring (non-ionizing) programmes for communication masts. With the establishment of the national competent authority, facilities using radioactive sources and radiation emitting devices have been brought under regulatory control. Effective regulatory control of radiation emitting devices are achieved through established legal framework, independent Regulatory Authority supported by

Exploring graphene field effect transistor devices to improve spectral resolution of semiconductor radiation detectors

Energy Technology Data Exchange (ETDEWEB)

Harrison, Richard Karl [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Howell, Stephen Wayne [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Martin, Jeffrey B. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Hamilton, Allister B. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

2013-12-01

Graphene, a planar, atomically thin form of carbon, has unique electrical and material properties that could enable new high performance semiconductor devices. Graphene could be of specific interest in the development of room-temperature, high-resolution semiconductor radiation spectrometers. Incorporating graphene into a field-effect transistor architecture could provide an extremely high sensitivity readout mechanism for sensing charge carriers in a semiconductor detector, thus enabling the fabrication of a sensitive radiation sensor. In addition, the field effect transistor architecture allows us to sense only a single charge carrier type, such as electrons. This is an advantage for room-temperature semiconductor radiation detectors, which often suffer from significant hole trapping. Here we report on initial efforts towards device fabrication and proof-of-concept testing. This work investigates the use of graphene transferred onto silicon and silicon carbide, and the response of these fabricated graphene field effect transistor devices to stimuli such as light and alpha radiation.

Dosimetric studies for gamma radiation validation of medical devices

International Nuclear Information System (INIS)

Soliman, Y.S.; Beshir, W.B.; Abdel-Fattah, A.A.; Abdel-Rehim, F.

2013-01-01

The delivery and validation of a specified dose to medical devices are key concerns to operators of gamma radiation facilities. The objective of the present study was to characterize the industrial gamma radiation facility and map the dose distribution inside the product-loading pattern during the validation and routine control of the sterilization process using radiochromic films. Cardboard phantoms were designed to achieve the homogeneity of absorbed doses. The uncertainty of the dose delivered during validation of the sterilization process was assessed. - Highlights: ► Using γ-rays for sterilization of hollow fiber dialyzers and blood tubing sets according to ISO 11137, 2006. ► Dosimetry studies of validations of γ-irradiation facility and sterilized medical devices. ► Places of D min and D max have been determined using FWT-60 films. ► Determining the target minimum doses required to meet the desired SAL of 10 −6 for the two products.

Irradiation technology Pt. 2. Research devices. Glossary on radiation technology. Besugarzastechnika 2. resz. Kiserleti berendezesek, sugartechnikai kislexikon

Energy Technology Data Exchange (ETDEWEB)

Foeldiak, G; Stenger, V

1982-01-01

It is a textbook and manual of a training course held at the Budapest Technical University for operators of irradiation devices. Calculation methods of radiation technology (estimation of activity variation, space dependence of dose rates, shielding, efficiency) are presented. Instructions for laboratory exercises (dose and dose rate measurements, sterilization by irradiation, handling of irradiation devices) involved in the course given. Two laboratory irradiation devices (RH-GAMMA-30, produced in the Soviet Union and the K-120-type semi-large scale device of the Isotope Institute of the Hungarian Academy of Sciences are described in detail. Handling instructions for the two devices and radiation protection regulations are given. A brief glossary in the field of radiation technology is added.

Medical Device Recalls in Radiation Oncology: Analysis of US Food and Drug Administration Data, 2002-2015

International Nuclear Information System (INIS)

Connor, Michael J.; Tringale, Kathryn; Moiseenko, Vitali; Marshall, Deborah C.; Moore, Kevin; Cervino, Laura; Atwood, Todd; Brown, Derek; Mundt, Arno J.; Pawlicki, Todd; Recht, Abram; Hattangadi-Gluth, Jona A.

2017-01-01

Purpose: To analyze all recalls involving radiation oncology devices (RODs) from the US Food and Drug Administration (FDA)'s recall database, comparing these with non–radiation oncology device recalls to identify discipline-specific trends that may inform improvements in device safety. Methods and Materials: Recall data on RODs from 2002 to 2015 were sorted into 4 product categories (external beam, brachytherapy, planning systems, and simulation systems). Outcomes included determined cause of recall, recall class (severity), quantity in commerce, time until recall termination (date FDA determines recall is complete), and time since 510(k) approval. Descriptive statistics were performed with linear regression of time-series data. Results for RODs were compared with those for other devices by Pearson χ"2 test for categorical data and 2-sample Kolmogorov-Smirnov test for distributions. Results: There were 502 ROD recalls and 9534 other class II device recalls during 2002 to 2015. Most recalls were for external beam devices (66.7%) and planning systems (22.9%), and recall events peaked in 2011. Radiation oncology devices differed significantly from other devices in all recall outcomes (P≤.04). Recall cause was commonly software related (49% vs 10% for other devices). Recall severity was more often moderate among RODs (97.6% vs 87.2%) instead of severe (0.2% vs 4.4%; P<.001). Time from 510(k) market approval to recall was shorter among RODs (P<.001) and progressively shortened over time. Radiation oncology devices had fewer recalled devices in commerce than other devices (P<.001). Conclusions: Compared with other class II devices, RODs experience recalls sooner after market approval and are trending sooner still. Most of these recalls were moderate in severity, and software issues are prevalent. Comprehensive analysis of recall data can identify areas for device improvement, such as better system design among RODs.

Medical Device Recalls in Radiation Oncology: Analysis of US Food and Drug Administration Data, 2002-2015

Energy Technology Data Exchange (ETDEWEB)

Connor, Michael J. [Department of Radiation Medicine and Applied Sciences, University of California, San Diego, La Jolla, California (United States); University of California Irvine School of Medicine, Irvine, California (United States); Tringale, Kathryn; Moiseenko, Vitali; Marshall, Deborah C.; Moore, Kevin; Cervino, Laura; Atwood, Todd; Brown, Derek; Mundt, Arno J.; Pawlicki, Todd [Department of Radiation Medicine and Applied Sciences, University of California, San Diego, La Jolla, California (United States); Recht, Abram [Department of Radiation Oncology, Beth Israel Deaconess Medical Center, Harvard Medical School, Boston, Massachusetts (United States); Hattangadi-Gluth, Jona A., E-mail: jhattangadi@ucsd.edu [Department of Radiation Medicine and Applied Sciences, University of California, San Diego, La Jolla, California (United States)

2017-06-01

Purpose: To analyze all recalls involving radiation oncology devices (RODs) from the US Food and Drug Administration (FDA)'s recall database, comparing these with non–radiation oncology device recalls to identify discipline-specific trends that may inform improvements in device safety. Methods and Materials: Recall data on RODs from 2002 to 2015 were sorted into 4 product categories (external beam, brachytherapy, planning systems, and simulation systems). Outcomes included determined cause of recall, recall class (severity), quantity in commerce, time until recall termination (date FDA determines recall is complete), and time since 510(k) approval. Descriptive statistics were performed with linear regression of time-series data. Results for RODs were compared with those for other devices by Pearson χ{sup 2} test for categorical data and 2-sample Kolmogorov-Smirnov test for distributions. Results: There were 502 ROD recalls and 9534 other class II device recalls during 2002 to 2015. Most recalls were for external beam devices (66.7%) and planning systems (22.9%), and recall events peaked in 2011. Radiation oncology devices differed significantly from other devices in all recall outcomes (P≤.04). Recall cause was commonly software related (49% vs 10% for other devices). Recall severity was more often moderate among RODs (97.6% vs 87.2%) instead of severe (0.2% vs 4.4%; P<.001). Time from 510(k) market approval to recall was shorter among RODs (P<.001) and progressively shortened over time. Radiation oncology devices had fewer recalled devices in commerce than other devices (P<.001). Conclusions: Compared with other class II devices, RODs experience recalls sooner after market approval and are trending sooner still. Most of these recalls were moderate in severity, and software issues are prevalent. Comprehensive analysis of recall data can identify areas for device improvement, such as better system design among RODs.

Recommended safety procedures for the selection, installation and use of baggage inspection x-ray equipment

International Nuclear Information System (INIS)

1978-05-01

Good X-ray equipment alone will not preclude unnecessary exposure to x-radiation. The equipment must be installed, maintained and used by adequately trained personnel, with due regard for the inherent hazards of such equipment and an appreciation of the need to observe proper operational procedures. It is the intent of this Code to define equipment specifications and conditions of installation and use for baggage inspection X-ray equipment, such that the hazard to operating personnel and the general public from such devices remains negligibly small. (auth)

Extreme Radiation Hardness and Space Qualification of AlGaN Optoelectronic Devices

International Nuclear Information System (INIS)

Sun, Ke-Xun; MacNeil, Lawrence; Balakrishnan, Kathik; Hultgren, Eric; Goebel, John; Bilenko, Yuri; Yang, Jinwei; Sun, Wenhong; Shatalov, Max; Hu, Xuhong; Gaska, Remis

2010-01-01

Unprecedented radiation hardness and environment robustness are required in the new generation of high energy density physics (HEDP) experiments and deep space exploration. National Ignition Facility (NIF) break-even shots will have a neutron yield of 10 15 or higher. The Europa Jupiter System Mission (EJSM) mission instruments will be irradiated with a total fluence of 10 12 protons/cm 2 during the space journey. In addition, large temperature variations and mechanical shocks are expected in these applications under extreme conditions. Hefty radiation and thermal shields are required for Si and GaAs based electronics and optoelectronics devices. However, for direct illumination and imaging applications, shielding is not a viable option. It is an urgent task to search for new semiconductor technologies and to develop radiation hard and environmentally robust optoelectronic devices. We will report on our latest systematic experimental studies on radiation hardness and space qualifications of AlGaN optoelectronic devices: Deep UV Light Emitting Diodes (DUV LEDs) and solarblind UV Photodiodes (PDs). For custom designed AlGaN DUV LEDs with a central emission wavelength of 255 nm, we have demonstrated its extreme radiation hardness up to 2 x 10 12 protons/cm 2 with 63.9 MeV proton beams. We have demonstrated an operation lifetime of over 26,000 hours in a nitrogen rich environment, and 23,000 hours of operation in vacuum without significant power drop and spectral shift. The DUV LEDs with multiple packaging styles have passed stringent space qualifications with 14 g random vibrations, and 21 cycles of 100K temperature cycles. The driving voltage, current, emission spectra and optical power (V-I-P) operation characteristics exhibited no significant changes after the space environmental tests. The DUV LEDs will be used for photoelectric charge management in space flights. For custom designed AlGaN UV photodiodes with a central response wavelength of 255 nm, we have

Device for positioning ultrasonic probes and/or television cameras on the outer surface of reactor pressure vessels

International Nuclear Information System (INIS)

Zipser, R.; Dose, G.F.

1977-01-01

The device makes possible periodical in-service inspections of welding seams and material of a reactor pressure vessel without local human presence. A 'support ring' encloses the pressure vessel in a horizontal plane with free space. It is vertically moved up and down in the space between pressure vessel and thermal shield by means of tackles. At a control desk placed in a protected area its movement is controlled and its vertical position is indicated. A 'rotating track' with its own drive is rotating remote-controlled on the 'support ring'. By a combination of the vertical with the rotating movement, an ultrasonic probe placed removably on the 'rotating hack', or a television camera will be brought to any position on the cylindrical circumference of the pressure vessel. Special devices extend the radius of action, in upward direction for inspecting the welding seams of the coolant nozzles, and in downward direction for the inspection of welds on the hemispherical bottom of the pressure vessel or on the outlet pipe nozzle placed there. The device remains installed during reactor operation, but is moved down to the lower horizontal surface of the thermal shield. Parts which are sensible to radiation like probes or television cameras and special devices will then be removed respectively mounted before beginning an inspection compaign. This position may be reached by the lower access in the biological shield and through an opening in the horizontal surface of the thermal shield. (HP) [de

Modeling of transient ionizing radiation effects in bipolar devices at high dose-rates

International Nuclear Information System (INIS)

FJELDLY, T.A.; DENG, Y.; SHUR, M.S.; HJALMARSON, HAROLD P.; MUYSHONDT, ARNOLDO

2000-01-01

To optimally design circuits for operation at high intensities of ionizing radiation, and to accurately predict their a behavior under radiation, precise device models are needed that include both stationary and dynamic effects of such radiation. Depending on the type and intensity of the ionizing radiation, different degradation mechanisms, such as photoelectric effect, total dose effect, or single even upset might be dominant. In this paper, the authors consider the photoelectric effect associated with the generation of electron-hole pairs in the semiconductor. The effects of low radiation intensity on p-II diodes and bipolar junction transistors (BJTs) were described by low-injection theory in the classical paper by Wirth and Rogers. However, in BJTs compatible with modem integrated circuit technology, high-resistivity regions are often used to enhance device performance, either as a substrate or as an epitaxial layer such as the low-doped n-type collector region of the device. Using low-injection theory, the transient response of epitaxial BJTs was discussed by Florian et al., who mainly concentrated on the effects of the Hi-Lo (high doping - low doping) epilayer/substrate junction of the collector, and on geometrical effects of realistic devices. For devices with highly resistive regions, the assumption of low-level injection is often inappropriate, even at moderate radiation intensities, and a more complete theory for high-injection levels was needed. In the dynamic photocurrent model by Enlow and Alexander. p-n junctions exposed to high-intensity radiation were considered. In their work, the variation of the minority carrier lifetime with excess carrier density, and the effects of the ohmic electric field in the quasi-neutral (q-n) regions were included in a simplified manner. Later, Wunsch and Axness presented a more comprehensive model for the transient radiation response of p-n and p-i-n diode geometries. A stationary model for high-level injection in p

Characterization of Radiation Hardened Bipolar Linear Devices for High Total Dose Missions

Science.gov (United States)

McClure, Steven S.; Harris, Richard D.; Rax, Bernard G.; Thorbourn, Dennis O.

2012-01-01

Radiation hardened linear devices are characterized for performance in combined total dose and displacement damage environments for a mission scenario with a high radiation level. Performance at low and high dose rate for both biased and unbiased conditions is compared and the impact to hardness assurance methodology is discussed.

Asymmetric devices based on carbon nanotubes for terahertz-range radiation detection

Energy Technology Data Exchange (ETDEWEB)

Fedorov, G. E., E-mail: gefedorov@mail.ru; Stepanova, T. S.; Gazaliev, A. Sh.; Gaiduchenko, I. A.; Kaurova, N. S.; Voronov, B. M.; Goltzman, G. N. [Moscow State Pedagogical University (Russian Federation)

2016-12-15

Various asymmetric detecting devices based on carbon nanotubes (CNTs) are studied. The asymmetry is understood as inhomogeneous properties along the conducting channel. In the first type of devices, an inhomogeneous morphology of the CNT grid is used. In the second type of devices, metals with highly varying work functions are used as the contact material. The relation between the sensitivity and detector configuration is analyzed. Based on the data obtained, approaches to the development of an efficient detector of terahertz radiation, based on carbon nanotubes are proposed.

Radiation Testing, Characterization and Qualification Challenges for Modern Microelectronics and Photonics Devices and Technologies

Science.gov (United States)

LaBel, Kenneth A.; Cohn, Lewis M.

2008-01-01

At GOMAC 2007, we discussed a selection of the challenges for radiation testing of modern semiconductor devices focusing on state-of-the-art memory technologies. This included FLASH non-volatile memories (NVMs) and synchronous dynamic random access memories (SDRAMs). In this presentation, we extend this discussion in device packaging and complexity as well as single event upset (SEU) mechanisms using several technology areas as examples including: system-on-a-chip (SOC) devices and photonic or fiber optic systems. The underlying goal is intended to provoke thought for understanding the limitations and interpretation of radiation testing results.

Remotely-operated equipment for inspection, measurement and handling

CERN Document Server

Bertone, C; CERN. Geneva. TS Department

2008-01-01

As part of the application of ALARA radiation dose reduction principles at CERN, inspection, measurement and handling interventions in controlled areas are being studied in detail. A number of activities which could be carried out as remote operations have already been identified and equipment is being developed. Example applications include visual inspection to check for ice formation on LHC components or water leaks, measurement of radiation levels before allowing personnel access, measurement of collimator or magnet alignment, visual inspection or measurements before fire service access in the event of fire, gas leak or oxygen deficiency. For these applications, a modular monorail train, TIM, has been developed with inspection and measurement wagons. In addition TIM provides traction, power and data communication for lifting and handling units such as the remote collimator exchange module and vision for other remotely operated units such as the TAN detector exchange mini-cranes. This paper describes the eq...

In-service inspections of V-230 reactor

International Nuclear Information System (INIS)

Prepechal, J.

1984-01-01

It is stated that despite certain constraints the configuration of the WWER-440 is such that it allows to make in-service inspections on a fully satisfactory scale. Three factors are discussed whose existence is necessary for the implementation of in-service inspections. The program defining the scale of inspections is satisfactory with regard to the safety and reliability of reactor operation. Its further development must result in reducing time consumption and radiation burden of personnel. Regulations for the implementation and evaluation of inspections represent the weakest link in the system of in-service inspections. At present, various organizations are dealing with the said problem within international cooperation. Equipment for in-service inspections of WWER-440 reactors is relatively good. The most important knowledge is summed up gained from the ten pre-service and in-service inspections of reactors of this type made so far. (Z.M.)

Intelligent Automated Nuclear Fuel Pellet Inspection System

International Nuclear Information System (INIS)

Keyvan, S.

1999-01-01

At the present time, nuclear pellet inspection is performed manually using naked eyes for judgment and decisionmaking on accepting or rejecting pellets. This current practice of pellet inspection is tedious and subject to inconsistencies and error. Furthermore, unnecessary re-fabrication of pellets is costly and the presence of low quality pellets in a fuel assembly is unacceptable. To improve the quality control in nuclear fuel fabrication plants, an automated pellet inspection system based on advanced techniques is needed. Such a system addresses the following concerns of the current manual inspection method: (1) the reliability of inspection due to typical human errors, (2) radiation exposure to the workers, and (3) speed of inspection and its economical impact. The goal of this research is to develop an automated nuclear fuel pellet inspection system which is based on pellet video (photographic) images and uses artificial intelligence techniques

The solar ultraviolet B radiation protection provided by shading devices with regard to its diffuse component.

Science.gov (United States)

Kudish, Avraham I; Harari, Marco; Evseev, Efim G

2011-10-01

The composition of the incident solar global ultraviolet B (UVB) radiation with regard to its beam and diffuse radiation fractions is highly relevant with regard to outdoor sun protection. This is especially true with respect to sun protection during leisure-time outdoor sun exposure at the shore and pools, where people tend to escape the sun under shade trees or different types of shading devices, e.g., umbrellas, overhangs, etc., believing they offer protection from the erythemal solar radiation. The degree of sun protection offered by such devices is directly related to the composition of the solar global UVB radiation, i.e., its beam and diffuse fractions. The composition of the incident solar global UVB radiation can be determined by measuring the global UVB (using Solar Light Co. Inc., Model 501A UV-Biometer) and either of its components. The beam component of the UVB radiation was determined by measuring the normal incidence beam radiation using a prototype, tracking instrument consisting of a Solar Light Co. Inc. Model 501A UV-Biometer mounted on an Eppley Solar Tracker Model St-1. The horizontal beam component of the global UVB radiation was calculated from the measured normal incidence using a simple geometric correlation and the diffuse component is determined as the difference between global and horizontal beam radiations. Horizontal and vertical surfaces positioned under a horizontal overhang/sunshade or an umbrella are not fully protected from exposure to solar global UVB radiation. They can receive a significant fraction of the UVB radiation, depending on their location beneath the shading device, the umbrella radius and the albedo (reflectance) of the surrounding ground surface in the case of a vertical surface. Shading devices such as an umbrella or horizontal overhang/shade provide relief from the solar global radiation and do block the solar global UVB radiation to some extent; nevertheless, a significant fraction of the solar global UVB

MACS as a tool for international inspections

Energy Technology Data Exchange (ETDEWEB)

Curtiss, J.A.; Indusi, J.P.

1995-08-01

The MACS/ACRS (Managed Access by Controlled Sensing/Access by Controlled Remote Sensing) system is a collection of communication devices, video capability, and distance-measuring equipment which can effectively substitute for the physical presence of a challenge inspector within a facility. The MACS design allows growth of the prototype, developed in response to the Chemical Weapons Convention (CWC), into a versatile device for inspection of sensitive nuclear facilities under other international arrangements, for example the proposed Fissile Material Cutoff Convention. A MACS/ACRS-type system in a standard, international-recognized configuration could resolve sensitive information and safety concerns through providing a means of achieving the goals of an inspection while excluding the inspector. We believe the technology used to develop MACS for the Defense Nuclear Agency, followed by ACRS for the Department of Energy, is universally adaptable for minimally-intrusive managed-access international inspections of sensitive sites.

MACS as a tool for international inspections

International Nuclear Information System (INIS)

Curtiss, J.A.; Indusi, J.P.

1995-01-01

The MACS/ACRS (Managed Access by Controlled Sensing/Access by Controlled Remote Sensing) system is a collection of communication devices, video capability, and distance-measuring equipment which can effectively substitute for the physical presence of a challenge inspector within a facility. The MACS design allows growth of the prototype, developed in response to the Chemical Weapons Convention (CWC), into a versatile device for inspection of sensitive nuclear facilities under other international arrangements, for example the proposed Fissile Material Cutoff Convention. A MACS/ACRS-type system in a standard, international-recognized configuration could resolve sensitive information and safety concerns through providing a means of achieving the goals of an inspection while excluding the inspector. We believe the technology used to develop MACS for the Defense Nuclear Agency, followed by ACRS for the Department of Energy, is universally adaptable for minimally-intrusive managed-access international inspections of sensitive sites

A survey of synchrotron radiation devices producing circular or variable polarization

International Nuclear Information System (INIS)

Kim, K.J.

1990-01-01

This paper reviews the properties and operating principles of the new types of synchrotron radiation devices that produce circular polarization, or polarization that can be modulated in arbitrary fashion

Short and long term ionizing radiation effects on charge-coupled devices in radiation environment of high-intensity heavy ion accelerators

International Nuclear Information System (INIS)

Belousov, A; Mustafin, E; Ensinger, W

2012-01-01

Radiation effects on semiconductor devices is a topical issue for high-intensity accelerator projects. In particular it concerns Charge-Coupled Device (CCD) cameras, which are widely used for beam profile monitoring and surveillance in high radiation environment. One should have a clear idea of short and long term radiation effects on such devices. To study these effects, a CCD camera was placed in positions less than half meter away from beam loss point. Primary heavy ion beam of 0.95GeV/n Uranium was dumped into a thick aluminium target creating high fluences of secondary particles (e.g., gammas, neutrons, protons). Effects of these particles on CCD camera were scored with LabView based acquisition software. Monte Carlo calculations with FLUKA code were performed to obtain fluence distributions for different particles and make relevant comparisons. Long term total ionising dose effects are represented by dark current increase, which was scored throughout experiment. Instant radiation effects are represented by creation of charge in CCD cells by ionising particles. Relation of this charge to beam intensity was obtained for different camera positions and fluences within 5 orders of magnitude ranges. With high intensities this charge is so high that it may dramatically influence data obtained from CCD camera used in high radiation environment. The linearity of described above relation confirms linear response of CCD to ionizing radiation. It gives an opportunity to find a new application to CCD cameras as beam loss monitors (BLM).

A Mobile Robotic System for the Inspection and Repair of SG Tubes in NPPs

Directory of Open Access Journals (Sweden)

Yong-Chil Seo

2016-04-01

Full Text Available The reliability and performance of a steam generator (SG is one of the serious concerns in the operation of pressurized water nuclear power plants. Because of high levels of radiation, robotic systems have been used to inspect and repair SG tubes. In this paper, we present a mobile robotic system that positions the inspection and repair tools while hanging down from the tube sheets where the tubes are fixed. All of the driving mechanisms of the mobile robot are actuated by electric motors to start its works, providing that the electric power is prepared without the additional need for an on-site air services. A special tube-holding mechanism with a high holding force has been developed to prevent falling from the tube sheets, even in the case of an electric power failure. We have also developed a quick installation guide device that guides the mobile robot to desired initial positions in the tube sheet exactly and quickly, which helps to reduce the radiation exposure of human workers during the installation work. This paper also provides on-site experimental results and lessons learned.

241-AY-102 Leak Detection Pit Drain Line Inspection Report

International Nuclear Information System (INIS)

Boomer, Kayle D.; Engeman, Jason K.; Gunter, Jason R.; Joslyn, Cameron C.; Vazquez, Brandon J.; Venetz, Theodore J.; Garfield, John S.

2014-01-01

This document provides a description of the design components, operational approach, and results from the Tank AY-102 leak detection pit drain piping visual inspection. To perform this inspection a custom robotic crawler with a deployment device was designed, built, and operated by IHI Southwest Technologies, Inc. for WRPS to inspect the 6-inch leak detection pit drain line

Short term ionizing radiation impact on charge-coupled devices in radiation environment of high-intensity heavy ion accelerators

International Nuclear Information System (INIS)

Belousov, A.; Mustafin, E.; Ensinger, W.

2012-01-01

This paper presents a first approach on studies of the results of short term ionizing radiation impact on charge-coupled device (CCD) chips in conditions typical for high-intensity ion accelerator areas. Radiation effects on semiconductor devices are a topical issue for high-intensity accelerator projects. In particular it concerns CCD cameras that are widely used for beam profile monitoring and surveillance in high radiation environment. 65 CCD cameras are going to be installed in the FAIR machines. It is necessary to have good understanding of radiation effects and their contribution to measured signal in CCD chips. A phenomenon of single event upset (SEU) in CCD chips is studied in the following experiment. By SEU in CCD chip we mean an event when an ionizing particle hits the CCD matrix cell and produces electron-hole pairs that are then collected and converted to a signal that is higher than certain level defined by author. Practically, it means that a certain cell will appear as a bright pixel on the resulting image from a chip. (authors)

New small devices for radiation detection: the Wee Pocket Chirper and the Portable Multichannel Analyzer

International Nuclear Information System (INIS)

Umbarger, C.J.

1980-08-01

Recent events have demonstrated the need for improved capability to monitor the exposure of workers to radiation and, in general, to identify and measure the many forms of radioactive materials found throughout the nuclear industry. Two radiation monitoring devices have been developed that are much smaller than existing instruments, yet exhibit superior performance and a longer battery life. The first instrument, the Wee Pocket Chirper, is a tiny, battery-powered warning device that chirps when exposed to radiation. The second instrument is a portable battery-powered, computer-based, multichannel analyzer that allows the user to examine radiation fields and to identify the types and amounts of radioactive materials present

Radionuclides for process control and inspection

International Nuclear Information System (INIS)

Hadden, R.J.B.

1987-01-01

Radiation sources have been used in process control for over 40 years. Their use in inspection, implying visual examination, although of much earlier origin in the form of gamma radiography, is also of recent emergence in the form of tomographic methods. This paper firstly reviews the justification for the continued world-wide usage of isotopic methods. It then reviews a selection of innovative process control applications, based on radiation sources, as illustrations of the present state of the art and also describes recent progress in inspection methods including progress in the development of on-line facilities. For all applications involving radiation sources, careful selection of parameters is required to achieve the highest efficiency compatible with an integrity suitable for the intended application. The paper concludes with a brief discussion of the common principles on which the fabrication of sources is based in order to satisfy national and international safety legislation. (author)

Machine vision system for remote inspection in hazardous environments

International Nuclear Information System (INIS)

Mukherjee, J.K.; Krishna, K.Y.V.; Wadnerkar, A.

2011-01-01

Visual Inspection of radioactive components need remote inspection systems for human safety and equipment (CCD imagers) protection from radiation. Elaborate view transport optics is required to deliver images at safe areas while maintaining fidelity of image data. Automation of the system requires robots to operate such equipment. A robotized periscope has been developed to meet the challenge of remote safe viewing and vision based inspection. (author)

Motion correction for passive radiation imaging of small vessels in ship-to-ship inspections

Energy Technology Data Exchange (ETDEWEB)

Ziock, K.P., E-mail: ziockk@ornl.gov [Oak Ridge National Laboratory, Oak Ridge, TN (United States); Boehnen, C.B.; Ernst, J.M.; Fabris, L. [Oak Ridge National Laboratory, Oak Ridge, TN (United States); Hayward, J.P. [Oak Ridge National Laboratory, Oak Ridge, TN (United States); Department of Nuclear Engineering, University of Tennessee, Knoxville, TN (United States); Karnowski, T.P.; Paquit, V.C.; Patlolla, D.R. [Oak Ridge National Laboratory, Oak Ridge, TN (United States); Trombino, D.G. [Lawrence Livermore National Laboratory, Livermore, CA (United States)

2016-01-01

Passive radiation detection remains one of the most acceptable means of ascertaining the presence of illicit nuclear materials. In maritime applications it is most effective against small to moderately sized vessels, where attenuation in the target vessel is of less concern. Unfortunately, imaging methods that can remove source confusion, localize a source, and avoid other systematic detection issues cannot be easily applied in ship-to-ship inspections because relative motion of the vessels blurs the results over many pixels, significantly reducing system sensitivity. This is particularly true for the smaller watercraft, where passive inspections are most valuable. We have developed a combined gamma-ray, stereo visible-light imaging system that addresses this problem. Data from the stereo imager are used to track the relative location and orientation of the target vessel in the field of view of a coded-aperture gamma-ray imager. Using this information, short-exposure gamma-ray images are projected onto the target vessel using simple tomographic back-projection techniques, revealing the location of any sources within the target. The complex autonomous tracking and image reconstruction system runs in real time on a 48-core workstation that deploys with the system.

Energy harvesting devices for harvesting energy from terahertz electromagnetic radiation

Science.gov (United States)

Novack, Steven D.; Kotter, Dale K.; Pinhero, Patrick J.

2012-10-09

Methods, devices and systems for harvesting energy from electromagnetic radiation are provided including harvesting energy from electromagnetic radiation. In one embodiment, a device includes a substrate and one or more resonance elements disposed in or on the substrate. The resonance elements are configured to have a resonant frequency, for example, in at least one of the infrared, near-infrared and visible light spectra. A layer of conductive material may be disposed over a portion of the substrate to form a ground plane. An optical resonance gap or stand-off layer may be formed between the resonance elements and the ground plane. The optical resonance gap extends a distance between the resonance elements and the layer of conductive material approximately one-quarter wavelength of a wavelength of the at least one resonance element's resonant frequency. At least one energy transfer element may be associated with the at least one resonance element.

Minimising radiation exposure due to source assembly-related deficiencies in industrial gamma radiography exposure devices (IGREDs)

International Nuclear Information System (INIS)

Sivaraman, G.; Kannan, R.; Nandakumar, A.N.; Subrahmanya, M.J.; Murthy, B.K.S.

2000-01-01

Industrial radiographers receive higher doses as compared to radiation workers in medicine, agriculture, research, etc. Hence, it is essential that industrial gamma radiography exposure device (IGRED) be provided with efficient and effective safety systems in their design and operation to ensure smooth operation and minimise radiation exposures to the operators and public. Even though all these exposure devices have undergone stringent tests for radiographic exposure devices under international or national standards, certain deficiencies were noticed when scientists of Radiological Physics and Advisory Division (RPAD), carried out radiography equipment inspection of IGREDs. Some examples are briefly described here. The use of depleted Uranium pencil in some models led to the source pencil getting jammed due to formation of Uranium Oxide and bulging of the pencil. The solution was to replace the uranium pencil with high quality tungsten pencils or stainless steel clad pencils. In one type of pencils the source assembly would flare up after some use obstructing the smooth movement of the source assembly. The suggestion to subject the source assemblies to heat treatment solved the problem. In another type, the source pencil was getting corroded in high humid condition and affected the source movement. When the composition of the source pencil was changed it could withstand high humid condition. Another model had a hook type coupling between source assembly and drive cable. This often resulted in disengagement of the source assembly from the drive cable. Suggestions were made to change the coupling to ball and socket coupling for smooth functioning and for 'fail-safe' operation. During early days of the use of remote operated IGRED, in one particular model of the IGRED, the Iridium source wafers were directly loaded in a single encapsulation. Once the welding gave way and the source wafers got strewn. Subsequently, the source pellets/wafers were doubly encapsulated

Space Radiation Environment Prediction for VLSI microelectronics devices onboard a LEO Satellite using OMERE-Trad Software

Science.gov (United States)

Sajid, Muhammad

This tutorial/survey paper presents the assessment/determination of level of hazard/threat to emerging microelectronics devices in Low Earth Orbit (LEO) space radiation environment with perigee at 300 Km, apogee at 600Km altitude having different orbital inclinations to predict the reliability of onboard Bulk Built-In Current Sensor (BBICS) fabricated in 350nm technology node at OptMA Lab. UFMG Brazil. In this context, the various parameters for space radiation environment have been analyzed to characterize the ionizing radiation environment effects on proposed BBICS. The Space radiation environment has been modeled in the form of particles trapped in Van-Allen radiation belts(RBs), Energetic Solar Particles Events (ESPE) and Galactic Cosmic Rays (GCR) where as its potential effects on Device- Under-Test (DUT) has been predicted in terms of Total Ionizing Dose (TID), Single-Event Effects (SEE) and Displacement Damage Dose (DDD). Finally, the required mitigation techniques including necessary shielding requirements to avoid undesirable effects of radiation environment at device level has been estimated /determined with assumed standard thickness of Aluminum shielding. In order to evaluate space radiation environment and analyze energetic particles effects on BBICS, OMERE toolkit developed by TRAD was utilized.

Lead Apron Inspection Using Infrared Light: A Model Validation Study.

Science.gov (United States)

McKenney, Sarah E; Otero, Hansel J; Fricke, Stanley T

2018-02-01

To evaluate defect detection in radiation protective apparel, typically called lead aprons, using infrared (IR) thermal imaging. The use of IR lighting eliminates the need for access to x-ray-emitting equipment and radiation dose to the inspector. The performance of radiation workers was prospectively assessed using both a tactile inspection and the IR inspection with a lead apron phantom over a 2-month period. The phantom was a modified lead apron with a series of nine holes of increasing diameter ranging from 2 to 35 mm in accordance with typical rejection criteria. Using the tactile method, a radiation worker would feel for the defects in the lead apron. For the IR inspection, a 250-W IR light source was used to illuminate the lead apron phantom; an IR camera detected the transmitted radiation. The radiation workers evaluated two stills from the IR camera. From the 31 participants inspecting the lead apron phantom with the tactile method, only 2 participants (6%) correctly discovered all 9 holes and 1 participant reported a defect that was not there; 10 of the 20 participants (50%) correctly identified all 9 holes using the IR method. Using a weighted average, 5.4 defects were detected with the tactile method and 7.5 defects were detected with the IR method. IR light can penetrate an apron's protective outer fabric and illuminate defects below the current standard rejection size criteria. The IR method improves defect detectability as compared with the tactile method. Copyright © 2017 American College of Radiology. Published by Elsevier Inc. All rights reserved.

Organic materials and devices for detecting ionizing radiation

Science.gov (United States)

Doty, F Patrick [Livermore, CA; Chinn, Douglas A [Livermore, CA

2007-03-06

A .pi.-conjugated organic material for detecting ionizing radiation, and particularly for detecting low energy fission neutrons. The .pi.-conjugated materials comprise a class of organic materials whose members are intrinsic semiconducting materials. Included in this class are .pi.-conjugated polymers, polyaromatic hydrocarbon molecules, and quinolates. Because of their high resistivities (.gtoreq.10.sup.9 ohmcm), these .pi.-conjugated organic materials exhibit very low leakage currents. A device for detecting and measuring ionizing radiation can be made by applying an electric field to a layer of the .pi.-conjugated polymer material to measure electron/hole pair formation. A layer of the .pi.-conjugated polymer material can be made by conventional polymer fabrication methods and can be cast into sheets capable of covering large areas. These sheets of polymer radiation detector material can be deposited between flexible electrodes and rolled up to form a radiation detector occupying a small volume but having a large surface area. The semiconducting polymer material can be easily fabricated in layers about 10 .mu.m to 100 .mu.m thick. These thin polymer layers and their associated electrodes can be stacked to form unique multi-layer detector arrangements that occupy small volume.

Parasitic effects in superconducting quantum interference device-based radiation comb generators

Energy Technology Data Exchange (ETDEWEB)

Bosisio, R., E-mail: riccardo.bosisio@nano.cnr.it [SPIN-CNR, Via Dodecaneso 33, 16146 Genova (Italy); NEST, Instituto Nanoscienze-CNR and Scuola Normale Superiore, I-56127 Pisa (Italy); Giazotto, F., E-mail: giazotto@sns.it [NEST, Instituto Nanoscienze-CNR and Scuola Normale Superiore, I-56127 Pisa (Italy); Solinas, P., E-mail: paolo.solinas@spin.cnr.it [SPIN-CNR, Via Dodecaneso 33, 16146 Genova (Italy)

2015-12-07

We study several parasitic effects on the implementation of a Josephson radiation comb generator based on a dc superconducting quantum interference device (SQUID) driven by an external magnetic field. This system can be used as a radiation generator similarly to what is done in optics and metrology, and allows one to generate up to several hundreds of harmonics of the driving frequency. First we take into account how the assumption of a finite loop geometrical inductance and junction capacitance in each SQUID may alter the operation of the devices. Then, we estimate the effect of imperfections in the fabrication of an array of SQUIDs, which is an unavoidable source of errors in practical situations. We show that the role of the junction capacitance is, in general, negligible, whereas the geometrical inductance has a beneficial effect on the performance of the device. The errors on the areas and junction resistance asymmetries may deteriorate the performance, but their effect can be limited to a large extent by a suitable choice of fabrication parameters.

Rail for inspection/maintenance device in TOKAMAK type container of a thermonuclear reactor

International Nuclear Information System (INIS)

Takahashi, Kenji.

1996-01-01

A circular rail divided into four arcuate parts for an inspection/maintenance device which runs in a TOKAMAK type container is disposed. Each of the divided rails is supported at the center of the outer surface rotatably by extendable rail supporting shafts. Each of the divided rail is constituted such that it can be contained between limiters disposed at the outer side of the TOKAMAK container when each of the rail support shafts is contracted. With such a constitution, each of the rail support shafts and arcuate rail is contracted and rotated from the outside of the TOKAMAK type container by an actuator. In order to form a circular rail, each of the rail support shafts is extended toward the center of the TOKAMAK type container, and then each of the arcuate rails is rotated into a horizontal state. Then, the joint portions of each of the arcuate rails are connected by using remote controllable locking rods. (I.S.)

Study of radiation shielding requirements for n-MOS devices on the Exosat spacecraft. Final report

International Nuclear Information System (INIS)

1977-01-01

The device-degradation and radiation-shielding problems presented by the probable use of an n-channel microprocessor integrated circuit of the 8080 type on the Exosat spacecraft of the European Space Agency, was studied. The radiation exposure likely for this device was calculated, using various assumptions for the amount of surrounding absorber, some being intentional shielding others being normal structure elements and device encapsulation. The conclusion was that this type of device could be used if careful engineering design and quality control were used. Mission doses vary between 5000 and 800 rads for various configurations and some patterns of MOS device will tolerate these doses. The use of specially thickened module covers was not recommended, a better method being upgrading device quality and applying internal (local) shielding when necessary and possibly modular addition of external plates in specific directions only. The result of this shielding philosophy would be much greater efficiency in weight use. The further development of a rads (reduction) per gram philosophy was strongly recommended. Throughout, the strong link between mission success and the choice (and control) of the correct MOS manufacturing technology is emphasized and some guidelines on control of manufactured MOS parts (n-channel and complementary type) with respect to tolerance to radiation are given

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)

Development and application of underwater robot vehicle for close inspection of spent fuels

Energy Technology Data Exchange (ETDEWEB)

Yun, J. S.; Park, B. S.; Song, T. G.; Kim, S. H.; Cho, M. W.; Ahn, S. H.; Lee, J. Y.; Oh, S. C.; Oh, W. J.; Shin, K. W.; Woo, D. H.; Kim, H. G.; Park, J. S

1999-12-01

The research and development efforts of the underwater robotic vehicle for inspection of spent fuels are focused on the development of an robotic vehicle which inspects spent fuels in the storage pool through remotely controlled actuation. For this purpose, a self balanced vehicle actuated by propellers is designed and fabricated, which consists of a radiation resistance camera, two illuminators, a pressure transducer and a manipulator. the algorithm for autonomous navigation is developed and its performance is tested at the swimming pool. The results of the underwater vehicle shows that the vehicle can easily navigate into the arbitrary directions while maintaining its balanced position. The camera provides a clear view of working environment by using the macro and zoom functions. The camera tilt device provides a wide field of view which is enough for monitoring the operation of manipulator. Also, the manipulator can pick up the dropped objects up to 4 kgf of weight. (author)

Developments of radiation safety requirements for the management of radiation devices

International Nuclear Information System (INIS)

Lee, Hee Seock; Choi, Jin Ho; Cheong, Yuon Young

2002-03-01

The approach of the risk-informed regulatory options was studied to develop the radiation safety requirements for the managements for radiation devices. The task analysis, exposure, accident scenario development, risk analysis, and systematic approach for regulatory options was considered in full, based on the NRC report, 'NUREG/CR-6642', and the translation of its core part was conducted for ongoing research. In this methodology, the diamond tree that includes human factors, etc, additionally with normal event tree, was used. According to the analysis results of this approach, the risk analysis and the development of regulatory options were applied for the electron linear accelerators and the qualitative results were obtained. Because the field user groups were participated in this study could contribute to the basis establishment of the risk-informed regulation policy through securing consensus and inducing particle interests. It will make an important role of establishing the detail plan of ongoing research

Developments of radiation safety requirements for the management of radiation devices

Energy Technology Data Exchange (ETDEWEB)

Lee, Hee Seock [Pohang Accelerator Lab, Pohang (Korea, Republic of); Choi, Jin Ho [Gachun University of Medicine and science, Incheon (Korea, Republic of); Cheong, Yuon Young [Asan Medical Center, Seoul (Korea, Republic of)] (and others)

2002-03-15

The approach of the risk-informed regulatory options was studied to develop the radiation safety requirements for the managements for radiation devices. The task analysis, exposure, accident scenario development, risk analysis, and systematic approach for regulatory options was considered in full, based on the NRC report, 'NUREG/CR-6642', and the translation of its core part was conducted for ongoing research. In this methodology, the diamond tree that includes human factors, etc, additionally with normal event tree, was used. According to the analysis results of this approach, the risk analysis and the development of regulatory options were applied for the electron linear accelerators and the qualitative results were obtained. Because the field user groups were participated in this study could contribute to the basis establishment of the risk-informed regulation policy through securing consensus and inducing particle interests. It will make an important role of establishing the detail plan of ongoing research.

Optimum power of radiation dose in X ray television systems of flaw inspection in industry

International Nuclear Information System (INIS)

Denbnovetskii, S.V.; Troitskii, V.A.; Belyi, N.G.; Grom, V.S.; Kuz'micheva, N.V.; Leshchishin, A.V.; Mikhailov, V.N.; Shutenko, O.V.

1990-01-01

The authors present the experimental dose characteristics of a x ray television system based on x ray vidicons with the diameter of the working field of 900 mm which operate in the continuous and pulsed conditions with the longer time of cumulation of radiation images on the target of the x ray vidicon. For each type of the inspected material, its thickness, and cumulation time, the dose characteristics were used to determine the optimum power of the exposure dose ensuring the maximum signal/noise ratio and detectability of the defects at the output of the system. (author)

A new XUV optical end-station to characterize compact and flexible photonic devices using synchrotron radiation

Science.gov (United States)

Marcelli, A.; Mazuritskiy, M. I.; Dabagov, S. B.; Hampai, D.; Lerer, A. M.; Izotova, E. A.; D'Elia, A.; Turchini, S.; Zema, N.; Zuccaro, F.; de Simone, M.; Javad Rezvani, S.; Coreno, M.

2018-03-01

In this contribution we present the new experimental end-station to characterize XUV diffractive optics, such as Micro Channel Plates (MCPs) and other polycapillary optics, presently under commission at the Elettra synchrotron radiation laboratory (Trieste, Italy). To show the opportunities offered by these new optical devices for 3rd and 4th generation radiation sources, in this work we present also some patterns collected at different energies of the primary XUV radiation transmitted by MCP optical devices working in the normal incidence geometry.

The JET high temperature in-vessel inspection system

International Nuclear Information System (INIS)

Businaro, T.; Cusack, R.; Calbiati, L.; Raimondi, T.

1989-01-01

The JET In-vessel Inspection System (IVIS) has been enhanced for operation under the following nominal conditions: vacuum vessel at 350 degC; vacuum vessel evacuated (∼10 -9 mbar); radiation dose during D-T phase 10 rads. The target resolution of the pictures is 2 mm at 5 m distance and tests on radiation resistance of the IVIS system are being carried out. Since June 1988, the new system is installed in the JET machine and the first inspections of the intire vessel at 250 degC have been satisfactory done. (author). 3 refs.; 6 figs.; 1 tab

Development of a Multi-Channel Ultrasonic Testing System for Automated Ultrasonic Pipe Inspection of Nuclear Power Plant

International Nuclear Information System (INIS)

Lee, Hee Jong; Cho, Chan Hee; Cho, Hyun Joon

2009-01-01

Currently almost all in-service-inspection techniques, applied in domestic nuclear power plants, are partial to field inspection technique. These kinds of techniques are related to managing nuclear power plants by the operation of foreign-produced inspection devices. There have been so many needs for development of native in-service-inspection device because there is no native diagnosis device for nuclear power plant inspection yet in Korea. In this research, we developed several core techniques to make an automated ultrasonic pipe inspection system for nuclear power plants. A high performance multi-channel ultrasonic pulser/receiver module, an A/D converter module and a digital main CPU module were developed and the performance of the developed modules was verified. The S/N ratio, noise level and signal acquisition performance of the developed modules showed proper level as we designed in the beginning.

Heat exchanger tube inspection using ultrasonic arrays

International Nuclear Information System (INIS)

Meyer, P.A.; Carodiskey, T.J.

1986-01-01

Tubing used in industrial heat exchangers is often subject to failure caused by corrosion and cracking. Technical conferences are used as a forum in the steam generator industry to ensure that the failure mechanisms are well understood and that the quality of the heat exchanger is maintained. The quality of a heat exchanger can be thought of as its ability to operate to design specifications over its intended life. This is the motivation to inspect and evaluate these devices periodically. Inspection, however, normally requires shutdown of the heat exchanger which is costly but is much more acceptable than an unscheduled shutdown due to failure of a tube. Therefore, the degree of inspection is established by balancing the cost of inspection with the risk of a tube failure. Any method of reducing the cost of inspection will permit a higher degree of inspection and, therefore, improve heat exchanger quality. This paper reviews the design and performance of an improved method of ultrasonic inspection of heat exchanger tubing with emphasis on applications in the nuclear industry

Robots in pipe and vessel inspection: past, present, and future

International Nuclear Information System (INIS)

Mueller, T.A.; Tyndall, J.F.

1984-01-01

Over the past several decades, remotely operated scanners have been employed to inspect piping and pressure vessels. These devices in their early forms were manually controlled manipulators functioning as mere extensions of the operator. With the addition of limit sensing, speed control, and positional feedback and display, the early manipulators became primitive robots. By adding computer controls with their degree of intelligence to the devices, they achieved the status of robots. Future applications of vision, adaptive control, proximity sensing, and pattern recognition will bring these devices to a level of intelligence that will make automated robotic inspection of pipes and pressure vessels a true reality

Health physics experience with nondestructive X-radiation facilities in the US Air Force

International Nuclear Information System (INIS)

Stencel, J.R.; Piltingsrud, H.V.

1976-01-01

Radiation safety experience in the construction and use of enclosed nondestructive inspection (NDI) facilities in the US Air Force, has reaffirmed the constant need for the health physicist to continually monitor and assit in upgrading these facilities. Health physics contributions include evaluation of initial shielding requirements, proper selection of construction material, insuring that adequate safety devices are installed and adequate personnel dosimetry devices are available, surveying the facility, and assisting in the safety education program. There is a need to better define NDI warning/safety devices, using the National Bureau of Standards, (NBS) Handbook 107 as the most applicable guide

Medical Device Recalls in Radiation Oncology: Analysis of US Food and Drug Administration Data, 2002-2015.

Science.gov (United States)

Connor, Michael J; Tringale, Kathryn; Moiseenko, Vitali; Marshall, Deborah C; Moore, Kevin; Cervino, Laura; Atwood, Todd; Brown, Derek; Mundt, Arno J; Pawlicki, Todd; Recht, Abram; Hattangadi-Gluth, Jona A

2017-06-01

To analyze all recalls involving radiation oncology devices (RODs) from the US Food and Drug Administration (FDA)'s recall database, comparing these with non-radiation oncology device recalls to identify discipline-specific trends that may inform improvements in device safety. Recall data on RODs from 2002 to 2015 were sorted into 4 product categories (external beam, brachytherapy, planning systems, and simulation systems). Outcomes included determined cause of recall, recall class (severity), quantity in commerce, time until recall termination (date FDA determines recall is complete), and time since 510(k) approval. Descriptive statistics were performed with linear regression of time-series data. Results for RODs were compared with those for other devices by Pearson χ 2 test for categorical data and 2-sample Kolmogorov-Smirnov test for distributions. There were 502 ROD recalls and 9534 other class II device recalls during 2002 to 2015. Most recalls were for external beam devices (66.7%) and planning systems (22.9%), and recall events peaked in 2011. Radiation oncology devices differed significantly from other devices in all recall outcomes (P≤.04). Recall cause was commonly software related (49% vs 10% for other devices). Recall severity was more often moderate among RODs (97.6% vs 87.2%) instead of severe (0.2% vs 4.4%; Panalysis of recall data can identify areas for device improvement, such as better system design among RODs. Copyright © 2017 Elsevier Inc. All rights reserved.

Inspection program for U.S. research reactors

International Nuclear Information System (INIS)

Isaac, Patrick J.

2010-01-01

This paper presents an established program for inspection of nuclear research reactors to ensure that systems and techniques are in accordance with regulatory requirements and to provide protection for the health and safety of the public. The inspection program, implemented from the time a facility gets licensed, remains in effect through operations, shutdown, decommissioning, and until the license is terminated. The program establishes inspection methodology for operating, safeguards, and decommissioning activities. Using a performance- based approach, inspectors focus their attention on activities important to safety. Inspection procedures allow the inspectors to assess facility safety and compliance to applicable requirements. A well designed inspection program is an integral part of the mechanism to ensure that the level of performance in the strategic areas of reactor safety, radiation safety, and safeguards is acceptable and provides adequate protection of public health and safety. (author)

Overview of a benefit/risk ratio optimized for a radiation emitting device used in non-destructive testing

Energy Technology Data Exchange (ETDEWEB)

Maharaj, H.P., E-mail: H_P_Maharaj@hc-sc.gc.ca [Health Canada, Dept. of Health, Consumer and Clinical Radiaton Protection Bureau, Ottawa, Ontario (Canada)

2016-03-15

This paper aims to provide an overview of an optimized benefit/risk ratio for a radiation emitting device. The device, which is portable, hand-held, and open-beam x-ray tube based, is utilized by a wide variety of industries for purposes of determining elemental or chemical analyses of materials in-situ based on fluorescent x-rays. These analyses do not cause damage or permanent alteration of the test materials and are considered a non-destructive test (NDT). Briefly, the key characteristics, principles of use and radiation hazards associated with the Hay device are presented and discussed. In view of the potential radiation risks, a long term strategy that incorporates risk factors and guiding principles intended to mitigate the radiation risks to the end user was considered and applied. Consequently, an operator certification program was developed on the basis of an International Standards Organization (ISO) standard (ISO 20807:2004) and in collaboration with various stake holders and was implemented by a federal national NDT certification body several years ago. It comprises a written radiation safety examination and hands-on training with the x-ray device. The operator certification program was recently revised and the changes appear beneficial. There is a fivefold increase in operator certification (Levels 1 a nd 2) to date compared with earlier years. Results are favorable and promising. An operational guidance document is available to help mitigate radiation risks. Operator certification in conjunction with the use of the operational guidance document is prudent, and is recommended for end users of the x-ray device. Manufacturers and owners of the x-ray devices will also benefit from the operational guidance document. (author)

Overview of a benefit/risk ratio optimized for a radiation emitting device used in non-destructive testing

International Nuclear Information System (INIS)

Maharaj, H.P.

2016-01-01

This paper aims to provide an overview of an optimized benefit/risk ratio for a radiation emitting device. The device, which is portable, hand-held, and open-beam x-ray tube based, is utilized by a wide variety of industries for purposes of determining elemental or chemical analyses of materials in-situ based on fluorescent x-rays. These analyses do not cause damage or permanent alteration of the test materials and are considered a non-destructive test (NDT). Briefly, the key characteristics, principles of use and radiation hazards associated with the Hay device are presented and discussed. In view of the potential radiation risks, a long term strategy that incorporates risk factors and guiding principles intended to mitigate the radiation risks to the end user was considered and applied. Consequently, an operator certification program was developed on the basis of an International Standards Organization (ISO) standard (ISO 20807:2004) and in collaboration with various stake holders and was implemented by a federal national NDT certification body several years ago. It comprises a written radiation safety examination and hands-on training with the x-ray device. The operator certification program was recently revised and the changes appear beneficial. There is a fivefold increase in operator certification (Levels 1 a nd 2) to date compared with earlier years. Results are favorable and promising. An operational guidance document is available to help mitigate radiation risks. Operator certification in conjunction with the use of the operational guidance document is prudent, and is recommended for end users of the x-ray device. Manufacturers and owners of the x-ray devices will also benefit from the operational guidance document. (author)

Thermal management in MoS{sub 2} based integrated device using near-field radiation

Energy Technology Data Exchange (ETDEWEB)

Peng, Jiebin [Department of Physics, National University of Singapore, Singapore 117546 (Singapore); Zhang, Gang, E-mail: zhangg@ihpc.a-star.edu.sg [Institute of High Performance Computing, A*STAR, Singapore 138632 (Singapore); Li, Baowen [Department of Mechanical Engineering, University of Colorado, Boulder, Colorado 80309 (United States)

2015-09-28

Recently, wafer-scale growth of monolayer MoS{sub 2} films with spatial homogeneity is realized on SiO{sub 2} substrate. Together with the latest reported high mobility, MoS{sub 2} based integrated electronic devices are expected to be fabricated in the near future. Owing to the low lattice thermal conductivity in monolayer MoS{sub 2}, and the increased transistor density accompanied with the increased power density, heat dissipation will become a crucial issue for these integrated devices. In this letter, using the formalism of fluctuation electrodynamics, we explored the near-field radiative heat transfer from a monolayer MoS{sub 2} to graphene. We demonstrate that in resonance, the maximum heat transfer via near-field radiation between MoS{sub 2} and graphene can be ten times higher than the in-plane lattice thermal conduction for MoS{sub 2} sheet. Therefore, an efficient thermal management strategy for MoS{sub 2} integrated device is proposed: Graphene sheet is brought into close proximity, 10–20 nm from MoS{sub 2} device; heat energy transfer from MoS{sub 2} to graphene via near-field radiation; this amount of heat energy then be conducted to contact due to ultra-high lattice thermal conductivity of graphene. Our work sheds light for developing cooling strategy for nano devices constructing with low thermal conductivity materials.

Regulatory inspection: a powerful tool to control industrial radioactive sources

International Nuclear Information System (INIS)

Silva, F.C.A. da; Leocadio, J.C.; Ramalho, A.T.

2008-01-01

An important contribution for Brazilian development, especially for the quality control of products, is the use of radiation sources by conventional industries. There are in Brazil roughly 3,000 radioactive sources spread out among 950 industries. The main industrial practices involved are: industrial radiography, industrial irradiators, industrial accelerators, well logging petroleum and nuclear gauges. More than 1,800 Radiation Protection Officers (RPOs) were qualified to work in these practices. The present work presents a brief description of the safety control over industrial radioactive installations performed by the Brazilian Regulatory Authority, i.e. the National Commission of Nuclear Energy (CNEN). This paper also describes the national system for radiation safety inspections, the regulation infrastructure and the national inventory of industrial installations. The inspections are based on specific indicators, and their periodicity depends on the risk and type of installation. The present work discusses some relevant aspects that must be considered during the inspections, in order to make the inspections more efficient in controlling the sources. One of these aspects regards the evaluation of the storage place for the sources, a very important parameter for preventing future risky situations. (author)

Robotic inspection of nuclear waste storage facilities

International Nuclear Information System (INIS)

Fulbright, R.; Stephens, L.M.

1995-01-01

The University of South Carolina and the Westinghouse Savannah River Company have developed a prototype mobile robot designed to perform autonomous inspection of nuclear waste storage facilities. The Stored Waste Autonomous Mobile Inspector (SWAMI) navigates and inspects rows of nuclear waste storage drums, in isles as narrow as 34 inches with drums stacked three high on each side. SWAMI reads drum barcodes, captures drum images, and monitors floor-level radiation levels. The topics covered in this article reporting on SWAMI include the following: overall system design; typical mission scenario; barcode reader subsystem; video subsystem; radiation monitoring subsystem; position determination subsystem; onboard control system hardware; software development environment; GENISAS, a C++ library; MOSAS, an automatic code generating tool. 10 figs

Underwater radiation measuring device

International Nuclear Information System (INIS)

Seki, Noriyuki; Suzuki, Yasuo

1998-01-01

The present invention provides a device for measuring, under water, radiation from spent fuels (long members to be detected) of nuclear power plants and reprocessing facilities. Namely, a detecting insertion tube (insertion tube) is disposed so as to be in parallel with axial direction of the long member to be detected stored underwater. A γ-ray detector is inserted to the inside of the insertion tube. A driving mechanism is disposed for moving the γ-ray detector in axial direction inside of the insertion tube. The driving mechanism preferably has a system that it moves the γ-ray detector by winding a detection signal cable around a driving drum. The driving mechanism is formed by inserting and securing a driving tube having screws formed on the side surface and inserting it into the insertion tube. It may have a system of moving the γ-ray detector together with the driving tube while engaging the teeth of a driving transfer mechanism with the screws of the driving tube. (I.S.)

Radiation transmission type pipe wall thinning detection device and measuring instruments utilizing ionizing radiation

International Nuclear Information System (INIS)

Higashi, Yasuhiko

2009-01-01

We developed the device to detect thinning of pipe thorough heat insulation in Power Plant, etc, even while the plant is under operation. It is necessary to test many parts of many pipes for pipe wall thinning management, but it is difficult within a limited time of the routine test. This device consists of detector and radiation source, which can detect the pipe (less than 500 mm in external diameter, less than 50 mm in thickness) with 1.6%-reproducibility (in a few-minutes measurement), based on the attenuation rate. Operation is easy and effective without removing the heat insulation. We will expand this thinning detection system, and contribute the safety of the Plant. (author)

Sampling inspection device

International Nuclear Information System (INIS)

Chiba, Keiichi.

1996-01-01

A holder is inserted to a holder guide, and is stopped at a position where one end of a hook disposed to the holder is not in contact with the holder guide (a position where hooks do not work). A cap incorporated with wiping paper is pushed up into a holder by a device rod with the wiping paper situated downwardly. The hooks of the holder are engaged to the grooves of the cap to secure the cap. The holder is moved to a predetermined place to wipe off the deposited materials on the surface of a vessel which contains radioactive wastes. Then, the holder is inserted to the holder guide, and is stopped at a position where the one end of the holder is raised. The securement of the gap is released, the cap is forced into a recovering cover by a discharging rod. The hooks of the recovering cover are caught by the grooves of the cap to secure the cap. Then, the cap is transported to a radioactivity measuring chamber. (I.N.)

Improvements to a neutral radiation detection and position sensitive process and devices

International Nuclear Information System (INIS)

Charpak, Georges; Nguyen, N.H.; Policarpo, Armando.

1977-01-01

This invention aims to provide a neutral radiation position sensitive process and device providing a spatial radiation satisfactory for most medical applications and an energy radiation that cannot be reached by gas detectors based on proportional counters or by scintillation counters. Only solid state detectors can compete with respect to energy resolution. The detector described enables large areas to be covered which cannot be reached at accessible costs by solid state detectors. With this aim in view, the invention suggests an incident neutral radiation and position sensitive process, particularly soft gamma and X radiations, whereby photoelectrons are made to form by incident radiation action on gas atoms contained in an enclosure. By means of an electric field, the electrons are diverted towards a space undergoing an electric field high enough in value to create photons by exciting gas atoms and returning them to the de-excited state. The photons are collected, through a transparent window, on a layer of a material for converting such photons into scintillations in the near or visible UV spectrum and the barycentre of the scintillations is positioned on the layer, for instance by photomultipliers or ionization detectors. According to another aspect of the invention, it suggests a detection and position sensitive device comprising (generally downstream of a collimator with a grid of inlet holes) a leak tight containment fitted with an inlet window transparent to incident radiations, filled with a gas producing electrons by interaction with the incident radiation, and fitted with electrodes for generating an electric field to divert the electrons to a space for creating secondary photons [fr

Emergency response activities and collecting damaged radiation devices from a war affected area in Croatia

International Nuclear Information System (INIS)

Subasic, Damir; Schaller, Antum

1997-01-01

A number of various devices containing ionizing radiation sources were in use in the area affected by the recent war in Croatia. In destruction caused by the war operations, a number of these devices were damaged, destroyed or even missed/lost. The actions undertaken to (re)collect these radiation sources, experience gained and lessons learned are reviewed. The importance of a well-organized national regulatory system is highlighted as a precondition for the efficient identification and safe collection of radiation sources which were under ruins. Experience from this event could be well applicable to similar situations caused by disasters and particularly for regulatory authorities who design emergency preparedness plans. (author)

Application of Nd/sup 3+/-doped silica fibers to radiation sensing devices

International Nuclear Information System (INIS)

Imamura, K.; Suzuki, T.; Gozen, T.; Tanaka, H.; Okamoto, S.

1987-01-01

Applications of rare-earth-ion-doped optical fibers to radiation sensing devices have been studied. It was revealed that rare-earth-ion-doped optical fibers are highly sensitive to radioactive rays such as gamma ray and thermal neutron flux and that they have little dependence on ambient temperature and optical power. An experimental distributed radiation sensing system incorporating Nd/sup 3+/-doped optical fibers, radiation resistant optical fibers and an OTDR was made and tested. The results proved that the distributed sensing system is practically adaptable to the measurement of the radioactive rays

Radiation shielding device

International Nuclear Information System (INIS)

Nakagawa, Takahiro; Yamagami, Makoto.

1996-01-01

A fixed shielding member made of a radiation shielding material is constituted in perpendicular to an opening formed on radiation shielding walls. The fixed shielding member has one side opened and has other side, the upper portion and the lower portion disposed in close contact with the radiation shielding walls. Movable shielding members made of a radiation shielding material are each disposed openably on both side of the fixed shielding member. The movable shielding member has a shaft as a fulcrum on one side thereof for connecting it to the radiation shielding walls. The other side has a handle attached for opening/closing the movable shielding member. Upon access of an operator, when each one of the movable shielding members is opened/closed on every time, leakage of linear or scattered radiation can be prevented. Even when both of the movable shielding members are opened simultaneously, the fixed shielding member and the movable shielding members form labyrinth to prevent leakage of linear radioactivity. (I.N.)

Realistic modeling of radiation transmission inspection systems

International Nuclear Information System (INIS)

Sale, K.E.

1993-01-01

We have applied Monte Carlo particle transport methods to assess a proposed neutron transmission inspection system for checked luggage. The geometry of the system and the time, energy and angle dependence of the source have been modeled in detail. A pulsed deuteron beam incident on a thick Be target generates a neutron pulse with a very broad energy spectrum which is detected after passage through the luggage item by a plastic scintillator detector operating in current mode (as opposed to pulse counting mode). The neutron transmission as a function of time information is used to infer the densities of hydrogen, carbon, oxygen and nitrogen in the volume sampled. The measured elemental densities can be compared to signatures for explosives or other contraband. By using such computational modeling it is possible to optimize many aspects of the design of an inspection system without costly and time consuming prototyping experiments or to determine that a proposed scheme will not work. The methods applied here can be used to evaluate neutron or photon schemes based on transmission, scattering or reaction techniques

Application of corrosion screening tools for riser inspection

International Nuclear Information System (INIS)

Zamir Mohamed Daud; Vijayan, S.

2003-01-01

As offshore facilities approach the end of their design life, owners would like to assess the condition and integrity of plant and equipment. Detailed inspection, including non-destructive testing (NDT), are implemented and results are utilised for predictive maintenance and estimating useful remaining life. Except for risk based inspection, the extent of surface coverage required would be more compared to inspection of pre-determined spots. Risers, for example, usually have several layers of coating that prevent use of conventional techniques for inspection of corrosion. Complete coverage requires access (including removal coatings and insulation). Inspection utilising the conventional NDT tools can be very slow and expensive. However, recent advances have forwarded the use of specialised NDT techniques that were developed for inspection of corrosion under insulation (CUI). This paper details two screening inspection tools, LIXI Profiler and RTD-INCOTEST that have been applied to inspection of risers. LIXI Profiler is based on attenuation of penetrating radiation by materials, and RTD-INCOTEST is based on decay of pulsed eddy current in materials. (Author)

Radiation effects and hardness of semiconductor electronic devices for nuclear industry

International Nuclear Information System (INIS)

Payat, R.; Friant, A.

1988-01-01

After a brief review of industrial and nuclear specificity and radiation effects in electronics components (semiconductors) the need for a specific test methodology of semiconductor devices is emphasized. Some studies appropriate for nuclear industry at D. LETI/DEIN/CEN-SACLAY are related [fr

Ultraviolet spectral distribution and erythema-weighted irradiance from indoor tanning devices compared with solar radiation exposures.

Science.gov (United States)

Sola, Yolanda; Baeza, David; Gómez, Miguel; Lorente, Jerónimo

2016-08-01

Concern regarding the impact of indoor tanning devices on human health has led to different regulations and recommendations, which set limits on erythema-weighted irradiance. Here, we analyze spectral emissions from 52 tanning devices in Spanish facilities and compare them with surface solar irradiance for different solar zenith angles. Whereas most of the devices emitted less UV-B radiation than the midday summer sun, the unweighted UV-A irradiance was 2-6 times higher than solar radiation. Moreover, the spectral distributions of indoor devices were completely different from that of solar radiation, differing in one order of magnitude at some UV-A wavelengths, depending on the lamp characteristics. In 21% of the devices tested, the erythema-weighted irradiance exceeded 0.3Wm(-2): the limit fixed by the European standard and the Spanish regulation. Moreover, 29% of the devices fall within the UV type 4 classification, for which medical advice is required. The high variability in erythema-weighted irradiance results in a wide range of exposure times to reach 1 standard erythemal dose (SED: 100Jm(-2)), with 62% of devices requiring exposures of UV-A dose during this time period would be from 1.4 to 10.3 times more than the solar UV-A dose. Copyright © 2016 Elsevier B.V. All rights reserved.

Utilization of photoconductive gain in a-Si:H devices for radiation detection

International Nuclear Information System (INIS)

Lee, H.K.; Drewery, J.S.; Hong, W.S.; Jing, T.; Kaplan, S.N.; Perez-Mendez, V.

1995-05-01

The photoconductive gain mechanism in a-Si:H was investigated in connection with applications to radiation detection. Various device types such as p-i-n, n-i-n and n-i-p-i-n structures were fabricated and tested. Photoconductive gain was measured in two time scales: one for short pulses of visible light ( 2 . Various gain results are discussed in terms of the device structure, applied bias and dark current

Application of complex programmable logic devices in memory radiation effects test system

International Nuclear Information System (INIS)

Li Yonghong; He Chaohui; Yang Hailiang; He Baoping

2005-01-01

The application of the complex programmable logic device (CPLD) in electronics is emphatically discussed. The method of using software MAX + plus II and CPLD are introduced. A new test system for memory radiation effects is established by using CPLD devices-EPM7128C84-15. The old test system's function are realized and, moreover, a number of small scale integrated circuits are reduced and the test system's reliability is improved. (authors)

Inspection device for fuel rod restraint by support lattice of fuel assembly

International Nuclear Information System (INIS)

Hasegawa, Isao; Senga, Masatoshi; Kada, Mitoshi.

1991-01-01

An inspection operation section for disposing fuel assembly vertically at predetermined positions, a control section wired therewith, a moving operation section movable in the direction of X, Y and Z axes by a driving signal sent from the control section are disposed to an inspection section main body. A downward bore scope and a upward bore scope, each of such a size as can be inserted to the gaps between the fuel rods, are disposed while opposing to each other for observing the inside of each of cells from above and below in support lattices of fuel assemblies. High performance television cameras are disposed to each of bore scopes to supply images to monitoring televisions in the control section. Thus, a displacing operation section of the inspection operation section is automatically controlled three-dimensionally, the downward bore scope and the upward bore scope are integrally intruded to the inside of the gaps between the predetermined fuel rods from a required height and stopped at a predetermined position, mounted automatically to a required cell of the support lattice to efficiently observe and inspect the fuel rod restraint. (N.H.)

Enabling inspection solutions for future mask technologies through the development of massively parallel E-Beam inspection

Science.gov (United States)

Malloy, Matt; Thiel, Brad; Bunday, Benjamin D.; Wurm, Stefan; Jindal, Vibhu; Mukhtar, Maseeh; Quoi, Kathy; Kemen, Thomas; Zeidler, Dirk; Eberle, Anna Lena; Garbowski, Tomasz; Dellemann, Gregor; Peters, Jan Hendrik

2015-09-01

The new device architectures and materials being introduced for sub-10nm manufacturing, combined with the complexity of multiple patterning and the need for improved hotspot detection strategies, have pushed current wafer inspection technologies to their limits. In parallel, gaps in mask inspection capability are growing as new generations of mask technologies are developed to support these sub-10nm wafer manufacturing requirements. In particular, the challenges associated with nanoimprint and extreme ultraviolet (EUV) mask inspection require new strategies that enable fast inspection at high sensitivity. The tradeoffs between sensitivity and throughput for optical and e-beam inspection are well understood. Optical inspection offers the highest throughput and is the current workhorse of the industry for both wafer and mask inspection. E-beam inspection offers the highest sensitivity but has historically lacked the throughput required for widespread adoption in the manufacturing environment. It is unlikely that continued incremental improvements to either technology will meet tomorrow's requirements, and therefore a new inspection technology approach is required; one that combines the high-throughput performance of optical with the high-sensitivity capabilities of e-beam inspection. To support the industry in meeting these challenges SUNY Poly SEMATECH has evaluated disruptive technologies that can meet the requirements for high volume manufacturing (HVM), for both the wafer fab [1] and the mask shop. Highspeed massively parallel e-beam defect inspection has been identified as the leading candidate for addressing the key gaps limiting today's patterned defect inspection techniques. As of late 2014 SUNY Poly SEMATECH completed a review, system analysis, and proof of concept evaluation of multiple e-beam technologies for defect inspection. A champion approach has been identified based on a multibeam technology from Carl Zeiss. This paper includes a discussion on the

ACEC: remote inspection, remote intervention, autonomous vehicle

International Nuclear Information System (INIS)

Anon.

1986-01-01

Early in 1979, the accident at the TMI-2 nuclear power station focused attention on the lack of inspection and intervention means in containments where high radiation levels do not allow the entrance of humans. Recent years have seen a trend towards significant developments in the application of robotic technology to maintenance and inspection in nuclear facilities. This paper presents the general development concept and the technical specifications of a mobile robot [fr

Control rod drive hydraulic device

International Nuclear Information System (INIS)

Takekawa, Toru.

1994-01-01

The device of the present invention can reliably prevent a possible erroneous withdrawal of control rod driving mechanism when the pressure of a coolant line is increased by isolation operation of hydraulic control units upon periodical inspection for a BWR type reactor. That is, a coolant line is connected to the downstream of a hydraulic supply device. The coolant line is connected to a hydraulic control unit. A coolant hydraulic detection device and a pressure setting device are disposed to the coolant line. A closing signal line and a returning signal line are disposed, which connect the hydraulic supply device and a flow rate control valve for the hydraulic setting device. In the device of the present invention, even if pressure of supplied coolants is elevated due to isolation of hydraulic control units, the elevation of the hydraulic pressure can be prevented. Accordingly, reliability upon periodical reactor inspection can be improved. Further, the facility is simplified and the installation to an existent facility is easy. (I.S.)

Possibilities of radiation sterilization for re-usage of medical devices in the medical management

International Nuclear Information System (INIS)

Tabei, Masae; Kudo, Hisaaki; Katsumura, Yosuke

2004-01-01

The rule for re-usage of medical single-use devices was established in US in 2000 based on the concept of Managed Care (total management of medicare on cost, quality and patients' satisfaction) and 20-30% of those devices are re-used at present. The re-usage is conducted in not only US but also Canada, Denmark, UK, India, China etc. Standing on the viewpoint, this paper described and discussed the possibility of re-usage of the single-use devices now prohibited in Japan, possible re-sterilization, possible re-usage of hollow fiber-type hemodialyzer following γ-ray sterilization with consideration for D-values against bacteria and viruses, cost estimation of electron beam sterilization for re-usage, and radiation sterilization of waste water and plastic materials. Radiation sterilization for re-usage of medical devices was concluded possible if their materials and records for their usage processes are proper, and should be conducted in a large scale after sufficient examinations by industries/government/academia. (N.I.)

Holographic inspection of nuclear plant

International Nuclear Information System (INIS)

Gordon, A.L.; Armour, I.A.; Glanville, R.; Malcolm, G.J.; Wright, D.G.

1988-01-01

The high resolution, enormous depth of field and high tolerance to radiation of holography mean that it has great potential as an inspection tool in the nuclear industry. In addition, the ability of double-pulse holography to yield detailed information on vibration over the whole field of both large and small structures provides measurements that often cannot be obtained in any other way. This paper reviews the development of equipment for the holographic inspection of nuclear fuel elements; a portable holocamera for use inside reactors; and the application of holographic techniques for vibration measurements in a nuclear power station. (author)

Remote inspection with multi-copters, radiological sensors and SLAM techniques

Science.gov (United States)

Carvalho, Henrique; Vale, Alberto; Marques, Rúben; Ventura, Rodrigo; Brouwer, Yoeri; Gonçalves, Bruno

2018-01-01

Activated material can be found in different scenarios, such as in nuclear reactor facilities or medical facilities (e.g. in positron emission tomography commonly known as PET scanning). In addition, there are unexpected scenarios resulting from possible accidents, or where dangerous material is hidden for terrorism attacks using nuclear weapons. Thus, a technological solution is important to cope with fast and reliable remote inspection. The multi-copter is a common type of Unmanned Aerial Vehicle (UAV) that provides the ability to perform a first radiological inspection in the described scenarios. The paper proposes a solution with a multi-copter equipped with on-board sensors to perform a 3D reconstruction and a radiological mapping of the scenario. A depth camera and a Geiger-Müler counter are the used sensors. The inspection is performed in two steps: i) a 3D reconstruction of the environment and ii) radiation activity inference to localise and quantify sources of radiation. Experimental results were achieved with real 3D data and simulated radiation activity. Experimental tests with real sources of radiation are planned in the next iteration of the work.

Remote inspection with multi-copters, radiological sensors and SLAM techniques

Directory of Open Access Journals (Sweden)

Carvalho Henrique

2018-01-01

Full Text Available Activated material can be found in different scenarios, such as in nuclear reactor facilities or medical facilities (e.g. in positron emission tomography commonly known as PET scanning. In addition, there are unexpected scenarios resulting from possible accidents, or where dangerous material is hidden for terrorism attacks using nuclear weapons. Thus, a technological solution is important to cope with fast and reliable remote inspection. The multi-copter is a common type of Unmanned Aerial Vehicle (UAV that provides the ability to perform a first radiological inspection in the described scenarios. The paper proposes a solution with a multi-copter equipped with on-board sensors to perform a 3D reconstruction and a radiological mapping of the scenario. A depth camera and a Geiger-Müler counter are the used sensors. The inspection is performed in two steps: i a 3D reconstruction of the environment and ii radiation activity inference to localise and quantify sources of radiation. Experimental results were achieved with real 3D data and simulated radiation activity. Experimental tests with real sources of radiation are planned in the next iteration of the work.

Response of Caenorhabditis elegans to wireless devices radiation exposure.

Science.gov (United States)

Fasseas, Michael K; Fragopoulou, Adamantia F; Manta, Areti K; Skouroliakou, Aikaterini; Vekrellis, Konstantinos; Margaritis, Lukas H; Syntichaki, Popi

2015-03-01

To examine the impact of electromagnetic radiation, produced by GSM (Global System for Mobile communications) mobile phones, Wi-Fi (Wireless-Fidelity) routers and wireless DECT (Digital Enhanced Cordless Telecommunications) phones, on the nematode Caenorhabditis elegans. We exposed synchronized populations, of different developmental stages, to these wireless devices at E-field levels below ICNIRP's (International Commission on Non-Ionizing Radiation Protection) guidelines for various lengths of time. WT (wild-type) and aging- or stress-sensitive mutant worms were examined for changes in growth, fertility, lifespan, chemotaxis, short-term memory, increased ROS (Reactive Oxygen Species) production and apoptosis by using fluorescent marker genes or qRT-PCR (quantitative Reverse Transcription-Polymerase Chain Reaction). No statistically significant differences were found between the exposed and the sham/control animals in any of the experiments concerning lifespan, fertility, growth, memory, ROS, apoptosis or gene expression. The worm appears to be robust to this form of (pulsed) radiation, at least under the exposure conditions used.

Heat resistant/radiation resistant cable and incore structure test device for FBR type reactor

International Nuclear Information System (INIS)

Tanimoto, Hajime; Shiono, Takeo; Sato, Yoshimi; Ito, Kazumi; Sudo, Shigeaki; Saito, Shin-ichi; Mitsui, Hisayasu.

1995-01-01

A heat resistant/radiation resistant coaxial cable of the present invention comprises an insulation layer, an outer conductor and a protection cover in this order on an inner conductor, in which the insulation layer comprises thermoplastic polyimide. In the same manner, a heat resistant/radiation resistant power cable has an insulation layer comprising thermoplastic polyimide on a conductor, and is provided with a protection cover comprising braid of alamide fibers at the outer circumference of the insulation layer. An incore structure test device for an FBR type reactor comprises the heat resistant/radiation resistant coaxial cable and/or the power cable. The thermoplastic polyimide can be extrusion molded, and has excellent radiation resistant by the extrusion, as well as has high dielectric withstand voltage, good flexibility and electric characteristics at high temperature. The incore structure test device for the FBR type reactor of the present invention comprising such a cable has excellent reliability and durability. (T.M.)

The use of ionising radiation screening devices in airports

International Nuclear Information System (INIS)

Lazo, T.

2010-01-01

Although the NEA generally focuses on radiological protection at nuclear power plants and related facilities, it also addresses other areas of radiological protection of interest to member countries. A particular subject of recent importance concerns the use of ionising radiation screening devices as part of airport security efforts. Modern body scanners can produce human images that can be used to detect weapons that may be hidden beneath a person's clothing. Heightened concerns over terrorist threats to airline flights have prompted many countries to consider the use, or expanded use of body scanners. The use of such devices raises a wide series of questions, some of which concern the radiological protection of those who might be scanned. As such, the Inter-Agency Committee on Radiation Safety (IACRS), an expert body in which the NEA works together with several other international organisations addressing radiological protection issues, recently developed a joint information paper laying out the key radiological protection and other issues that should be or have been considered when making decisions as to whether ionising radiation body scanners should be deployed in airports. This article provides an overview of the information paper. In assessing the possible use of X-ray body scanners, there are two significant radiological protection issues that may be of relevance with regard to the government decision whether their use is justified. First, although the individual exposures are very low, the exposure experienced by the scanned population as a whole will depend on whether all passengers are systematically scanned, or alternatively whether passengers are selected for scanning randomly or on the basis of specific criteria. The manner in which passengers would be selected would need to be known in order to appropriately assess the full radiological protection impact of scanner use. Second, the use of X-ray body scanners on sensitive groups, such as pregnant

Emergency response activities and collecting damaged radiation devices from a war affected area in Croatia

Energy Technology Data Exchange (ETDEWEB)

Subasic, Damir; Schaller, Antum [APO-Hazardous Waste Management Agency, Zagreb (Croatia)

1997-12-31

A number of various devices containing ionizing radiation sources were in use in the area affected by the recent war in Croatia. In destruction caused by the war operations, a number of these devices were damaged, destroyed or even missed/lost. The actions undertaken to (re)collect these radiation sources, experience gained and lessons learned are reviewed. The importance of a well-organized national regulatory system is highlighted as a precondition for the efficient identification and safe collection of radiation sources which were under ruins. Experience from this event could be well applicable to similar situations caused by disasters and particularly for regulatory authorities who design emergency preparedness plans. (author) 4 refs., 1 tab.

Determination of the permeability of α-, β- and γ-radiation in textile fabrics by Gamma-Scout device

International Nuclear Information System (INIS)

Gintibidze, N.; Mardaleishvili, Z.

2009-01-01

The goal of the present was the measurement of radiation permeability in textile fabrics by Gamma-Scout device and the comparison of the obtained results with the radiation background of the ambient air. The authors of this article have produced new fiber Fibron-3, which, according to theoretical calculations, reduces permeability of solar radiation. With this in mind, an experiment was performed. Three samples of the knitted cloth from Fibron-3 were taken, and the permeability of solar radiation in them was determined. The measurements were performed on Gamma-Scout device. The comparative analysis of the permeability of solar radiation in fabrics of different fibrous structure was performed. It was inferred that the degree of radiation permeability in fabrics depended on the thread thickness and the fiber structure. (author)

Nondestructive test for assembly relationship of initiating explosive device

International Nuclear Information System (INIS)

Wang Xiangang; Zhang Chaozong; Guo Zhiping

2009-01-01

A 3D computed tomography (CT) method to inspect assembly relationship of initiating explosive device and to nondestructively evaluate assembly relationship by building geometric model from CT images was described. The experiment result proves that this method accurately inspects assembly relationship of initiating explosive device. (authors)

On the development of the METAR family of inspection tools

Energy Technology Data Exchange (ETDEWEB)

Lavoie, E. [Inst. de recherche d' Hydro-Quebec, Varennes, Quebec (Canada)]. E-mail: lavoie.eric@ireq.ca; Rousseau, G. [Hydro-Quebec, Central Nucleaire Gentilly-2, Gentilly, Quebec (Canada); Reynaud, L. [Inst. de recherche d' Hydro-Quebec, Varennes, Quebec (Canada)

2003-07-01

Since 1998, Hydro Quebec Research Centre (IREQ), in collaboration with Gentilly-2, has been working on the development of inspection devices for the feeder tubes of CANDU power plants. The first tool to come out of this work was the Metar bracelet, now used throughout the CANDU utilities, consisting of 14 ultrasonic probes held in place in a rigid bracelet to measure the thickness of the pipes and moved around manually along the pipe. Following the success of the Metar, a motorized version, i.e. the Crawler, has been developed to inspect beyond the operator arm's reach to access hard to reach place or further down the pipes in the reactor. This new system has been tested at 3 different stations and will be commercially available soon. Finally, the same technology was used to develop a motorized 2-axis crack detection device to answer new concerns about the feeder. Other configurations, depending on the demands from the industry, could also be developed for specific inspection needs, for example; inspection of the graylock welds, 360{sup o} inspection of feeders, or multitasking inspection on a single frame, etc. Most of the designs shown in this article have been or will be patented and are, or will be, licensed to a partner company to make them commercially available to the industry. This paper gives a brief history of the project and a description of the technologies developed in the last 5 years concerning feeder inspection. (author)

Synchrotron radiation A general overview and a review of storage rings, research facilities, and insertion devices

International Nuclear Information System (INIS)

Winick, H.

1989-01-01

Synchrotron radiation, the electromagnetic radiation given off by electrons in circular motion, is revolutionizing many branches of science and technology by offering beams of vacuum ultraviolet light and x rays of immense flux and brightness. In the past decade there has been an explosion of interest in these applications leading activity to construct new research facilities based on advanced storage rings and insertion device sources. Applications include basic and applied research in biology, chemistry, medicine, and physics plus many areas of technology. In this article we present a general overview of the field of synchrotron radiation research, its history, the present status and future prospects of storage rings and research facilities, and the development of wiggler and undulator insertion devices as sources of synchrotron radiation

Linear devices in combined high-level radiation environments

International Nuclear Information System (INIS)

van Vonno, N.W.

1987-01-01

The design of precision analog integrated circuits for use in combined high-level radiation environments has traditionally been on a full-custom basis. The use of semicustom design methods has become prevalent in digital devices, with standard cell libraries and gate arrays readily available from multiple vendors. This paper addresses the application of semicustom design techniques to analog parts. In all cases the emphasis is on bipolar technology, since this provides an optimal combination of precision and radiation hardness. A mixed mode analog/digital (A/D) cell family for implementing semicustom designs is described, together with the fabrication process used. Specific processing and design methods are used to provide circuit hardness against neutron, total gamma dose, and transient gamma environments. Semicustom mixed analog/digital design is seen as an appropriate methodology for implementation of medium-performance mixed mode functions for radiation-hardened applications. This leads to trade-offs in process complexity and performance. Full custom design remains necessary for demanding applications such as high-speed A/D conversion and associated sample/hold functions. An A/D cell family optimized for hardness is described, together with the bipolar process used to implement it

Radiation leaking protection device

International Nuclear Information System (INIS)

Sunami, Yoshio; Mitsumori, Kojiro

1980-01-01

Purpose: To prevent radioactivity from leaking outside of a reactor container by way of pipeways passing therethrough, by supplying pressurized fluid between each of a plurality of valves for separating the pipeways. Constitution: Pressurized fluid is supplied between each of a plurality of valves for separating pipeways. For instance, water in a purified water tank is pressurized by a pressure pump and the pressure of the pressurized water is controlled by a differential pressure detector, a pressure controller and a pressure control valve. In the case if a main steam pipe is ruptured outside of the reactor container or to be repaired, the separation valves are wholly closed and then the pressurizing device is actuated to supply pressurized water containing no radioactivity from the purified water tank to the position between the valves. The pressure in the pressurized water is controlled such that it is always higher by a predetermined level than the pressure in the reactor. This prevents the radioacitivity in the reactor core from leaking outside of the container passing through the valves, whereby radiation exposure in the working can be reduced and the circumferential contamination upon accident of pipeway rupture can be decreased. (Kawakami, Y.)

Radiation Practices. Annual report 2004

International Nuclear Information System (INIS)

Rantanen, E.

2005-06-01

A total of 1791 safety licences for the use of radiation were current at the end of 2004. There were 1924 responsible parties engaged in licence-exempt dental X-ray practices, made notifiable to STUK. Regulatory control of the use of radiation was carried out through regular inspections performed at places of use, test packages sent by post to dental X-ray facilities and maintenance of a Dose Register. Radiation safety guides were also published and research was conducted to support the regulatory control. In 2004, STUK conducted 438 inspections of licensed practices and 38 inspections of notifiable licence-exempt dental X-ray practices. Restrictions were imposed on the use of five appliances. Repairs were ordered in 150 inspections and recommended in 85 inspections. No remarks were given in 229 inspections. A total of 11 082 workers engaged in radiation work were subject to individual monitoring in 2004. 135 000 dose entries were made in the register maintained by STUK. In no case did the individual dose of any worker exceed the dose limits stipulated in the Radiation Decree. Regulatory control of natural radiation concentrated on radon at workplaces and exposure of aircrews to cosmic radiation. At the end of 2004, 55 workplaces including a total of 74 work areas were subject to radon monitoring. A total of 2540 pilots and cabin crew members were monitored for exposure to cosmic radiation. Metrological activities continued with calibration and development work as in previous years. Regulatory control of the use of non-ionizing radiation focused particularly on mobile phones and sunbeds. Radiation safety assessments were also made for public broadcasting equipment, radars, 'artificial sun' aboard a cruise liner, UVC bactericide lamps in a bakery and show laser lights. A recommendation on radiation safety for sunbeds was prepared in association with other Nordic countries. Most research and development work was done in jointly financed research projects and

Inspection apparatus for a vessel made of magnetic metal

International Nuclear Information System (INIS)

Clark, J.P.; Foster, A.C.; Smith, T.D.

1976-01-01

Previous systems intended for in-situ inspection of the pressure vessels of nuclear reactors are of uneasy use on encumbered surfaces. Said invention relates to a remote-control device for inspecting vessel walls. It comprises a conveyor able to be propelled, possibly around obstacles, towards any place inside the vessel; said vehicle is provided with magnetic wheels driven by an electric motor and separately controlled. The conveyor is accurately located on the vessel by using an acoustic device involving a triangular method, and consisting in an acoustic signal emitter mounted on the conveyor and at least three receiving transducers mounted on the vessel wall [fr

2013 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act Title II Disposal Sites

International Nuclear Information System (INIS)

2013-01-01

This report, in fulfillment of a license requirement, presents the results of long-term surveillance and maintenance activities conducted by the U.S. Department of Energy (DOE) Office of Legacy Management in 2013 at six uranium mill tailings disposal sites reclaimed under Title II of the Uranium Mill Tailings Radiation Control Act (UMTRCA) of 1978. These activities verified that the UMTRCA Title II disposal sites remain in compliance with license requirements. DOE manages six UMTRCA Title II disposal sites under a general license granted by the U.S. Nuclear Regulatory Commission (NRC) established at Title 10 Code of Federal Regulations Part 40.28. Reclamation and site transition activities continue at other sites, and DOE ultimately expects to manage approximately 27 Title II disposal sites. Long-term surveillance and maintenance activities and services for these disposal sites include inspecting and maintaining the sites; monitoring environmental media and institutional controls; conducting any necessary corrective action; and performing administrative, records, stakeholder services, and other regulatory functions. Annual site inspections and monitoring are conducted in accordance with site-specific long-term surveillance plans (LTSPs) and procedures established by DOE to comply with license requirements. Each site inspection is performed to verify the integrity of visible features at the site; to identify changes or new conditions that may affect the long-term performance of the site; and to determine the need, if any, for maintenance, follow-up inspections, or corrective action. LTSPs and site compliance reports are available online at http://www.lm.doe.gov

2013 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act Title II Disposal Sites

Energy Technology Data Exchange (ETDEWEB)

None

2013-11-01

This report, in fulfillment of a license requirement, presents the results of long-term surveillance and maintenance activities conducted by the U.S. Department of Energy (DOE) Office of Legacy Management in 2013 at six uranium mill tailings disposal sites reclaimed under Title II of the Uranium Mill Tailings Radiation Control Act (UMTRCA) of 1978. These activities verified that the UMTRCA Title II disposal sites remain in compliance with license requirements. DOE manages six UMTRCA Title II disposal sites under a general license granted by the U.S. Nuclear Regulatory Commission (NRC) established at Title 10 Code of Federal Regulations Part 40.28. Reclamation and site transition activities continue at other sites, and DOE ultimately expects to manage approximately 27 Title II disposal sites. Long-term surveillance and maintenance activities and services for these disposal sites include inspecting and maintaining the sites; monitoring environmental media and institutional controls; conducting any necessary corrective action; and performing administrative, records, stakeholder services, and other regulatory functions. Annual site inspections and monitoring are conducted in accordance with site-specific long-term surveillance plans (LTSPs) and procedures established by DOE to comply with license requirements. Each site inspection is performed to verify the integrity of visible features at the site; to identify changes or new conditions that may affect the long-term performance of the site; and to determine the need, if any, for maintenance, follow-up inspections, or corrective action. LTSPs and site compliance reports are available online at http://www.lm.doe.gov

Verification tests for remote controlled inspection system in nuclear power plants

International Nuclear Information System (INIS)

Kohno, Tadaaki

1986-01-01

Following the increase of nuclear power plants, the total radiation exposure dose accompanying inspection and maintenance works tended to increase. Japan Power Engineering and Inspection Corp. carried out the verification test of a practical power reactor automatic inspection system from November, 1981, to March, 1986, and in this report, the state of having carried out this verification test is described. The objects of the verification test were the equipment which is urgently required for reducing radiation exposure dose, the possibility of realization of which is high, and which is important for ensuring the safety and reliability of plants, that is, an automatic ultrasonic flaw detector for the welded parts of bend pipes, an automatic disassembling and inspection system for control rod driving mechanism, a fuel automatic inspection system, and automatic decontaminating equipments for steam generator water chambers, primary system crud and radioactive gas in coolant. The results of the verification test of these equipments were judged as satisfactory, therefore, the application to actual plants is possible. (Kako, I.)

Terahertz Radome Inspection

Directory of Open Access Journals (Sweden)

Fabian Friederich

2018-01-01

Full Text Available Radomes protecting sensitive radar, navigational, and communications equipment of, e.g., aircraft, are strongly exposed to the environment and have to withstand harsh weather conditions and potential impacts. Besides their significance to the structural integrity of the radomes, it is often crucial to optimize the composite structures for best possible radio performance. Hence, there exists a significant interest in non-destructive testing techniques, which can be used for defect inspection of radomes in field use as well as for quality inspection during the manufacturing process. Contactless millimeter-wave and terahertz imaging techniques provide millimeter resolution and have the potential to address both application scenarios. We report on our development of a three-dimensional (3D terahertz imaging system for radome inspection during industrial manufacturing processes. The system was designed for operation within a machining center for radome manufacturing. It simultaneously gathers terahertz depth information in adjacent frequency ranges, from 70 to 110 GHz and from 110 to 170 GHz by combining two frequency modulated continuous-wave terahertz sensing units into a single measurement device. Results from spiraliform image acquisition of a radome test sample demonstrate the successful integration of the measurement system.

Malfunction of cardiac devices after radiotherapy without direct exposure to ionizing radiation: mechanisms and experimental data.

Science.gov (United States)

Zecchin, Massimo; Morea, Gaetano; Severgnini, Mara; Sergi, Elisabetta; Baratto Roldan, Anna; Bianco, Elisabetta; Magnani, Silvia; De Luca, Antonio; Zorzin Fantasia, Anna; Salvatore, Luca; Milan, Vittorino; Giannini, Gianrossano; Sinagra, Gianfranco

2016-02-01

Malfunctions of cardiac implantable electronical devices (CIED) have been described after high-energy radiation therapy even in the absence of direct exposure to ionizing radiation, due to diffusion of neutrons (n) causing soft errors in inner circuits. The purpose of the study was to analyse the effect of scattered radiation on different types and models of CIED and the possible sources of malfunctions. Fifty-nine explanted CIED were placed on an anthropomorphous phantom of tissue-equivalent material, and a high-energy photon (15 MV) radiotherapy course (total dose = 70 Gy) for prostate treatment was performed. All devices were interrogated before and after radiation. Radiation dose, the electromagnetic field, and neutron fluence at the CIED site were measured. Thirty-four pacemakers (PM) and 25 implantable cardioverter-defibrillators (ICD) were analysed. No malfunctions were detected before radiation. After radiation a software malfunction was evident in 13 (52%) ICD and 6 (18%) PM; no significant electromagnetic field or photon radiations were detected in the thoracic region. Neutron capture was demonstrated by the presence of the (198)Au((197)Au + n) or (192)Ir((191)Ir + n) isotope activation; it was significantly greater in ICD than in PM and non-significantly greater in damaged devices. A greater effect in St Jude PM (2/2 damaged), Boston (9/11), and St Jude ICD (3/6) and in older ICD models was observed; the year of production was not relevant in PM. High-energy radiation can cause different malfunctions on CIED, particularly ICD, even without direct exposure to ionizing radiation due to scattered radiation of neutrons produced by the linear accelerator. Published on behalf of the European Society of Cardiology. All rights reserved. © The Author 2015. For permissions please email: journals.permissions@oup.com.

A comparison of ionizing radiation damage in CMOS devices from 60Co gamma rays, electrons and protons

International Nuclear Information System (INIS)

He Baoping; Yao Zhibin; Zhang Fengqi

2009-01-01

Radiation hardened CC4007RH and non-radiation hardened CC4011 devices were irradiated using 60 Co gamma rays, 1 MeV electrons and 1-9 MeV protons to compare the ionizing radiation damage of the gamma rays with the charged particles. For all devices examined, with experimental uncertainty, the radiation induced threshold voltage shifts (ΔV th ) generated by 60 Co gamma rays are equal to that of 1 MeV electron and 1-7 MeV proton radiation under 0 gate bias condition. Under 5 V gate bias condition, the distinction of threshold voltage shifts (ΔV th ) generated by 60 Co gamma rays and 1 MeV electrons irradiation are not large, and the radiation damage for protons below 9 MeV is always less than that of 60 Co gamma rays. The lower energy the proton has, the less serious the radiation damage becomes. (authors)

Inspection method for solidification product of radioactive waste and method of preparing solidification product of radiation waste

International Nuclear Information System (INIS)

Izumida, Tatsuo; Tamada, Shin; Matsuda, Masami; Kamata, Shoji; Kikuchi, Makoto.

1993-01-01

A powerful X-ray generation device using an electron-ray accelerator is used for inspecting presence or absence of inner voids in solidification products of radioactive wastes during or after solidification. By installing the X-ray CT system and the radioactive waste solidifying facility together, CT imaging for solidification products is conducted in a not-yet cured state of solidifying materials during or just after the injection. If a defect that deteriorates the durability of the solidification products should be detected, the solidification products are repaired, for example, by applying vibrations to the not-yet cured solidification products. Thus, since voids or cracks in the radioactive wastes solidification products, which were difficult to be measured so far, can be measured in a short period of time accurately thereby enabling to judge adaptability to the disposal standards, inspection cost for the radioactive waste solidification product can be saved remarkably. Further, the inside of the radioactive waste solidification products can be evaluated correctly and visually, so that safety in the ground disposal storage of the radioactive solidification products can be improved remarkably. (N.H.)

The portable GIS applied to geotechnical inspections; O GIS portatil para inspecoes geotecnicas

Energy Technology Data Exchange (ETDEWEB)

Rabaco, Lis M.; Lins, Alexandre F. [PETROBRAS S.A., Rio de Janeiro, RJ (Brazil); Costa, Rogerio M.; Freitas, Carlos F. [CONCREMAT, Rio de Janeiro, RJ (Brazil)

2005-07-01

The purpose of this paper is to implement an interface using tool to pack the GIS application to carry out a field inspection. The solution was implemented on pocket equipment using a simplified map and database integrated with the GIS Corporative. The main objective is to avoid paper work in field inspections. The emphases are on geotechnical inspections in order to assist the recuperation of information about points with geotechnical risk. There are interfaces with external device as GPS for insertion of points of risk. A set of tools are developed for bidirectional synchronization among the Corporative GIS and the pocket devices. The project focused geotechnical inspections on field, in order to synchronize automatically the information collected with the pocket GIS application with a Web server, packing all information from field operation to managers. (author)

The development of in-cell remote inspection system in Tokai reprocessing plant

International Nuclear Information System (INIS)

Ishibashi, Yuzo

1985-01-01

In the Tokai fuel reprocessing plant, the containment is triple, i.e. the vessel containing radioactive material, then the concrete cell structure and finally the housing building. The fuel reprocessing plant is now proceeding with the development of an in-cell remote inspection system. The inspection system is for inspection of the cell itself and the equipment etc. in the cell, concerning the integrity. Described are the following: the course taken and problems in development of the remote inspection system; development of the floor rambling type remote inspection equipment and the multiple armed type, both for inspection of in-cell ''drip trays''; in-cell equipment inspection devices in specifications etc.; problems in its future development. (Mori, K.)

Emerging nondestructive inspection methods for aging aircraft

Energy Technology Data Exchange (ETDEWEB)

Beattie, A; Dahlke, L; Gieske, J [and others

1994-01-01

This report identifies and describes emerging nondestructive inspection (NDI) methods that can potentially be used to inspect commercial transport and commuter aircraft for structural damage. The nine categories of emerging NDI techniques are: acoustic emission, x-ray computed tomography, backscatter radiation, reverse geometry x-ray, advanced electromagnetics, including magnetooptic imaging and advanced eddy current techniques, coherent optics, advanced ultrasonics, advanced visual, and infrared thermography. The physical principles, generalized performance characteristics, and typical applications associated with each method are described. In addition, aircraft inspection applications are discussed along with the associated technical considerations. Finally, the status of each technique is presented, with a discussion on when it may be available for use in actual aircraft maintenance programs. It should be noted that this is a companion document to DOT/FAA/CT-91/5, Current Nondestructive Inspection Methods for Aging Aircraft.

Gauging device

International Nuclear Information System (INIS)

Qurnell, F.D.; Patterson, C.B.

1979-01-01

A gauge supporting device for measuring say a square tube comprises a pair of rods or guides in tension between a pair of end members, the end members being spaced apart by a compression member or members. The tensioned guides provide planes of reference for measuring devices moved therealong on a carriage. The device is especially useful for making on site dimensional measurements of components, such as irradiated and therefore radioactive components, that cannot readily be transported to an inspection laboratory. (UK)

Research on dose setting for radiation sterilization of medical device

International Nuclear Information System (INIS)

Zhang Tongcheng; Liu Qingfang; Zhong Hongliang; Mi Zhisu; Wang Chunlei; Jiang Jianping

2002-01-01

Objective: To establish the radiation sterilization dose for medical devices using data of bioburden on the medical device. Methods: Firstly determination of recovery ratio and correction coefficient of the microbiological test method was used according to ISO11737 standard, then determination of bioburden on the products, finally the dose setting was completed based on the Method 1 in ISO11137 standard. Results: Fifteen kinds of medical devices were tested. Bioburden range was from 8.6-97271.2 CFU/device, recovery ration range 54.6%-100%, correction co-efficiency range 1.00-1.83, D 10 distribution from 1.40 to 2.82 kGy, verification dose (dose at SAL = 10 -2 ) range 5.1-17.6 kGy and sterilization dose (dose at SAL 10 -6 ) range 17.5-32.5 kGy. Conclusion: One hundred samples of each kind of product were exposed to the pre-determined verification dose and then the sterility test was performed. Each sterility test showed positive number was not greater than two. This indicated that the sterilization dose established for each kind of product was statistically acceptable

Inspections Report 2002 - 2003; Tillsynsrapport 2002 - 2003

Energy Technology Data Exchange (ETDEWEB)

Viidas, Josefin

2004-10-01

The report summarises primarily the supervision of waste management and environmental protection at the nuclear facilities that was carried out by the Swedish Radiation Protection Authority in 2002 and 2003. A summary of the inspections and a description of important issues connected with the supervision of nuclear facilities are given. The inspections during 2002 focused on the investigation and coverage of the mishap related to the transport of iridium from Studsvik. The Studsvik project was initiated and the remaining supervision was temporarily given lower priority. In 2003 SSI performed two theme inspections. One focused on the handling of waste management and the other on the limitation of the effluent. Extensive supervision efforts concentrated also on Ranstad Mineral inc.

Recent state of CdTe-based radiation detectors

International Nuclear Information System (INIS)

Ohno, R.

2004-01-01

Recent state for development of CdTe-based radiation detectors is reviewed. The progress of the technologies such as the crystal growth of CdTe and CdZnTe, the deposition of electrodes on the crystal, the design of read out ASIC, and the bonding between crystal and ASIC, opened the way for the development of imaging devices for practical uses. A X-ray imager for non destructive inspections and a gamma ray imager for small animal radioisotope experiments or nuclear medicine are presented as examples. (author)

Holography for fast reactor inspection

International Nuclear Information System (INIS)

Tozer, B.A.

1980-01-01

Holography, an optical process whereby an image of the original subject can be reconstructed in three dimensions, is being developed for use as an optical inspection tool. With a potential information storage density of 10 16 bits/m 2 , the ability to reconstruct in 3 dimensions, a depth of field of up to 8 metres, extremely wide angle of view, and potentially diffraction limited resolution, holography should be invaluable for the optical recording of fast reactors during construction, and the inspection of optically accessible regions during operation, or maintenance down-times. The photographic emulsions used for high resolution holography are fine-grained and fog only very slowly when subjected to γ-radiation, so that inspection of highly radio-active regions and components can be effected satisfactorily. Some of the practical limitations affecting holography are described and ways of overcoming them discussed. Some preliminary results are presented. (author)

Thermal and radiation losses in a linear device

International Nuclear Information System (INIS)

Rosenau, P.; Degani, D.

1980-01-01

An analysis is presented of the electron temperature in a linear device which includes the effect of thermal conduction, heat flux limit, radiation, and end plugs. It is found that the thermal conduction and the heat flux limit are dominant in the initial phase of cooling, while the later phase is almost completely controlled by radiation that spatially homogenizes the temperature distribution. In the case of bremsstrahlung, within the frame of the present model, the temperature decays to zero in a finite time. This process takes the form of a cooling wave that moves from the ends of the column to the center. Impurities cause a milder, exponential decay, which is still much faster than the algebraic conduction decay. The thermal effectiveness of the end plugs is described by a convective transfer coefficient h/sub p/. Its scaling law (in terms of the coupled plamsa-plug system) reveals that a very high plug-plasma density ratio provides a simple way to significantly retard the cooling

Underwater running device

International Nuclear Information System (INIS)

Kogure, Sumio; Matsuo, Takashiro; Yoshida, Yoji

1996-01-01

An underwater running device for an underwater inspection device for detecting inner surfaces of a reactor or a water vessel has an outer frame and an inner frame, and both of them are connected slidably by an air cylinder and connected rotatably by a shaft. The outer frame has four outer frame legs, and each of the outer frame legs is equipped with a sucker at the top end. The inner frame has four inner frame legs each equipped with a sucker at the top end. The outer frame legs and the inner frame legs are each connected with the outer frame and the inner frame by the air cylinder. The outer and the inner frame legs can be elevated or lowered (or extended or contracted) by the air cylinder. The sucker is connected with a jet pump-type negative pressure generator. The device can run and move by repeating attraction and releasing of the outer frame legs and the inner frame legs alternately while maintaining the posture of the inspection device stably. (I.N.)

Method of analyzing the shipping inspection water in nuclear fuels

International Nuclear Information System (INIS)

Ishikawa, Tatsuo; Izumoji, Yoshiaki.

1984-01-01

Purpose: To automatically perform radioactive-corrosion-products removing operation and thereby automatic analysis for shipping inspection water. Method: An radioactive-corrosion-product removing device has a column filled with a chelate resin layer. Shipping-inspection water as a specimen is injected from a sample-water inlet to the column, passes through the chelate resin layer, issues through the sample-water exit and is then stored once in a sample collector. The shipping inspection water sampled in the sampling collector is sent to an inspection port in an on-line or off-line manner and gamma-ray determination is made by a gamma-ray spectrum analyzer. (Horiuchi, T.)

Development of FBR visual inspection technique in sodium

International Nuclear Information System (INIS)

Suzuki, T.; Nagai, S.; Shioyama, T.; Sato, M.; Karasawa, H.; Maruyama, F.; Ota, S.; Hida, T.; Kai, M.

1995-01-01

Because the reactor vessel of Fast Breeder Reactor is filled with opaque liquid sodium, it is expected to develop an acoustic visual inspection technique in sodium. The acoustic 3 dimensional image processing technique and the elemental parts of the visual inspection equipment in sodium have been developed at the first stage of the in-sodium visual inspection technique development. The cross correlation processing has been applied to improve the S/N ratio in the acoustic echo that are deteriorated by wetting in sodium and the low sensitivity that are also deteriorated by rather smaller diameter to integrate the high density multiple acoustic sensors. The improvement of S/N ratio has been realized by the cross correlation between acoustic echo data that is reflected from the objects and M-series continuous wave that is transmitted from the acoustic transducer. The high speed parallel processing circuits, in which DSPs (Digital Signal Processors) are included, have been developed to realize high speed processing by employing (the circuits connected to) each of sensors in parallel. Synthetic Aperture Focussing Technique (SAFT) has been applied to the acoustic 3-dimensional image processing. The amounts of ellipsoids must be drawn into the 3-dimensional memory to compose the 3-dimensional image by SAFT. Then, a high performance work-station has been employed to deal with enormous data to compose the acoustic 3 dimensional image. Motors and cables, which can be operated under the condition of high-temperature and high-radiation environment, have been developed as the parts of the manipulator which will be used for visual inspection equipment in sodium. A prototype drive mechanism consists of the manipulator with three joints and a scanner with an arrayed acoustic sensors which a sweeps in fan-shape mechanically. The manipulatory type prototype drive mechanism and the signal processing device have been developed and tested, and the acoustic 3-dimensional image of pyramid

Regulations providing for the inspection of gamma radiography equipment

International Nuclear Information System (INIS)

1981-01-01

Pursuant to the 1938 Act on X-rays and radium, etc and the 1976 regulations on supervision and use of installations and apparatus which release radiation representing a hazard to health, the State Institute of Radiation Health issued these regulations providing for a system of periodic inspections of gamma radiography equipment for radiation protection purposes. They entered into force on 1 July 1981 [fr

Taking SiC Power Devices to the Final Frontier: Addressing Challenges of the Space Radiation Environment

Science.gov (United States)

Lauenstein, Jean-Marie; Casey, Megan

2017-01-01

Silicon carbide power device technology has the potential to enable a new generation of aerospace power systems that demand high efficiency, rapid switching, and reduced mass and volume in order to expand space-based capabilities. For this potential to be realized, SiC devices must be capable of withstanding the harsh space radiation environment. Commercial SiC components exhibit high tolerance to total ionizing dose but to date, have not performed well under exposure to heavy ion radiation representative of the on-orbit galactic cosmic rays. Insertion of SiC power device technology into space applications to achieve breakthrough performance gains will require intentional development of components hardened to the effects of these highly-energetic heavy ions. This work presents heavy-ion test data obtained by the authors over the past several years for discrete SiC power MOSFETs, JFETs, and diodes in order to increase the body of knowledge and understanding that will facilitate hardening of this technology to space radiation effects. Specifically, heavy-ion irradiation data taken under different bias, temperature, and ion beam conditions is presented for devices from different manufacturers, and the emerging patterns discussed.

Simulating threshold voltage shift of MOS devices due to radiation in the low-dose range

CERN Document Server

Wan Xin Heng; Gao Wen Yu; Huang Ru; Wang Yang Yuan

2002-01-01

An analytical MOSFET threshold voltage shift model due to radiation in the low-dose range has been developed for circuit simulations. Experimental data in the literature shows that the model predictions are in good agreement. It is simple in functional form and hence computationally efficient. It can be used as a basic circuit simulation tool for analysing MOSFET exposed to a nuclear environment up to about 1 Mrad(Si). In accordance with common believe, radiation induced absolute change of threshold voltage was found to be larger in irradiated PMOS devices. However, if the radiation sensitivity is defined in the way authors did it, the results indicated NMOS rather than PMOS devices are more sensitive, specially at low doses. This is important from the standpoint of their possible application in dosimetry

Design of radiation-chemical devices with gamma source for sewage treatment

International Nuclear Information System (INIS)

Mendel'son, Eh.L.; Gol'din, V.A.; Breger, A.Kh.

1981-01-01

The semiempirical method of calculating conductivity of radiation- chemical devices (RCD) with γ-sources to purify domestic and industrial drainage waters and other processes in liquid phase systems which meet definite requirements based on taking into account the structure of the technological process, is suggested RCD of a new type is developed. It is coaxially cylindrical. A correcting coefficient which takes into account the difference in the actual time of keeping a current of drainage water in the device and its avaraged calculation value, conditioned by the longtitudinal transfer of a substance in the device, is determined. It is shown that the above RCD productivity can be considerably increased due to creating the structure of adisplacement current which provides the equality of absorbed doses in all its elements [ru

Hydro-Quebec inspection robot RIT-LRG

International Nuclear Information System (INIS)

Champagne, D.; Rinfret, F.; Bourgault, Y.G.

2008-01-01

Hydro Quebec's Research Centre (IREQ), has developed a variety of inspection tools over the years. The Metar bracelet for the feeder tubes, the REC robot for the heat exchanger and the RIT robot for the Delayed Neutron system just to name a few. This paper discusses with the successful deployment of the Camera Probe Positioning robot for Visual Inspection of the sample lines of the delayed neutron system of CANDU power plants. This RIT robot has three possible configurations (Face, Cabinet and LRG configurations) and has remained a prototype version although it has been used over the years in many outage inspection campaigns since 1997. The main advantages of using this robot are: the significant reduction in radiation exposure, the high quality of the data collected and the archiving of inspection data for further analysis and reports. In 2007, Gentilly-2 (G-2), decided to industrialize the LRG configuration of the RIT robot and to designate it the standard tool for the inspection of the Delayed Neutron System. An improved RIT-LRG robot, along with its control box and command station was developed. The software had to be rewritten requiring an ergonomics analysis of user tasks, work station and interface display. These issues included both physical and cognitive requirements aspects. The two principal topics of this paper will be on the Inspection Robot Technology developed and highlights of the 2008 outage inspection campaign. (author)

Hydro-Quebec inspection robot RIT-LRG

Energy Technology Data Exchange (ETDEWEB)

Champagne, D., E-mail: champagne.dominique@ireq.ca [Inst. de recherche d' Hydro-Quebec, Quebec (Canada); Rinfret, F.; Bourgault, Y.G., E-mail: rinfret.francois@hydro.qc.ca, E-mail: bourgault.yves.g@hydro.qc.ca [Hydro-Quebec, Becancour, Quebec (Canada)

2008-07-01

Hydro Quebec's Research Centre (IREQ), has developed a variety of inspection tools over the years. The Metar bracelet for the feeder tubes, the REC robot for the heat exchanger and the RIT robot for the Delayed Neutron system just to name a few. This paper discusses with the successful deployment of the Camera Probe Positioning robot for Visual Inspection of the sample lines of the delayed neutron system of CANDU power plants. This RIT robot has three possible configurations (Face, Cabinet and LRG configurations) and has remained a prototype version although it has been used over the years in many outage inspection campaigns since 1997. The main advantages of using this robot are: the significant reduction in radiation exposure, the high quality of the data collected and the archiving of inspection data for further analysis and reports. In 2007, Gentilly-2 (G-2), decided to industrialize the LRG configuration of the RIT robot and to designate it the standard tool for the inspection of the Delayed Neutron System. An improved RIT-LRG robot, along with its control box and command station was developed. The software had to be rewritten requiring an ergonomics analysis of user tasks, work station and interface display. These issues included both physical and cognitive requirements aspects. The two principal topics of this paper will be on the Inspection Robot Technology developed and highlights of the 2008 outage inspection campaign. (author)

Role of radiations in assuring quality in space programme

International Nuclear Information System (INIS)

Viswanathan, K.

1993-01-01

Penetrating radiations such as x-rays, gamma rays, neutrons are extensively used for radiographic inspection of various components used in space programmes. Some of these are rocket motor segments, assembled motors, composite nozzles, igniters, pyro devices, and various critical sub systems. These components employ advanced materials like composites, propellants, insulation materials, alloy steels, maraging steel, pyro techniques etc. Often they are in complex geometrical shapes and assemblies. Simulation of radiation environment on a number of components used in satellites is also carried out using radiation sources. This will help in assessing the effect of terrestrial radiation on the components that work in space. Future trends in the exploitation of radiation for space applications include automated radiography and development of expert systems, computed tomography, improvement in realtime radiography, Compton back scatter tomography etc. Adapting some of the advancements in medical radiology to industrial environment is also a welcome step in future. (author). 2 figs

49 CFR 229.25 - Tests: Every periodic inspection.

Science.gov (United States)

2010-10-01

... mechanical gauges used by the engineer to aid in the control or braking of the train or locomotive, except... follows: (1) All automatic controls, alarms and protective devices shall be inspected and tested. (2...

2013 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act Title I Disposal Sites

Energy Technology Data Exchange (ETDEWEB)

None, None

2014-03-01

This report, in fulfillment of a license requirement, presents the results of long-term surveillance and maintenance activities conducted by the U.S. Department of Energy (DOE) Office of Legacy Management (LM) in 2013 at 19 uranium mill tailings disposal sites established under Title I of the Uranium Mill Tailings Radiation Control Act (UMTRCA) of 1978.1 These activities verified that the UMTRCA Title I disposal sites remain in compliance with license requirements. DOE operates 18 UMTRCA Title I sites under a general license granted by the U.S. Nuclear Regulatory Commission (NRC) in accordance with Title 10 Code of Federal Regulations Part 40.27 (10 CFR 40.27). As required under the general license, a long-term surveillance plan (LTSP) for each site was prepared by DOE and accepted by NRC. The Grand Junction, Colorado, Disposal Site, one of the 19 Title I sites, will not be included under the general license until the open, operating portion of the cell is closed. The open portion will be closed either when it is filled or in 2023. This site is inspected in accordance with an interim LTSP. Long-term surveillance and maintenance services for these disposal sites include inspecting and maintaining the sites; monitoring environmental media and institutional controls; conducting any necessary corrective actions; and performing administrative, records, stakeholder relations, and other regulatory stewardship functions. Annual site inspections and monitoring are conducted in accordance with site-specific LTSPs and procedures established by DOE to comply with license requirements. Each site inspection is performed to verify the integrity of visible features at the site; to identify changes or new conditions that may affect the long-term performance of the site; and to determine the need, if any, for maintenance, follow-up or contingency inspections, or corrective action in accordance with the LTSP. LTSPs and site compliance reports are available on the Internet at http://www.lm.doe.gov/.

Preliminary technical assessment of an inflatable inspection probe - phase II

International Nuclear Information System (INIS)

Anon.

1987-01-01

A technique used to inspect many types of heat exchanger tubing in power generation equipment employs an eddy current test method. This test method requires that a probe be inserted into and through the tubing. With the objective of having a probe small enough to navigate tubing irregularities and always maintaining probe-to-tube proximity, EPRI Program Manager Gary Dau conceived a device (probe) that utilizes an inflatable, elastic bladder. Owing to its compliant properties, this new device would pass through tube irregularities, yet could keep the eddy current coils near to the internal surfaces of the tubing. Under RP2673-1, Battelle conducted work to evaluate and suggest candidate elastomeric materials to be used as the expandable bladder. The basic materials that were identified: thermoplastic urethane, polyurethane foam, polychloroprene, and polyisoprene. Given these materials and the expandable inspection device, as it was conceptualized at that time, manufacturing processes suitable for production were also evaluated. The likely manufacturing processes to be employed for the production of the expandable device using the suggested materials are cast molding and solution dipping. Work in 1986 involved the evaluation of alternative designs that could be used for the expandable inspection probe. The designs that were ultimately selected and that are compatible with materials and commercial manufacturing processes already identified are presented in the final report on this project

Chalcogenide Glass Radiation Sensor; Materials Development, Design and Device Testing

Energy Technology Data Exchange (ETDEWEB)

Mitkova, Maria; Butt, Darryl; Kozicki, Michael; Barnaby, Hugo

2013-04-30

For many decades, various radiation detecting material have been extensively researched, to find a better material or mechanism for radiation sensing. Recently, there is a growing need for a smaller and effective material or device that can perform similar functions of bulkier Geiger counters and other measurement options, which fail the requirement for easy, cheap and accurate radiation dose measurement. Here arises the use of thin film chalcogenide glass, which has unique properties of high thermal stability along with high sensitivity towards short wavelength radiation. The unique properties of chalcogenide glasses are attributed to the lone pair p-shell electrons, which provide some distinctive optical properties when compared to crystalline material. These qualities are derived from the energy band diagram and the presence of localized states in the band gap. Chalcogenide glasses have band tail states and localized states, along with the two band states. These extra states are primarily due to the lone pair electrons as well as the amorphous structure of the glasses. The localized states between the conductance band (CB) and valence band (VB) are primarily due to the presence of the lone pair electrons, while the band tail states are attributed to the Van der Waal's forces between layers of atoms [1]. Localized states are trap locations within the band gap where electrons from the valence band can hop into, in their path towards the conduction band. Tail states on the other hand are locations near the band gap edges and are known as Urbach tail states (Eu). These states are occupied with many electrons that can participate in the various transformations due to interaction with photons. According to Y. Utsugi et. al.[2], the electron-phonon interactions are responsible for the generation of the Urbach tails. These states are responsible for setting the absorption edge for these glasses and photons with energy near the band gap affect these states. We have

77 FR 41417 - Regulatory Science Considerations for Medical Countermeasure Radiation Biodosimetry Devices

Science.gov (United States)

2012-07-13

... scientific and technological challenges for performance validation of radiation biodosimetry devices. Date... participants (non-FDA employees) is through Bldg. 1 where routine security check procedures will be performed... this document. FDA will do its best to accommodate requests to make public comment. Individuals and...

Increasing for effectiveness of inspection of the use of radioactive substances well logging

International Nuclear Information System (INIS)

Hesty Rimadianny

2015-01-01

One of the utilization of nuclear power is the use of radioactive substances for well logging. To ensure the achievement of radiation safety and security in the use of radioactive substances for well logging activities BAPETEN carries out inspections in accordance with the mandate as sepulated in the Government Regulation No. 29 of 2008 on the Licensing Resource Utilization Ionizing Radiation and Nuclear Materials. Besides referring to the implementation of Government Regulation inspection also refers to BAPETEN Chairman Regulation No. 5 of 2009 on Radiation Safety in the Use of Radioactive material for well logging. In 2014, of 18 facilities inspected the most significant findings include the availability of equipment safety and security of radioactive substances, as well as the availability and suitability of documents and records of safety and security of radioactive substances for well logging activities. Based on these findings BAPETEN needs to make efforts to increase the effectiveness of inspections on the use of radioactive substances for well logging. Increasing the effectiveness of these inspections include a commitment for the frequency of well logging inspection, the number of qualified of inspectors in accordance with the established procedures and optimizing the law enforcement process which includes the application of administrative sanctions in the form of a written warning, license suspension, revocation until reporting to law enforcement. Besides, BAPETEN need to improve the effectiveness of outreach programs and legal guidance as a precaution in the long run. (author)

Visual Inspection of the Flow Distribution Plate Bolts of a Nuclear Steam Generator

International Nuclear Information System (INIS)

Jeong, Woo Tae; Kim, Suk Tae; Sohn, Wook; Kang, Duk Won; Kang, Seok Chul

2007-01-01

To develop a system for visually inspecting the flow distribution plate (FDP) bolts of a nuclear steam generator, we reviewed several types of similar inspection equipment. The equipment which are currently available are mostly for inspecting lower part of a steam generator such as tube sheets and annulus except ELVS (Eggcrate Visual Inspection System). However, the design concept of ELVS could not be used for developing a device which enables the visual inspection of flow distribution plate bolts. Therefore, based on the current state of the art technology on the similar equipment, we conceptually designed a new inspection system for checking the FDP bolts

Improvements in televisual and photographic inspections of AGRs

International Nuclear Information System (INIS)

Hayter, R.; Wadsworth, A.

1988-01-01

The visual inspection techniques and equipment used at AGR Power Stations have been improved and updated in the light of need and technological advance, new equipment being developed and introduced where necessary. Specifically this report covers the development and use of: a short TRIUMPH compatible photographic camera 600 mm long x 75 mm dia taking 50 shots on a 35 mm film; a 240 mm dia photographic pod taking high quality 70 mm format photographs of large in-reactor volumes; a photographic camera of cross section 37 x 17 mm for the inspection of helically wound AGR boilers and the subsequent development of this latter device into a state of the art TV inspection camera. (author)

Wearable device for monitoring momentary presence of intense x-ray and/or ultra-violet radiations

International Nuclear Information System (INIS)

Shriner, W.

1981-01-01

A credit-card-size clear-plastic-encased device can be worn or carried by a person to warn him of the momentary presence of dangerous intensities of ultra-violet and/or x-ray radiations. A base lamina (e.g. of cardboard) is coated with a material (e.g. zinc-cadmium sulfide or lead-barium sulfate) which fluoresces under such radiations. Numerals, letters, words or symbols are printed over the fluorescent coat with a material inhibitory to said radiations so that a warning message in dark print will appear on a light background when dangerous intensities of said radiations are present. An x-ray-warning area is covered with an ultra-violet absorbing screen so that said area will glow only under x-rays (Which rays will also activate the remaining ultra-violet-responsive area). The colors of the laminas and the coats are so selected that the messages are not visible when dangerous radiations are not present. If desired, only the message can be printed with fluorescent material so as to glow on a darker background. Optionally, step-layer attenuation devices can be added to indicate degrees of radiation; and reflecting surfaces can underlie the fluorescent coat to increase efficiency and/or sensitively

A study of radiation vulnerability of ferroelectric material and devices

International Nuclear Information System (INIS)

Coiec, Y.M.; Musseau, O.; Leray, J.L.

1994-01-01

The radiation effects on ferroelectric material and devices are presented, based on commercially available samples. After recalling the background, effects in ferroelectric PZT capacitors are presented, concerning dose, neutrons and fatigue associated with dose effects. Physical implications and interpretations are sketched. In a second stage, effects are studied at the complete non-volatile RAM device level. Vulnerability in dose, dose rate and neutron fluence of commercial 4 kbit ferroelectric RAM is addressed. 64 kbit results are mentioned in dose rate. These results are compared to previously published data from other manufacturers or laboratories and supplement them. In the appendix, equivalence between rad(Si) and rad (PZT) is discussed in the case of low energy ''10 keV Aracor'' x-rays and 60 Co gamma rays

The inspection of components by X ray in real time in automobile industry

International Nuclear Information System (INIS)

Demandt, K.

1987-01-01

Besides a brief introduction to the state of the art of automobile components inspection by radiography in real time, some examples are discussed. New developments and a possible application for automobile components inspection by x-radiation are discussed. (E.G.) [pt

Evaluation of pelletron accelerator facility to study radiation effects on semiconductor devices

Energy Technology Data Exchange (ETDEWEB)

Prakash, A. P. Gnana; Pushpa, N.; Praveen, K. C.; Naik, P. S.; Revannasiddaiah, D. [Department of Studies in Physics, University of Mysore, Manasagangotri, Mysore-570006, Karnataka (India)

2012-06-05

In this paper we present the comprehensive results on the effects of different radiation on the electrical characteristics of different semiconductor devices like Si BJT, n-channel MOSFETs, 50 GHz and 200 GHz silicon-germanium heterojunction bipolar transistor (SiGe HBTs). The total dose effects of different radiation are compared in the same total dose ranging from 100 krad to 100 Mrad. We show that the irradiation time needed to reach very high total dose can be reduced by using Pelletron accelerator facilities instead of conventional irradiation facilities.

Evaluation of pelletron accelerator facility to study radiation effects on semiconductor devices

International Nuclear Information System (INIS)

Prakash, A. P. Gnana; Pushpa, N.; Praveen, K. C.; Naik, P. S.; Revannasiddaiah, D.

2012-01-01

In this paper we present the comprehensive results on the effects of different radiation on the electrical characteristics of different semiconductor devices like Si BJT, n-channel MOSFETs, 50 GHz and 200 GHz silicon-germanium heterojunction bipolar transistor (SiGe HBTs). The total dose effects of different radiation are compared in the same total dose ranging from 100 krad to 100 Mrad. We show that the irradiation time needed to reach very high total dose can be reduced by using Pelletron accelerator facilities instead of conventional irradiation facilities.

Advanced inspection and repair techniques for primary side components

International Nuclear Information System (INIS)

Elm, Ralph

1998-01-01

The availability of nuclear power plant mainly depends on the components of the Nuclear Steam Supply System (NSSS) such as reactor pressure vessel, core internals and steam generators. The last decade has been characterized by intensive inspection and repair work on PWR steam generators. In the future, it can be expected, that the inspection of the reactor pressure vessel and the inspection and repair of its internals, in both PWR and BWR will be one of the challenges for the nuclear community. Due to this challenge, new, advanced inspection and repair techniques for the vital primary side components have been developed and applied, taking into account such issues as: use of reliable and fast inspection methods, repair of affected components instead of costly replacement, reduction of outage time compared to conventional methods, minimized radiation exposure, acceptable costs. This paper reflects on advanced inspection and repair techniques such as: Baffle Former Bolt inspection and replacement, Barrel Former Bolt inspection and replacement, Mechanized UT and visual inspection of reactor pressure vessels, Steam Generator repair by advanced sleeving technology. The techniques described have been successfully applied in nuclear power plants and improved the operation performance of the components and the NPP. (author). 6 figs

Improving radiation hardness in space-based Charge-Coupled Devices through the narrowing of the charge transfer channel

Science.gov (United States)

Hall, D. J.; Skottfelt, J.; Soman, M. R.; Bush, N.; Holland, A.

2017-12-01

Charge-Coupled Devices (CCDs) have been the detector of choice for imaging and spectroscopy in space missions for several decades, such as those being used for the Euclid VIS instrument and baselined for the SMILE SXI. Despite the many positive properties of CCDs, such as the high quantum efficiency and low noise, when used in a space environment the detectors suffer damage from the often-harsh radiation environment. High energy particles can create defects in the silicon lattice which act to trap the signal electrons being transferred through the device, reducing the signal measured and effectively increasing the noise. We can reduce the impact of radiation on the devices through four key methods: increased radiation shielding, device design considerations, optimisation of operating conditions, and image correction. Here, we concentrate on device design operations, investigating the impact of narrowing the charge-transfer channel in the device with the aim of minimising the impact of traps during readout. Previous studies for the Euclid VIS instrument considered two devices, the e2v CCD204 and CCD273, the serial register of the former having a 50 μm channel and the latter having a 20 μm channel. The reduction in channel width was previously modelled to give an approximate 1.6× reduction in charge storage volume, verified experimentally to have a reduction in charge transfer inefficiency of 1.7×. The methods used to simulate the reduction approximated the charge cloud to a sharp-edged volume within which the probability of capture by traps was 100%. For high signals and slow readout speeds, this is a reasonable approximation. However, for low signals and higher readout speeds, the approximation falls short. Here we discuss a new method of simulating and calculating charge storage variations with device design changes, considering the absolute probability of capture across the pixel, bringing validity to all signal sizes and readout speeds. Using this method, we

Remotely controlled inspection and handling systems for decommissioning tasks in nuclear facilities

International Nuclear Information System (INIS)

Schreck, G.; Bach, W.; Haferkamp, H.

1993-01-01

The Institut fur Werkstoffkunde at the University of Hanover has recently developed three remotely controlled systems for different underwater inspection and dismantling tasks. ODIN I is a tool guiding device, particularly being designed for the dismantling of the steam dryer housing of the KRB A power plant at Gundremmingen, Germany. After being approved by the licencing organization TUEV Bayern, hot operation started in November 1992. The seven axes remotely controlled handling system ZEUS, consisting of a three translatory axes guiding machine and a tool handling device with four rotatory axes, has been developed for the demonstration of underwater plasma arc cutting of spherical metallic components with great wall thicknesses. A specially designed twin sensor system and a modular torch, exchanged by means of a remote controlled tool changing device, will be used for different complex cutting tasks. FAUST, an autonomous, freediving underwater vehicle, was designed for complex inspection, maintenance and dismantling tasks. It is equipped with two video cameras, an ultrasonic and a radiologic sensor and a small plasma torch. A gripper and a subsidiary vehicle for inspection may be attached. (author)

To a scientific substantiation of a practical method of inspection of radiating conditions on territories, polluted with atmospheric fallout

International Nuclear Information System (INIS)

Burmistrov, V.R; Makarenko, N.G.; Karimova, L.M.

2001-01-01

Full text: In the report a question on necessity of practical development of a method of inspection of radiating fields, adapted to a nature of pollution is put. 50-year study of radionuclides pollution, dropping out from atmosphere after nuclear tests or failures, have shown non-perspective of traditional techniques of inspection of a radiating conditions on large territories. The detailed measurements covering surface without gaps are very expensive, and use of a unloaded grid requires interpolation irregular mosaic structure. Detection Fractal structure at the analysis Chernobyl losses and pollution of fragments of Semipalatinsk test nuclear site specify necessity of the account of self-similar properties of pollution in philosophy of measurement. For realization of potential opportunities Fractal field the special circuit of measurements, distinguished from, is required standard. Fractal approach requires shooting with system of crossed vicinities on chosen detailed platforms, making a rather small part of surveyed territory. These data will allow to reveal scale laws, which are universal in a significant range of scales. Using scaling of small platforms, it is possible to receive correct estimation of structure of pollution of large territories. The stated above reasons are based on our experiments on fractal approach to the analysis of continuous shooting (aero-scale shooting of scale 1:5000) in a zone of Semipalatinsk test site on three platforms by the sizes on 1000x400 m 2 . Our results specify necessity revision almost of all conclusions, received earlier on the basis of traditional techniques

A Broad Coverage Neutron Source For Security Inspections

Science.gov (United States)

Yang, Yang; Robert, Stubbers; Linchun, Wu; George, Miley

2004-05-01

To meet the increasing demanding requirements for security safety inspections, a line-type neutron source employing a cylindrical IEC (RC-IEC) is proposed for non-destructive "in situ" security inspections. The advantages of such a neutron source include line geometry, modularity, swithcability, variable source strength, low cost with minimum maintenance. Detailed description of a 1/3 scale cylindrical device is presented, which might demonstrate that a reasonably long RC-IEC produces a stable discharge with reasonably uniform neutron production along the cylindrical axis. Aiming at the neutron production efficiency at the order of 106 n/J, several methods to maximize neutron production efficiency are discussed. The results of a two-dimensional computer code(MCP) using a Monte Carlo numerical approach for the RC-IEC device are presented together with an analysis of neutron yield vs. different operation parameters.

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

International Nuclear Information System (INIS)

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

2013-01-01

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

An Articulated Inspection Arm for fusion purposes

Energy Technology Data Exchange (ETDEWEB)

Villedieu, E., E-mail: eric.villedieu@cea.fr [CEA-IRFM, 13108 Saint Paul lez Durance (France); Bruno, V.; Pastor, P.; Gargiulo, L. [CEA-IRFM, 13108 Saint Paul lez Durance (France); Song, Y.T.; Cheng, Y.; Feng, H. [Institute of Plasma Physics, Chinese Academy of Sciences, Hefei (China); Liu, C. [CEA-IRFM, 13108 Saint Paul lez Durance (France); Institute of Plasma Physics, Chinese Academy of Sciences, Hefei (China); Shi, S.S. [Institute of Plasma Physics, Chinese Academy of Sciences, Hefei (China)

2016-11-01

Highlights: • Requirements for in vacuum tokamak inspection are presented. • Development of a prototype of the Articulated Inspection Arm is described. • The upgrade of the prototype to convert it into a fully operational device is detailed. • Future applications of inspection robots in the new fusion reactors is discussed. - Abstract: Fusion Tokamaks are complex machines which require special conditions for their operation, in particular, high vacuum inside the vessel and high temperature of the vessel walls. During plasma phases, the first wall components are highly stressed and a control is necessary in case of doubt about their condition. To be able to make safely such an inspection in a short period of time is a great advantage. The Articulated Inspection Arm (AIA) developed by the CEA provides the capability for fast inspections of the first wall overall surface keeping the vacuum and temperature conditions of the vessel. The robot prototype was validated in Tore Supra in 2008. In the frame of a joint laboratory, CEA/IRFM and ASIPP have decided to upgrade the existing AIA prototype to use it routinely in the EAST and WEST tokamaks. The robot has followed an important upgrade program in 2013 and 2014. The document presents the various upgrades made on the mechanics, the sensors, the electronics, the control station and the integration adaptation for the operation on EAST. From the AIA experience, thoughts for future inspection robots are given.

An Articulated Inspection Arm for fusion purposes

International Nuclear Information System (INIS)

Villedieu, E.; Bruno, V.; Pastor, P.; Gargiulo, L.; Song, Y.T.; Cheng, Y.; Feng, H.; Liu, C.; Shi, S.S.

2016-01-01

Highlights: • Requirements for in vacuum tokamak inspection are presented. • Development of a prototype of the Articulated Inspection Arm is described. • The upgrade of the prototype to convert it into a fully operational device is detailed. • Future applications of inspection robots in the new fusion reactors is discussed. - Abstract: Fusion Tokamaks are complex machines which require special conditions for their operation, in particular, high vacuum inside the vessel and high temperature of the vessel walls. During plasma phases, the first wall components are highly stressed and a control is necessary in case of doubt about their condition. To be able to make safely such an inspection in a short period of time is a great advantage. The Articulated Inspection Arm (AIA) developed by the CEA provides the capability for fast inspections of the first wall overall surface keeping the vacuum and temperature conditions of the vessel. The robot prototype was validated in Tore Supra in 2008. In the frame of a joint laboratory, CEA/IRFM and ASIPP have decided to upgrade the existing AIA prototype to use it routinely in the EAST and WEST tokamaks. The robot has followed an important upgrade program in 2013 and 2014. The document presents the various upgrades made on the mechanics, the sensors, the electronics, the control station and the integration adaptation for the operation on EAST. From the AIA experience, thoughts for future inspection robots are given.

Design considerations for an intelligent mobile robot for mixed-waste inspection

Energy Technology Data Exchange (ETDEWEB)

Sias, F.R.; Dawson, D.M.; Schalkoff, R.J. [Clemson Univ., SC (United States). Dept. of Electrical and Computer Engineering; Byrd, J.S.; Pettus, R.O. [South Carolina Univ., Columbia, SC (United States). Dept. of Electrical and Computer Engineering

1993-06-01

Large quantities of low-level radioactive waste are stored in steel drums at various Department of Energy (DOE) sites in the United States. Much of the stored waste qualifies as mixed waste and falls under Environmental Protection Agency (EPA) regulations that require periodic inspection. A semi-autonomous mobile robot is being developed during Phase 1 of a DOE contract to perform the inspection task and consequently reduce the radiation exposure of inspection personnel to ALARA (as low as reasonably achievable). The nature of the inspection process, the resulting robot design requirements, and the current status of the project are the subjects of this paper.

Design considerations for an intelligent mobile robot for mixed-waste inspection

International Nuclear Information System (INIS)

Sias, F.R.; Dawson, D.M.; Schalkoff, R.J.; Byrd, J.S.; Pettus, R.O.

1993-01-01

Large quantities of low-level radioactive waste are stored in steel drums at various Department of Energy (DOE) sites in the United States. Much of the stored waste qualifies as mixed waste and falls under Environmental Protection Agency (EPA) regulations that require periodic inspection. A semi-autonomous mobile robot is being developed during Phase 1 of a DOE contract to perform the inspection task and consequently reduce the radiation exposure of inspection personnel to ALARA (as low as reasonably achievable). The nature of the inspection process, the resulting robot design requirements, and the current status of the project are the subjects of this paper

A study of radiation vulnerability of ferroelectric material and devices

Energy Technology Data Exchange (ETDEWEB)

Coic, Y M; Musseau, O; Leray, J L [CEA Centre d` Etudes de Bruyeres-le-Chatel, 91 (France)

1994-12-31

The radiation effects on ferroelectric material and devices are presented, based on commercially available samples. After recalling the background, effects in ferroelectric PZT capacitors are presented, concerning dose, neutrons and fatigue associated with dose effects. Physical implications and interpretations are sketched. In a second stage, effects are studied at the complete non-volatile RAM device level. Vulnerability in dose, dose rate and neutron fluence of commercial 4 kbit ferroelectric RAM is addressed. 64 kbit results are mentioned in dose rate. These results are compared to previously published data from other manufacturers or laboratories and supplement them. In the appendix, equivalence between rad (Si) and rad (PZT) is discussed in the case of low energy ``10 keV Aracor`` s-rays and {sup 60}Co gamma rays. (author). 24 refs., 11 figs., 7 tabs.

A study of radiation vulnerability of ferroelectric material and devices

International Nuclear Information System (INIS)

Coic, Y.M.; Musseau, O.; Leray, J.L.

1994-01-01

The radiation effects on ferroelectric material and devices are presented, based on commercially available samples. After recalling the background, effects in ferroelectric PZT capacitors are presented, concerning dose, neutrons and fatigue associated with dose effects. Physical implications and interpretations are sketched. In a second stage, effects are studied at the complete non-volatile RAM device level. Vulnerability in dose, dose rate and neutron fluence of commercial 4 kbit ferroelectric RAM is addressed. 64 kbit results are mentioned in dose rate. These results are compared to previously published data from other manufacturers or laboratories and supplement them. In the appendix, equivalence between rad (Si) and rad (PZT) is discussed in the case of low energy ''10 keV Aracor'' s-rays and 60 Co gamma rays. (author). 24 refs., 11 figs., 7 tabs

An intelligent inspection and survey robot. Volume 2

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-12-15

Radioactive materials make up a significant part of the hazardous-material inventory of the Department of Energy. Much of the radioactive material will be inspected or handled by robotic systems that contain electronic circuits that may be damaged by gamma radiation and other particles emitted from radioactive material. This report examines several scenarios, the damage that may be inflicted, and methods that may be used to protect radiation-hardened robot control systems. Commercial sources of components and microcomputers that can withstand high radiation exposure are identified.

An intelligent inspection and survey robot. Volume 2

International Nuclear Information System (INIS)

1995-01-01

Radioactive materials make up a significant part of the hazardous-material inventory of the Department of Energy. Much of the radioactive material will be inspected or handled by robotic systems that contain electronic circuits that may be damaged by gamma radiation and other particles emitted from radioactive material. This report examines several scenarios, the damage that may be inflicted, and methods that may be used to protect radiation-hardened robot control systems. Commercial sources of components and microcomputers that can withstand high radiation exposure are identified

Testing and analysis of tube voltage and tube current in the radiation generator for mammography

International Nuclear Information System (INIS)

Jung, Hong Ryang; Hong, Dong Hee; Han, Beom Hui

2014-01-01

Breast shooting performance management and quality control of the generator is applied to the amount of current IEC(International Electrotechnical Commission) 60601-2-45 tube voltage and tube current are based on standards that were proposed in the analysis of the test results were as follows. Tube voltage according to the value of the standard deviation by year of manufacture from 2001 to 2010 as a 42-3.15 showed the most significant, according to the year of manufacture by tube amperage value of the standard deviation to 6.38 in the pre-2000 showed the most significant , manufactured after 2011 the standard deviation of the devices, the PAE(Percent Average Error) was relatively low. This latest generation device was manufactured in the breast of the tube voltage and tube diagnosed shooting the correct amount of current to maintain the performance that can be seen. The results of this study as the basis for radiography diagnosed breast caused by using the device's performance and maintain quality control, so the current Food and Drug Administration 'about the safety of diagnostic radiation generator rule' specified in the test cycle during three years of self-inspection radiation on a radiation generating device ensure safety and performance of the device using a coherent X-ray(constancy) by two ultimately able to keep the radiation dose to the public to reduce the expected effect is expected

New challenge for the radiation protection: devices for the radioactivity dispersion

International Nuclear Information System (INIS)

Mora, J. C.; Robles, B.; Cancio, C.

2006-01-01

In recent years the terrorist attacks produced in several countries have changed the mind of the security experts. This has also included the Radiation Protection aspects. Newly considered features have required the update of emergency response and preparedness, ad well as a greater emphasis on security. Within the Radiation Protection field has been introduced the radiological and nuclear terrorism definition. almost every organism and research centre involved in Radiation Protection is nowadays working on. The possible terrorist attack scenarios have already been defined and the use of an explosive to disperse radioactive material, known as a Radiation Dispersion Devices (RDD), has been specified as the most probable one. Studies to mitigate against the chance of attack and to mitigate the consequences of any attack with a RDD are complex, due to the innovation that introduce. This leads to a need to take some immediate preventative actions and to carry out additional R and D efforts. This document presents some considerations on the possible RDD design and behaviour in order to prevent and prepare against a possible attack. (Author) 17 refs

Preliminary study on the relation between the coping patterns and mental health of radiation control personnel and nondestructive inspectors engaged in the periodic inspections of nuclear power plants.

Science.gov (United States)

Nagaoka, Chika; Uchida, Yukiko

2014-01-01

In order to safely manage nuclear power plants, their workforce should be mentally healthy. This study clarifies the coping strategies of radiation control personnel and nondestructive inspectors engaged in the periodic inspection of nuclear power plants, the effect of the coping strategies on their mental health, as well as any effect based on whether or not they had worked after the nuclear disaster caused by the Great East Japan Earthquake and tsunami in March 2011. A questionnaire survey was administered to 133 technicians attending a certification course, and among them, our subjects of analysis were 104 people with work experience in radiation control and/or nondestructive inspection. The results indicated that even among workers of the same company who were assigned to similar duties in the periodic inspections of nuclear power plants, the group that had worked at a nuclear plant after the disaster had a tendency to use coping strategies, such as giving up and avoidance-like thinking, which was dissimilar to the group that had not worked at a nuclear plant after the disaster. Further, the former group had higher levels of distress than those who tended to use other coping strategies. In addition, the results suggested that the plan-drafting strategy adopted by the group that had not worked after the disaster did not result in stress reduction. Based on these results, we propose a stress management program specifically for radiation workers.

Procedure for the determination of gap and base ground surface configurations beneath the bottom plate of storage tanks using neutron gauging inspection techniques : including radiation safety procedure and emergency procedure

International Nuclear Information System (INIS)

Jaafar Abdullah

1993-01-01

The procedure is intended for the neutron gauging inspection of gap between the bottom plate and the foundation of bulk storage tanks, which potentially exhibit uneven sinking of the bottom plate and the foundation. Its describes the requirements for the performance of neutron back scattered inspection techniques (or radiometric non-destructive evaluation techniques), using an isotopic neutron source associated with neutron detecting systems, to detect and size the gap between the bottom plate and the foundations as well as to quantify the presence of hydrogenous materials (e.g. oil or water) underneath the bottom plate. This procedure is not only outline the requirements for the neutron gauging inspection, but also describes the requirements which shall be taken into account in formulating the radiation safety and emergency procedures for the neutron gauging inspection works

Quantitative Inspection of Remanence of Broken Wire Rope Based on Compressed Sensing.

Science.gov (United States)

Zhang, Juwei; Tan, Xiaojiang

2016-08-25

Most traditional strong magnetic inspection equipment has disadvantages such as big excitation devices, high weight, low detection precision, and inconvenient operation. This paper presents the design of a giant magneto-resistance (GMR) sensor array collection system. The remanence signal is collected to acquire two-dimensional magnetic flux leakage (MFL) data on the surface of wire ropes. Through the use of compressed sensing wavelet filtering (CSWF), the image expression of wire ropes MFL on the surface was obtained. Then this was taken as the input of the designed back propagation (BP) neural network to extract three kinds of MFL image geometry features and seven invariant moments of defect images. Good results were obtained. The experimental results show that nondestructive inspection through the use of remanence has higher accuracy and reliability compared with traditional inspection devices, along with smaller volume, lighter weight and higher precision.

A conceptual design of the set-up for solid state spectroscopy with free electron laser and insertion device radiation

CERN Document Server

Makhov, V N

2001-01-01

The set-up for complex solid state spectroscopy with the use of enhanced properties of radiation from insertion devices and free electron lasers is proposed. Very high flux and pulsed properties of radiation from insertion devices and free electron lasers offer the possibility for the use of such powerful techniques as electron paramagnetic resonance (EPR) and optically detected magnetic resonance (ODMR) for the studies of excited states of electronic excitations or defects in solids. The power density of radiation can become high enough for one more method of exited-state spectroscopy: transient optical absorption spectroscopy. The set-up is supposed to combine the EPR/ODMR spectrometer, i.e. cryostat supplied with superconducting magnet and microwave system, and the optical channels for excitation (by radiation from insertion devices or free electron laser) and detection of luminescence (i.e. primary and secondary monochromators). The set-up can be used both for 'conventional' spectroscopy of solids (reflec...

Equipment for fully automatic radiographic pipe inspection

International Nuclear Information System (INIS)

Basler, G.; Sperl, H.; Weinschenk, K.

1977-01-01

The patent describes a device for fully automatic radiographic testing of large pipes with longitudinal welds. Furthermore the invention enables automatic marking of films in radiographic inspection with regard to a ticketing of the test piece and of that part of it where testing took place. (RW) [de

Development of a light weighted mobile robot for SG tube inspection in NPP

International Nuclear Information System (INIS)

Seo, Yong Chil; Jeong, Kyung Min; Shin, Hochul; Gweng, Jung Ju; Lee, Sung Uk; Jeong, Seung Ho; Choi, Young Soo; Kim, Seung Ho; Shin, Chun Sup; Park, Ki Tae

2012-01-01

Steam generators (SG) are among the most critical components of pressurized water Nuclear Power Plants (NPP). SG tubes must provide a reliable pressure boundary between the primary and secondary cooling water, because any leakage from tube defects could result in the release of radioactivity to the environment. Thus degradations of steam generators tubes should be monitored and inspected periodically under nuclear regulation. In service inspections of SG tubes are carried out using eddy current test (ECT) and the defected tubes are usually plugged. Because the radioactivity in the internal SG chambers limits free access of human workers, remote manipulators are required. In South Korea, Manipulators such as the Zet ec SM series and the Westinghouse ROSA series have bee used. Such manipulators are rigidly mounted to man ways or tube sheets of SG. Confusions of the inspected tubes may occur from deflection of the manipulators. To reduce the deflections of the manipulators for covering the large working areas of tube sheets, sufficient rigidity is required and that leads to an increase of the weight. Such weight increase results in some difficulties for handling and more radiation exposure of human workers. Recently light weighed mobile robots have been introduced by Westinghouse and Zet ec. The robots can move keeping in contact with the tube sheets using devices which are commonly called cam locks. They are easier to handle and provide no confusion for the position of the inspected tubes. But when the clamping forces are loosed accidentally, they can be fall down and light repair works can be performed. This paper provides the design results for a lightweight mobile robot which is being developed in cooperation of our institutes

Development of a light weighted mobile robot for SG tube inspection in NPP

Energy Technology Data Exchange (ETDEWEB)

Seo, Yong Chil; Jeong, Kyung Min; Shin, Hochul; Gweng, Jung Ju; Lee, Sung Uk; Jeong, Seung Ho; Choi, Young Soo; Kim, Seung Ho [KAERI, Daejeon (Korea, Republic of); Shin, Chun Sup; Park, Ki Tae [Korea Plant Service and Engineering, Busan (Korea, Republic of)

2012-10-15

Steam generators (SG) are among the most critical components of pressurized water Nuclear Power Plants (NPP). SG tubes must provide a reliable pressure boundary between the primary and secondary cooling water, because any leakage from tube defects could result in the release of radioactivity to the environment. Thus degradations of steam generators tubes should be monitored and inspected periodically under nuclear regulation. In service inspections of SG tubes are carried out using eddy current test (ECT) and the defected tubes are usually plugged. Because the radioactivity in the internal SG chambers limits free access of human workers, remote manipulators are required. In South Korea, Manipulators such as the Zet ec SM series and the Westinghouse ROSA series have bee used. Such manipulators are rigidly mounted to man ways or tube sheets of SG. Confusions of the inspected tubes may occur from deflection of the manipulators. To reduce the deflections of the manipulators for covering the large working areas of tube sheets, sufficient rigidity is required and that leads to an increase of the weight. Such weight increase results in some difficulties for handling and more radiation exposure of human workers. Recently light weighed mobile robots have been introduced by Westinghouse and Zet ec. The robots can move keeping in contact with the tube sheets using devices which are commonly called cam locks. They are easier to handle and provide no confusion for the position of the inspected tubes. But when the clamping forces are loosed accidentally, they can be fall down and light repair works can be performed. This paper provides the design results for a lightweight mobile robot which is being developed in cooperation of our institutes.

Remote Inspection, Measurement and Handling for LHC

CERN Document Server

Kershaw, K; Coin, A; Delsaux, F; Feniet, T; Grenard, J L; Valbuena, R

2007-01-01

Personnel access to the LHC tunnel will be restricted to varying extents during the life of the machine due to radiation, cryogenic and pressure hazards. The ability to carry out visual inspection, measurement and handling activities remotely during periods when the LHC tunnel is potentially hazardous offers advantages in terms of safety, accelerator down time, and costs. The first applications identified were remote measurement of radiation levels at the start of shut-down, remote geometrical survey measurements in the collimation regions, and remote visual inspection during pressure testing and initial machine cool-down. In addition, for remote handling operations, it will be necessary to be able to transmit several real-time video images from the tunnel to the control room. The paper describes the design, development and use of a remotely controlled vehicle to demonstrate the feasibility of meeting the above requirements in the LHC tunnel. Design choices are explained along with operating experience to-dat...

Risk-based inspection in the context of nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Soares, Wellington A.; Vasconcelos, Vanderley de; Rabello, Emerson G., E-mail: soaresw@cdtn.br, E-mail: vasconv@cdtn.br, E-mail: egr@cdtn.br [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

2015-07-01

Nuclear power plant owners have to consider several aspects like safety, availability, costs and radiation exposure during operation of nuclear power plants. They also need to demonstrate to regulatory bodies that risk assessment and inspection planning processes are being implemented in effective and appropriate manner. Risk-Based Inspection (RBI) is a methodology that, unlike time-based inspection, involves a quantitative assessment of both failure probability and consequence associated with each safety-related item. A correctly implemented RBI program classifies individual equipment by its risks and prioritizes inspection efforts based on this classification. While in traditional deterministic approach, the inspection frequencies are constant, in the RBI approach the inspection interval for each item depends on the risk level. Regularly, inspection intervals from RBI result in risk levels lower or equal than deterministic inspection intervals. According to the literature, RBI solutions improve integrity and reduce costs through a more effective inspection. Risk-Informed In-service Inspection (RI-ISI) is the equivalent term used in the nuclear area. Its use in nuclear power plants around world is briefly reviewed in this paper. Identification of practice methodologies for performing risk-based analyses presented in this paper can help both Brazilian nuclear power plant operator and regulatory body in evaluating the RI-ISI technique feasibility as a tool for optimizing inspections within nuclear plants. (author)

Risk-based inspection in the context of nuclear power plants

International Nuclear Information System (INIS)

Soares, Wellington A.; Vasconcelos, Vanderley de; Rabello, Emerson G.

2015-01-01

Nuclear power plant owners have to consider several aspects like safety, availability, costs and radiation exposure during operation of nuclear power plants. They also need to demonstrate to regulatory bodies that risk assessment and inspection planning processes are being implemented in effective and appropriate manner. Risk-Based Inspection (RBI) is a methodology that, unlike time-based inspection, involves a quantitative assessment of both failure probability and consequence associated with each safety-related item. A correctly implemented RBI program classifies individual equipment by its risks and prioritizes inspection efforts based on this classification. While in traditional deterministic approach, the inspection frequencies are constant, in the RBI approach the inspection interval for each item depends on the risk level. Regularly, inspection intervals from RBI result in risk levels lower or equal than deterministic inspection intervals. According to the literature, RBI solutions improve integrity and reduce costs through a more effective inspection. Risk-Informed In-service Inspection (RI-ISI) is the equivalent term used in the nuclear area. Its use in nuclear power plants around world is briefly reviewed in this paper. Identification of practice methodologies for performing risk-based analyses presented in this paper can help both Brazilian nuclear power plant operator and regulatory body in evaluating the RI-ISI technique feasibility as a tool for optimizing inspections within nuclear plants. (author)

WE-D-BRE-01: A Sr-90 Irradiation Device for the Study of Cutaneous Radiation Injury

Energy Technology Data Exchange (ETDEWEB)

Dorand, JE; Bourland, JD [Department of Radiation Oncology and Department of Physics, Wake Forest University, Winston-Salem, NC (United States); Burnett, LR [KeraNetics, LLC, Winston-Salem, NC (United States); Tytell, M [Department of Neurobiology and Anatomy, Wake Forest School of Medicine, Winston-Salem, NC (United States)

2014-06-15

Purpose: To determine dosimetric character for a custom-built Sr-90 beta irradiator designed for the study of Cutaneous Radiation Injury (CRI) in a porcine animal model. In the event of a radiological accident or terrorist event, Sr-90, a fission by-product, will likely be produced. CRI is a main concern due to the low energy and superficial penetration in tissue of beta particles from Sr-90. Seven 100 mCi plaque Sr-90 radiation sources within a custom-built irradiation device create a 40 mm diameter region of radiation-induced skin injury as part of a larger project to study the efficacy of a topical keratin-based product in CRI healing. Methods: A custom-built mobile irradiation device was designed and implemented for in vivo irradiations. Gafchromic™ EBT3 radiochromic film and a PTW Markus chamber type 23343 were utilized for dosimetric characterization of the beta fluence at the surface produced by this device. Films were used to assess 2-dimensional dose distribution and percent depth dose characteristics of the radiation field. Ion chamber measurements provided dose rate data within the field. Results: The radiation field produced by the irradiation device is homogeneous with high uniformity (∼5%) and symmetry (∼3%) with a steep dose fall-off with depth from the surface. Dose rates were determined to be 3.8 Gy/min and 3.3 Gy/min for film and ion chamber measurements, respectively. A dose rate of 3.4 Gy/min was used to calculate irradiation times for in vivo irradiations. Conclusion: The custom-built irradiation device enables the use of seven Sr-90 beta sources in an array to deliver a 40 mm diameter area of homogeneous skin dose with a dose rate that is useful for research purposes and clinically relevant for the induction of CRI. Doses of 36 and 42 Gy successfully produce Grade III CRI and are used in the study of the efficacy of KeraStat™. This project has been funded in whole or in part with Federal funds from the Biomedical Advanced Research and

Development of NDT techniques for the inspection of WSGHWR pressure tubes

International Nuclear Information System (INIS)

Gray, B.S.; Highmore, P.J.; Rudlin, J.R.; Cooper, A.G.

1979-01-01

The fuel for the Steam Generating Heavy Water Reactor at Winfrith Heath is contained in vertical Zircaloy pressure tubes and is cooled by boiling light water. This paper describes the development of NDT techniques for the inservice examination of the pressure tubes to provide continuing assurance of the absence of axial crack-like defects. The resultant equipment has to operate in water-filled tubes in the presence of the radiation field due to the irradiated fuel elements in adjacent tubes. Also, a layer of surface oxide on the inside of the tubes has been found to significantly affect the behaviour of a prototype inspection device. To provide adequate sensitivity in these conditions, without the occurrence of unnecessary spurious indications, a combination of techniques has been developed. This involves the use of ultrasonics in both pulse-echo and 'pitch and catch' mode together with a single frequency eddy current technique. Laboratory work using artificial defects is described and also how the development programme was modified to accommodate the results of in-reactor tests using a prototype device. Reference is also made to the development of CCTV equipment to provide a supplementary visual examination. (author)

9 CFR 381.204 - Marking of poultry products offered for entry; official import inspection marks and devices.

Science.gov (United States)

2010-01-01

... Products FOOD SAFETY AND INSPECTION SERVICE, DEPARTMENT OF AGRICULTURE AGENCY ORGANIZATION AND TERMINOLOGY; MANDATORY MEAT AND POULTRY PRODUCTS INSPECTION AND VOLUNTARY INSPECTION AND CERTIFICATION POULTRY PRODUCTS... 9 Animals and Animal Products 2 2010-01-01 2010-01-01 false Marking of poultry products offered...

Development of In-situation radioactivity Inspection system

International Nuclear Information System (INIS)

Min, Sujung; Lee, Sanghun; Kim, Miyoung; Kim, Myungjin; Lee, Unjang; Park, Jungkyun

2015-01-01

Many Korean people worry about radioactive contamination of Japanese and Korean marine products. Radioactive contamination of processed foodstuffs, livestock, marine products, farm products imported from Japan and fishes caught in coastal waters of Korea has become an important social issue. Radioactivity inspections of those foods are executed manually with portable measuring instruments or at labs using their samples. In consequence, there are some problem of time delay and low reliability. To protect the health of citizens from radioactivity contained in Japanese marine products imported to Korea, a system to inspect radioactivity in real time will be developed. The system is to measure the radioactivity level of farm and marine products continuously and automatically at inspection sites of an agency checking radiation of imported foodstuffs to determine radioactive contamination. Product performance assessment and tests will be conducted later. When the system develops and its commercialization begins, people's anxiety about radioactive contamination of foods after the Fukushima nuclear accident will be eased and people will be able to trust the radioactive inspection

Development of In-situation radioactivity Inspection system

Energy Technology Data Exchange (ETDEWEB)

Min, Sujung; Lee, Sanghun; Kim, Miyoung; Kim, Myungjin; Lee, Unjang [ORIONENC Co., Seoul (Korea, Republic of); Park, Jungkyun [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2015-05-15

Many Korean people worry about radioactive contamination of Japanese and Korean marine products. Radioactive contamination of processed foodstuffs, livestock, marine products, farm products imported from Japan and fishes caught in coastal waters of Korea has become an important social issue. Radioactivity inspections of those foods are executed manually with portable measuring instruments or at labs using their samples. In consequence, there are some problem of time delay and low reliability. To protect the health of citizens from radioactivity contained in Japanese marine products imported to Korea, a system to inspect radioactivity in real time will be developed. The system is to measure the radioactivity level of farm and marine products continuously and automatically at inspection sites of an agency checking radiation of imported foodstuffs to determine radioactive contamination. Product performance assessment and tests will be conducted later. When the system develops and its commercialization begins, people's anxiety about radioactive contamination of foods after the Fukushima nuclear accident will be eased and people will be able to trust the radioactive inspection.

Nuclear data needs for non-intrusive inspection

International Nuclear Information System (INIS)

Smith, D. L.; Michlich, B. J.

2000-01-01

Various nuclear-based techniques are being explored for use in non-intrusive inspection. Their development is motivated by the need to prevent the proliferation of nuclear weapons, to thwart trafficking in illicit narcotics, to stop the transport of explosives by terrorist organizations, to characterize nuclear waste, and to deal with various other societal concerns. Non-intrusive methods are sought in order to optimize inspection speed, to minimize damage to packages and containers, to satisfy environmental, health and safety requirements, to adhere to legal requirements, and to avoid inconveniencing the innocent. These inspection techniques can be grouped into two major categories: active and passive. They almost always require the use of highly penetrating radiation and therefore are generally limited to neutrons and gamma rays. Although x-rays are widely employed for these purposes, their use does not constitute nuclear technology and therefore is not discussed here. This paper examines briefly the basic concepts associated with nuclear inspection and investigates the related nuclear data needs. These needs are illustrated by considering four of the methods currently being developed and tested

Nuclear data needs for non-intrusive inspection

International Nuclear Information System (INIS)

Smith, D.L.; Micklich, B.J.

2001-01-01

Various nuclear-based techniques are being explored for use in non-intrusive inspection. Their development is motivated by the need to prevent the proliferation of nuclear weapons, to thwart trafficking in illicit narcotics, to stop the transport of explosives by terrorist organizations, to characterize nuclear waste, and to deal with various other societal concerns. Non-intrusive methods are sought in order to optimize inspection speed, to minimize damage to packages and containers, to satisfy environmental, health and safety requirements, to adhere to legal requirements, and to avoid inconveniencing the innocent. These inspection techniques can be grouped into two major categories: active and passive. They almost always require the use of highly penetrating radiation and therefore are generally limited to neutrons and gamma rays. Although x-rays are widely employed for these purposes, their use does not constitute 'nuclear technology' and therefore is not discussed here. This paper examines briefly the basic concepts associated with nuclear inspection and investigates the related nuclear data needs. These needs are illustrated by considering four of the methods currently being developed and tested. (author)

The MCNP simulation of the X-ray leakage of X-ray security inspection equipment

International Nuclear Information System (INIS)

Wang Kai; Liu Bin; Hu Wenchao; Zhao Wei

2011-01-01

Objective: To simulate the radiation leakage of the X-ray security inspection equipment used in the subways stations. Methods: We use the MCNP4C code to simulate the X-ray leakage of the equipment during the working process. Result: the biggest amount of radiation received by the body is 8.26 μSv/a, however, if the Lead screens of the X-ray security equipment is intact, the amount of radiation received by the body is only 0.0727 μSv/a. The final. Conclusions: When the baggage get in /out the X-ray security inspection equipment, the gas in Lead screens was made, and then the amount of radiation received by human body increased; The amount of radiation received by the body is close to but still below 10 μSv/a which is the exemption criteria set by the 'safety of radiation sources of ionizing radiation protection and basic standards'(GB18871-2002). (authors)

Report by the work-group on 'safety of medical devices emitting ionizing radiations'. Articulation of radiation protection requirements of the 97/43/Euratom directive and IAEA recommendations with the essential requirements of the 93/42/CEE directive related to medical devices used in external radiotherapy

International Nuclear Information System (INIS)

2010-01-01

As some dysfunctions and events had been reported in 2007 and 2008 in field of radiotherapy, this report aims at clarifying the articulation between the different European regulations concerning medical devices emitting ionizing radiations and radiation protection. The authors report a survey with device manufacturers, and analyze the content of the different regulations and recommendations. Then, the authors recommend and propose a set of actions related to the IAEA requirements and recommendations, to CE marking requirements, and to new radiation protection and safety requirements present in the Euratom directive

A mobile robot for remote inspection of radioactive waste

International Nuclear Information System (INIS)

Suh, Y. C.; Kim, C. H.; Cho, J. W.; Choi, Y. S.; Kim, S. H.

2004-01-01

Tele-operation and remote monitoring techniques are essential and important technologies for the inspection and maintenance of the radioactive waste. A mobile robot has been developed for the application of remote monitoring and inspection of nuclear facilities, where human access is limited because of the high-level radioactive environments. The mobile robot was designed with reconfigurable crawler type of wheels attached on the front and rear side in order to pass through the ditch. The extendable mast, mounted on the mobile robot, car be extended up to 8 m vertically. The robust controller for radiation is designed in focus on electric components to prevent abnormal operation in a highly radioactivated area during reactor operation. This robot system will enhance the reliability of nuclear power facilities, and cope with the unexpected radiation accident

Radiation-induced interface state generation in MOS devices with reoxidised nitrided SiO2 gate dielectrics

International Nuclear Information System (INIS)

Lo, G.Q.; Shih, D.K.; Ting, W.; Kwong, D.L.

1989-01-01

In this letter, the radiation-induced interface state generation ΔD it in MOS devices with reoxidised nitrided gate oxides has been studied. The reoxidised nitrided oxides were fabricated by rapid thermal reoxidation (RTO) of rapidly thermal nitrided (RTN) SiO 2 . The devices were irradiated by exposure to X-rays at doses of 0.5-5.0 Mrad (Si). It is found that the RTO process improves the radiation hardness of RTN oxides in terms of interface state generation. The enhanced interface ''hardness'' of reoxidised nitrided oxides is attributed to the strainless interfacial oxide regrowth or reduction of hydrogen concentration during RTO of RTN oxides. (author)

Radiation Practices. Annual Report 2005

International Nuclear Information System (INIS)

Rantanen, E.

2006-06-01

1764 safety licences for the use of radiation were current at the end of 2005. 1907 responsible parties were engaged in notifiable licence-exempt dental X-ray practices. Regulatory control of the use of radiation was performed through regular inspections performed at places of use, test packages sent by post to dental X-ray facilities and maintenance of the Dose Register. Radiation safety guides were also published and research was conducted in support of regulatory control. STUK conducted 458 inspections of licensed practices and 62 inspections of notifiable licence-exempt dental X-ray practices in 2005. 273 remedial orders and recommendations were issued. Use of one appliance was prohibited. A total of 11 698 workers engaged in radiation work were subject to individual monitoring in 2005. 137 000 dose entries were made in the Dose Register. In no case did the individual dose of any worker exceed the dose limits stipulated in the Radiation Decree. Regulatory control of natural radiation focused on radon at workplaces and exposure of aircrews to cosmic radiation. 90 workplaces including a total of 233 work areas were subject to radon monitoring during 2005. 2600 pilots and cabin crew members were monitored for exposure to cosmic radiation. Metrological activities continued with calibration and development work as in previous years. Regulatory control of the use of non-ionizing radiation in 2005 continued to focus particularly on mobile phones and sunbeds. 15 mobile phone types were tested in market surveillance of mobile phones. A total of 44 sunbed appliances were inspected at 36 sunbed facilities. Most research and development work took place within jointly financed research projects. This work focused especially on developing testing and measuring methods for determining exposure to electromagnetic fields caused by mobile phones and their base stations. There were 13 abnormal incidents involving the use of radiation in 2005. Eight of these incidents concerned

Quantitative Inspection of Remanence of Broken Wire Rope Based on Compressed Sensing

Science.gov (United States)

Zhang, Juwei; Tan, Xiaojiang

2016-01-01

Most traditional strong magnetic inspection equipment has disadvantages such as big excitation devices, high weight, low detection precision, and inconvenient operation. This paper presents the design of a giant magneto-resistance (GMR) sensor array collection system. The remanence signal is collected to acquire two-dimensional magnetic flux leakage (MFL) data on the surface of wire ropes. Through the use of compressed sensing wavelet filtering (CSWF), the image expression of wire ropes MFL on the surface was obtained. Then this was taken as the input of the designed back propagation (BP) neural network to extract three kinds of MFL image geometry features and seven invariant moments of defect images. Good results were obtained. The experimental results show that nondestructive inspection through the use of remanence has higher accuracy and reliability compared with traditional inspection devices, along with smaller volume, lighter weight and higher precision. PMID:27571077

Quantitative Inspection of Remanence of Broken Wire Rope Based on Compressed Sensing

Directory of Open Access Journals (Sweden)

Juwei Zhang

2016-08-01

Full Text Available Most traditional strong magnetic inspection equipment has disadvantages such as big excitation devices, high weight, low detection precision, and inconvenient operation. This paper presents the design of a giant magneto-resistance (GMR sensor array collection system. The remanence signal is collected to acquire two-dimensional magnetic flux leakage (MFL data on the surface of wire ropes. Through the use of compressed sensing wavelet filtering (CSWF, the image expression of wire ropes MFL on the surface was obtained. Then this was taken as the input of the designed back propagation (BP neural network to extract three kinds of MFL image geometry features and seven invariant moments of defect images. Good results were obtained. The experimental results show that nondestructive inspection through the use of remanence has higher accuracy and reliability compared with traditional inspection devices, along with smaller volume, lighter weight and higher precision.

Improvements in or relating to the inspection of underwater structures

International Nuclear Information System (INIS)

Caldecourt, L.R.; Evans, G.V.; Parsons, T.V.

1980-01-01

A radiation detector is described, for use in the inspection of underwater structures, which is capable of withstanding high pressures and arduous marine conditions. The ingress of water into the body of the radiation detector tube is prevented by the use of a resilient waterproof compound. Marine structures incorporating such radiation detectors are described, whereby the presence or density of flowing cement grout in the legs of an offshore platform may be determined. (U.K.)

Filter and window assemblies for high power insertion device synchrotron radiation sources

International Nuclear Information System (INIS)

Khounsary, A.M.; Viccaro, P.J.; Kuzay, T.M.

1992-01-01

The powerful beams of x-ray radiation generated by insertion devices at high power synchrotron facilities deposit substantial amounts of localized heat in the front end and optical components that they intercept. X-ray beams from undulator sources, in particular, are confined to very narrow solid angles and therefore impose very high absorbed heat fluxes. This paper is devoted to a detailed study of the design of windows for the Advanced Photon Source undulators and wigglers, emphasizing alternative design concepts, material considerations, and cooling techniques necessary for handling the high heat load of the insertion devices. Various designs are thermally and structurally analyzed by numerically simulating full-power operating conditions. This analysis also has relevance to the design and development of other beam line components which are subjected to the high heat loads of insertion devices

Structural assessment procedure of corroding submarine gas pipelines using on-line inspection data

International Nuclear Information System (INIS)

Nordin Yahaya

2000-01-01

This paper presents 'the alternative approach of overall procedure in the assessment of corroded pipelines using data gathered by the on-line inspection device. The methodology adopts a generalised approach of analysing pipeline inspection data and a prediction of the structural reliability due to the deteriorating corrosion environment. The whole assessment methodology is divided into four separate stages; 1 to IV. Stages 1 and 11 are the initial procedure prior to the actual analysis of the inspection data. The scope of this paper is concerted into the procedure to be taken in Stage 111 where the stage is sub-divided into 3 major steps; Part A, B and C. These procedures are Part A (statistical and probabilistic analysis of the inspection data) and Part B (the application of extreme value statistics) and C (reliability assessment). Stage IV (risk assessment) is the final step in the procedure where the consequences of failure are evaluated. The proposed risk-based assessment procedure is more systematic and reliable to account for a huge amount of collected data usually obtained in an on-line inspection using the intelligent devices. The outcomes of this risk-based methodology can be very useful in the decision-making process by the operation management. This in turn will produce an efficient inspection, repair and maintenance program and enhanced the optimised return in investment. (author)

Searching for Orphan radiation sources

International Nuclear Information System (INIS)

Bystrov, Evgenij; Antonau, Uladzimir; Gurinovich, Uladzimir; Kazhamiakin, Valery; Petrov, Vitaly; Shulhovich, Heorhi; Tischenko, Siarhei

2008-01-01

Full text: The problem of orphan sources cannot be left unaddressed due high probability of accidental exposure and use of sources for terrorism. Search of objects of this kind is complex particularly when search territory is large. This requires devices capable of detecting sources, identifying their radionuclide composition, and correlating scan results to geographical coordinates and displaying results on a map. Spectral radiation scanner AT6101C can fulfill the objective of search for gamma and neutron radiation sources, radionuclide composition identification, correlation results to geographical coordinates and displaying results on a map. The scanner consists of gamma radiation scintillation detection unit based on NaI(Tl) crystal, neutron detection unit based on two He 3 counters, GPS receiver and portable ruggedized computer. Built-in and application software automates entire scan process, saving all results to memory for further analysis with visual representation of results as spectral information diagrams, count rate profile and gamma radiation dose rates on a geographical map. The scanner informs operator with voice messages on detection of radiation sources, identification result and other events. Scanner detection units and accessories are packed in a backpack. Weighing 7 kg, the scanner is human portable and can be used for scan inside cars. The scanner can also be used for radiation mapping and inspections. (author)

Remote visual testing (RVT) for the diagnostic inspection of feedwater heaters

International Nuclear Information System (INIS)

Nugent, M.J.; Pellegrino, B.A.

1991-01-01

In this paper the benefits and limitations of Non-Destructive Testing (NDT) on feedwater heaters will be briefly reviewed. All Remote Visual Testing (RVT) devices including borescopes, fiberscopes, videoborescopes and Closed Circuit Television (CCTV) cameras will be discussed along with currently accepted formats for documentation. The benefits of a comprehensive in-place inspection involving Remote Visual Testing will be discussed in relationship to its diagnostic capabilities. The results of eight post-service heater inspections will be discussed along with the root cause of failure of seven unique failure mechanisms. These inspections, including FWH access, RVT tool and data analysis, will be detailed

Total-dose radiation effects data for semiconductor devices. 1985 supplement. Volume 2, part A

International Nuclear Information System (INIS)

Martin, K.E.; Gauthier, M.K.; Coss, J.R.; Dantas, A.R.V.; Price, W.E.

1986-05-01

Steady-state, total-dose radiation test data, are provided in graphic format for use by electronic designers and other personnel using semiconductor devices in a radiation environment. The data were generated by JPL for various NASA space programs. This volume provides data on integrated circuits. The data are presented in graphic, tabular, and/or narrative format, depending on the complexity of the integrated circuit. Most tests were done using the JPL or Boeing electron accelerator (Dynamitron) which provides a steady-state 2.5 MeV electron beam. However, some radiation exposures were made with a cobalt-60 gamma ray source, the results of which should be regarded as only an approximate measure of the radiation damage that would be incurred by an equivalent electron dose

10 CFR 36.61 - Inspection and maintenance.

Science.gov (United States)

2010-01-01

... emergency source return control required by § 36.31(c). (7) Leak-tightness of systems through which pool water circulates (visual inspection). (8) Operability of the heat and smoke detectors and extinguisher... for radioactive contamination in pool water required by § 36.59(b) using a radiation check source, if...

Inspection and repair of steam generator tubing with a robot

International Nuclear Information System (INIS)

Boehm, H.H.; Foerch, H.

1985-01-01

During inspection and repair of steam generator tubing, radiation exposure to personnel is an unrequested endowment. To combat this intrinsic handicap, a robot has been designed for deployment in all operations inside the steam generator water chamber. This measure drastically reduces entering time and also improves inspection capabilities with regard to the accuracy and reproduction of the desired tube address. The inherent flexibility of the robot allows for performing various inspection and repair techniques: eddy-current testing of tubing; ultrasonic testing of tubing; visual examination of tube ends; profilometry measurements; tube plugging; plug removal; tube extraction; sleeving of tubes; tube end repair; chemical cleaning; and thermal treatment. Plant experience has highlighted the following features of the robot: 1) short installation and demounting periods; 2) installation independent of manhole location; 3) installation possible from outside the steam generator; 4) only one relocation required to address all the tube positions; 5) fast and highly accurate positioning; 6) operational surveillance not required; and 7) drastic reduction of radiation exposure to personnel during repair work

Theoretic simulation for CMOS device on total dose radiation response

International Nuclear Information System (INIS)

He Baoping; Zhou Heqin; Guo Hongxia; He Chaohui; Zhou Hui; Luo Yinhong; Zhang Fengqi

2006-01-01

Total dose effect is simulated for C4007B, CC4007RH and CC4011 devices at different absorbed dose rate by using linear system theory. When irradiation response and dose are linear, total dose radiation and post-irradiation annealing at room temperature are determined for one random by choosing absorbed dose rate, and total dose effect at other absorbed dose rate can be predicted by using linear system theory. The simulating results agree with the experimental results at different absorbed dose rate. (authors)

Radiological protection requirements applicable to non-invasive inspection of charges with ionizing radiation; Requisitos de proteção radiológica aplicáveis em inspeção não invasiva de cargas com radiação ionizante

Energy Technology Data Exchange (ETDEWEB)

Crespo, S.C.; Palmieri, J.A.S. [Faculdade Casa Branca, SP (Brazil). Pós-Graduação de Proteção Radiológica em Aplicações Médicas, Industriais e Nucleares; Lima, C.M.A. [MAXIM Cursos, Rio de Janeiro, RJ (Brazil); Silva, F.C.A. da, E-mail: franciscodasilva13uk@gmail.com [Instituto de Radioproteção e Dosimetria (IRD/CNEN-RJ), Rio de Janeiro, RJ (Brazil)

2017-07-01

The US twin towers attack in 2001 raised concerns about terrorism, illicit trafficking of materials and the possible use of a 'dirty bomb' (DDR), affecting the control of entry and exit of products. Thus, the use of ionizing radiation scanning systems of containers at ports and borders was started to investigate possible entries of illegal material. Brazil, adhering to this concern and due to the holding of major events such as RIO + 20, World Cup, Olympics, etc., increased safety in the movement of goods using non-invasive inspection. Linear electron accelerators, which produce high energy X-rays in the range of 1.5 to 9 MeV, are used to inspect the containers. Since in Brazil there is no specific technical regulation for the operation of non-invasive inspection equipment with X-rays and linear accelerators, ten main technical requirements are presented. It is essential that a technical regulation is drawn up by placing the system of non-invasive inspection of cargo with ionizing radiation in the international radiation protection standard.

Remote repair and inspection technics in Tokai reprocessing plant

International Nuclear Information System (INIS)

Koyama, Kenji; Ishibashi, Yuzo; Otani, Yosikuni

1986-01-01

Tokai reprocessing plant of Power Reactor and Nuclear Fuel Development Corp. is the only factory in Japan which treats 0.7 t/day of the spent fuel from LWR power stations and recovers remaining uranium and newly produced plutonium. Since the reprocessing plant started the hot test in September, 1977, about eight years have elapsed, and 233 t of spent fuel was treated as of August, 1985. During this period, the development of various remote working techniques have been carried out to cope with the failure of equipment and to strengthen the preventive maintenance of equipment. In this report, the development of the techniques for the remote repair of leaking dissolving tanks and the development of the remote inspection system for confirming the soundness of equipment in cells are described. In nuclear facilities, from the viewpoint of the reduction of radiation exposure accompanying the works under high radiation, labor saving, the increase of capacity factor by shortening the period of repair works, the improvement of safety and reliability of the facilities by perfecting checkup and inspection and so on, it is strongly desired to put robots in practical use for maintenance and inspection. (Kako, I.)

Development of the mobile manipulator for inspection and maintenance in nuclear power plants and application of the modul devices

International Nuclear Information System (INIS)

Ohmichi, Takeo; Hosaka, Shigetaka; Nishihara, Masatoshi; Nakayama, Junji; Sato, Masatoshi

1986-01-01

In nuclear power stations, remote operation devices have been positively developed and applied, thus largely contributed to the reduction of the radiation exposure of workers. However, when requirements are diversified, the number of devices increases, and their management becomes complicated. The largest obstacle to the adaption of versatile robots in nuclear power stations is the environmental condition, and the small size for narrow space and the capability to withstand severe temperature, humidity and radiation must be ensured with high reliability. Mitsubishi Heavy Industries, Ltd. carried out the development of the manipulator for light works, which takes early counter-measures to the abnormality during operation, for five years as the subsidized project by the Ministry of International Trade and Industry. This robot is composed of a slave robot working in vessels and the central control system. The slave robot comprises a modular manipulator arm, the slave controller, a running carriage and the three-dimensional visual system. The components of the central control system are connected with optical fibers. The features and function and applicability of this manipulator are described. (Kako, I.)

Risk-Informed Decisions Optimization in Inspection and Maintenance

International Nuclear Information System (INIS)

Robertas Alzbutas

2002-01-01

The Risk-Informed Approach (RIA) used to support decisions related to inspection and maintenance program is considered. The use of risk-informed methods can help focus the adequate in-service inspections and control on the more important locations of complex dynamic systems. The focus is set on the highest risk measured as conditional core damage frequency, which is produced by the frequencies of degradation and final failure at different locations combined with the conditional failure consequence probability. The probabilities of different degradation states per year and consequences are estimated quantitatively. The investigation of inspection and maintenance process is presented as the combination of deterministic and probabilistic analysis based on general risk-informed model, which includes the inspection and maintenance program features. Such RIA allows an optimization of inspection program while maintaining probabilistic and fundamental deterministic safety requirements. The failure statistics analysis is used as well as the evaluation of reliability of inspections. The assumptions regarding the effectiveness of the inspection methods are based on a classification of the accessibility of the welds during the inspection and on the different techniques used for inspection. The probability of defect detection is assumed to depend on the parameters either through logarithmic or logit transformation. As example the modeling of the pipe systems inspection process is analyzed. The means to reduce a number of inspection sites and the cumulative radiation exposure to the NPP inspection personnel with a reduction of overall risk is presented together with used and developed software. The developed software can perform and administrate all the risk evaluations and ensure the possibilities to compare different options and perform sensitivity analysis. The approaches to define an acceptable level of risk are discussed. These approaches with appropriate software in

Rules on the Inspection of Gamma Radiography Equipment

International Nuclear Information System (INIS)

1981-01-01

These Rules issued by the State Institute of Radiation Hygiene (SIS) set out the obligations of licences and vendors of gamma radiography equipment for purposes of quality control. The Rules provide for a programme of periodic inspections and services by personnel approved by SIS. (NEA)

Radiation exposure dose on persons engaged in radiation-related industries in Korea

International Nuclear Information System (INIS)

Lim, Bong Sik

2006-01-01

This study investigated the status of radiation exposure doses since the establishment of the 'Regulations on Safety Management of Diagnostic Radiation Generation Device' in January 6, 1995. The level of radiation exposure in people engaged or having been engaged in radiation-related industries of inspection organizations, educational organization, military units, hospitals, public health centers, businesses, research organizations or clinics over a 5 year period from Jan. 1, 2000 to Dec. 31, 2004 was measured. The 149,205 measurement data of 57,136 workers registered in a measurement organization were analysed in this study. Frequency analysis, a Chi-square test, Chi-square trend test, and ANOVA was used for data analysis. Among 57,136 men were 40,870 (71.5%). 50.3% of them were radiologic technologists, otherwise medical doctors (22.7%), nurse (2.9%) and others (24.1%). The average of depth radiation and surface radiation during the 5-year period were found to decrease each year. Both the depth radiation and surface radiation exposure were significantly higher in males, in older age groups, in radiological technologists of occupation. The departments of nuclear medicine had the highest exposure of both depth and surface radiation of the divisions of labor. There were 1.98 and 2.57 per 1,000 person-year were exposed more than 20 mSv (limit recommended by International Commission on Radiological Protection) in depth and surface radiation consequently. The total exposure per worker was significantly decreased by year. But Careful awareness is needed for the workers who exposed over 20 mSv per year. In order to minimize exposure to radiation, each person engaged in a radiation-related industry must adhere to the individual safety management guidelines more thoroughly. In addition, systematic education and continuous guidance aimed at increasing the awareness of safety must be provided

Implantation of inspection and radiation protection plan

International Nuclear Information System (INIS)

Cunha, J.L.R. da

1988-01-01

Methods, means and procedures adopted by Petrobras engineering service to survey safety radiation protection of the companies that carry out radiographic services of PETROBRAS are showed. The systematic used in certification of personel, procedures, audits and field survey concerning radiation protection, are described. (C.M.) [pt

In-Line Acoustic Device Inspection of Leakage in Water Distribution Pipes Based on Wavelet and Neural Network

Directory of Open Access Journals (Sweden)

Dileep Kumar

2017-01-01