Proceedings of the Seminar 'Irradiation Technologies and the IRASM Facility'

International Nuclear Information System (INIS)

Ponta, Corneliu Catalin; Moise, Ioan Valentin

1999-01-01

The seminar devoted to 'Irradiation Technologies and the IRASM Facility' aimed at debating the principal problems related to one of the most important project ever developed in Romania, at the Horia Hulubei National Institute of Physics and Nuclear Engineering, in collaboration with IAEA. IRASM (an acronym for Multiple Purpose Irradiation Facility) is using initially a 60 Co of 100 kCi irradiation source (to be replaced after an promotional stage by a 2 MCi Co source). It is designed to irradiate a materials volume of about 35,000 m 3 /year. Health, agriculture, food industry and materials industry are the most targeted customers. It will be used for sterilization of medical materials and pharmaceuticals products, peat and seed (and other agricultural products) decontamination and sterilization, experimental irradiation of food products, irradiation of composite plastics and other industrial products, etc. The seminar was a first meeting of Romanian specialists in radiation processing with potential users of these technologies as well as with decision making persons working with national governmental and regulation authorities. Twelve communications were presented as a basis for discussion. These were: 1. IRASM - a technical assistance IAEA project and the prospects for technological irradiation in Romania (Serban Dobrescu); 2. IRASM facility - goal, present stage, perspectives (Corneliu C. Ponta); 3. Nuclear safeguards and radioprotection at IRASM (Ioan Valentin Moise); 4. Nuclear safeguard policy for IRASM (Mariana Irimia, Gabriela Vladescu, Ion Cristian); 5. Technological dosimetry at IRASM (Rodica Macrin, Rodica Moraru, Nicolae Valcov); 6. Quality assurance in building and exploiting IRASM (Ioana Domsa); 7. Current status of irradiation technologies in IFIN-HH (Mitica Dragusin); 8. Chemical-pharmaceutical, cosmetic and medical product sterilization (Paul Adrian, Eleonora Gheorghiu); 9. The concept of sterilization and the sterilization testing (Ileana Petcu

Facts about food irradiation: Safety of irradiation facilities

International Nuclear Information System (INIS)

1991-01-01

This fact sheet considers the safety of industrial irradiation facilities. Although there have been accidents, none of them has endangered public health or environmental safety, and the radiation processing industry is considered to have a very good safety record. Gamma irradiators do not produce radioactive waste, and the radiation sources at the facilities cannot explode nor in any other way release radioactivity into the environment. 3 refs

3. Standardization of food irradiation in developing countries

International Nuclear Information System (INIS)

Twum-Danso, L.

1981-01-01

The need is stressed for clearly defined guidelines and regulations for the consumption of irradiated foods and the operation of irradiation facilities. This requires the establishment of a responsible body. The example of Ghana is used as illustration. Food standards are mandatory. The Ghana Standards Board was established under NLC Decree 199, subsequently superseded by NRC Decree 173:1973 as amended by AFRC Decree 44:1977. The aims and functions of the Board are described, and forms in which its powers are operative. Two types of certificate are granted: the Certification Mark and the Exemption Certificate. The formulation of food standards is done through technical committees. The National Codex (Alimentarius) Committee is responsible for establishing food standards for Board approval. Membership of this committee is drawn from available expertise from industry, research institutions, government departments, the universities, etc. The various steps in the preparation of Codex Standards are outlined. For the certification of irradiated food in Ghana the international requirements as outlined by CXFA (Codex Committee on Food Additives) need to be met

International Facility for Food Irradiation Technology

International Nuclear Information System (INIS)

Farkas, J.

1982-01-01

The International Facility for Food Irradiation Technology (IFFIT) was set up in November 1978 for a period of five years at the Pilot Plant for Food Irradiation, Wageningen, The Netherlands under an Agreement between the FAO, IAEA and the Ministry of Agriculture and Fisheries of the Government of the Netherlands. Under this Agreement, the irradiation facilities, office space and services of the Pilot Plant for Food Irradiation are put at IFFIT's disposal. Also the closely located Research Foundation, ITAL, provides certain facilities and laboratory services within the terms of the Agreement. The FAO and IAEA contribute US-Dollar 25,000. Annually for the duration of IFFIT. (orig.) [de

Electron beam irradiation facility for low to high dose irradiation applications

International Nuclear Information System (INIS)

Petwal, V.C.; Wanmode, Yashwant; Verma, Vijay Pal; Bhisikar, Abhay; Dwivedi, Jishnu; Shrivastava, P.; Gupta, P.D.

2013-01-01

Electron beam based irradiation facilities are becoming more and more popular over the conventional irradiator facilities due to many inherent advantages such as tunability of beam energy, availability of radiation both in electron mode and X-ray mode, wide range of the dose rate, control of radiation from a ON-OFF switch and other safety related merits. A prototype experimental facility based on electron accelerator has been set-up at RRCAT to meet the low-dose, medium dose and high-dose requirements for radiation processing of food, agricultural and medical products. The facility can be operated in the energy range from 7-10 MeV at variable power level from 0.05-3 kW to meet the dose rate requirement of 100 Gy to kGy. The facility is also equipped with a Bremsstrahlung converter optimized for X-ray irradiation at 7.5 MV. Availability of dose delivery in wide range with precision control and measurement has made the facility an excellent tool for researchers interested in electron/X-ray beam irradiation. A precision dosimetry lab based on alanine EPR and radiochromic film dosimetry system have been established to characterize the radiation field and precise dose measurements. Electron beam scattering technique has been developed to achieve low dose requirement for EB irradiation of various seeds such as groundnut, wheat, soybeans, moong beans, black gram etc. for mutation related studies. This paper describes various features of the facility together with the dosimetric measurements carried out for qualification of the facility and recent irradiation experiments carried out using this facility. (author)

Monte Carlo simulations and dosimetric studies of an irradiation facility

Energy Technology Data Exchange (ETDEWEB)

Belchior, A. [Instituto Tecnologico e Nuclear, Estrada nacional no. 10, Apartado 21, 2686-953 Sacavem (Portugal)], E-mail: anabelchior@itn.pt; Botelho, M.L; Vaz, P. [Instituto Tecnologico e Nuclear, Estrada nacional no. 10, Apartado 21, 2686-953 Sacavem (Portugal)

2007-09-21

There is an increasing utilization of ionizing radiation for industrial applications. Additionally, the radiation technology offers a variety of advantages in areas, such as sterilization and food preservation. For these applications, dosimetric tests are of crucial importance in order to assess the dose distribution throughout the sample being irradiated. The use of Monte Carlo methods and computational tools in support of the assessment of the dose distributions in irradiation facilities can prove to be economically effective, representing savings in the utilization of dosemeters, among other benefits. One of the purposes of this study is the development of a Monte Carlo simulation, using a state-of-the-art computational tool-MCNPX-in order to determine the dose distribution inside an irradiation facility of Cobalt 60. This irradiation facility is currently in operation at the ITN campus and will feature an automation and robotics component, which will allow its remote utilization by an external user, under REEQ/996/BIO/2005 project. The detailed geometrical description of the irradiation facility has been implemented in MCNPX, which features an accurate and full simulation of the electron-photon processes involved. The validation of the simulation results obtained was performed by chemical dosimetry methods, namely a Fricke solution. The Fricke dosimeter is a standard dosimeter and is widely used in radiation processing for calibration purposes.

Characterization of the fast neutron irradiation facility of the Portuguese Research Reactor after core conversion

International Nuclear Information System (INIS)

Marques, J.G.; Sousa, M.; Santos, J.P.; Fernandes, A.C.

2011-01-01

The fast neutron irradiation facility of the Portuguese Research Reactor was characterized after the reduction in uranium enrichment and rearrangement of the core configuration. In this work we report on the determination of the hardness parameter and the 1 MeV equivalent neutron flux along the facility, in the new irradiation conditions, following ASTM E722 standard.

Reconstruction of Co-60 Irradiation Facility No.1

International Nuclear Information System (INIS)

Nakamura, Yoshiteru; Takada, Isao; Kaneko, Hirohisa; Hirao, Toshio; Haneda, Noriyuki; Mitomo, Shouichi; Tachibana, Hiroyuki; Yoshida, Kenzou

1989-01-01

Cobalt Irradiation Facility No.1 was constructed in 1964 as the first large scale Co-60 irradiation facility equipped a deep water pool for source storage of Co-60 sources. Recently, the reconstruction of the facility was decided because the aging of various parts of the facility became remarkable and new research programs required upgradings of the facility. Important points of upgradings are as follows: A shielding capacity of the source storage and pool is increased to 55.5 PBq from 18.5 PBq. The opening in a floor of the irradiation room which is used for the source lifting in the room, is enlarged in order to utilize a large and high intensity source. Radiation resistance of the irradiation apparatus and installed equipments in the radiation room is increased for a high dose rate irradiation. Basic structure and shape of the facility building such as shielding, pool and building roof is not changed but electrical, mechanical equipments and systems are completely renewed. To increase a reliability, the irradiation apparatus and systems are also replaced with an improved and up-to-date one designed based on operation experiences of Co-60 facilities at TRCRE through many years. In addition, auxiliary equipments such as radiation monitors, manipulators, water treatment system and so on are replaced. This report presents the reconstruction of Co-60 Irradiation Facility No.1 stressing on the replacement and modification of the irradiation apparatus. (author)

Mechanical Design and Manufacturing Preparation of Loading Unloading Irradiation Facility in Reflector Irradiation Position

International Nuclear Information System (INIS)

Hasibuan, Djaruddin

2004-01-01

Base on planning to increase of the irradiation service quality in Multi purpose Reactor-GAS, the mechanical design and manufacturing of the (n,γ) irradiation facility has been done. The designed of (n,γ) irradiation facility is a new facility in Multi purpose Reactor-GAS. The design doing by design of stringer, guide bar and hanger. By the design installation, the continuous irradiation service of non fission reaction will be easy to be done without reactor shut down. The design of the facility needs 3 pieces Al pipe by 36 x 1.5 mm, a peace of Al round bar by 80 mm diameter and a piece of Al plate by 20 x 60 x 0.2 mm for the stringer and guide bar manufacturing. By the building of non fission irradiation facility in the reflector irradiation position, will make the irradiation service to be increased. (author)

International standards and agreements in food irradiation

International Nuclear Information System (INIS)

Cetinkaya, N.

2004-01-01

The economies of both developed and developing countries have been effected by their exported food and agricultural products. Trading policies of food and agricultural products are governed by international agreement as well as national regulations. Trade in food and agricultural commodities may be affected by both principal Agreements within the overall World Trade Organization (WTO) Agreement, though neither specifically refers to irradiation or irradiated foods. The principal Agreements are the Technical Barriers to Trade (TBT) Agreement and the Sanitary and Phyto sanitary (SPS) Agreement. The SPS of the WTO requires governments to harmonize their sanitary and phyto sanitary measures on as wide basis as possible. Related standards, guidelines and recommendations of international standard setting bodies such as the Codex Alimentarius Commission (food safety); the International Plant Protection Convention (IPPC) (plant health and quarantine); and International Office of Epizootic (animal health and zoo noses) should be used in such a harmonization. International Standards for Phyto sanitary Measures (ISPM) no.18 was published under the IPPC by FAO (April 2003, Rome-Italy). ISPM standard provides technical guidance on the specific procedure for the application of ionizing radiation as a phyto sanitary treatment for regulated pests or articles. Moreover, Codex Alimentarius Commission, Codex General Standard for Irradiated Foods (Stand 106-1983) and Recommended International Code of Practice were first published in 1983 and revised in March 2003. Scope of this standard applies to foods processed by ionizing radiation that is used in conjunction with applicable hygienic codes, food standards and transportation codes. It does not apply to foods exposed to doses imparted by measuring instruments used for inspection purposes. Codex documents on Principles and Guidelines for the Import/Export Inspection and Certification of Foods have been prepared to guide international

Pagure {sup 60}Co panoramic irradiation facility; Pagure irradiateur panoramique au {sup 60}Co

Energy Technology Data Exchange (ETDEWEB)

Puig, J R; Laizier, J; Lorin, M; Laroche, R [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

1967-07-01

After a description of the various parts of 'PAGURE', a 10 KCi panoramic irradiation facility, and of the operations data, a critic scrutiny is given. From the experience of five years operations, working of the facility can be thought of very satisfying. From the point of view of standardization of irradiation facilities, PAGURE can be taken, in its range, as a standard design. (authors) [French] Apres avoir decrit les differents elements constitutifs de 1'irradiateur panoramique de 10 KCi 'PAGURE' et precise les donnees d'exploitation, on en fait l'examen critique. A la lumiere de cinq annees d'utilisation, le fonctionnement de 1'irradiateur apparait extremement satisfaisant. Dans une perspective de standardisation des appareils, on peut, dans sa gamme, le considerer comme une realisation type. (auteurs)

The operation of post-irradiation examination facility

International Nuclear Information System (INIS)

Kim, Eun Ka; Min, Duk Ki; Lee, Young Kil

1994-12-01

The operation of post-irradiation examination facility was performed as follow. HVAC and pool water treatment system were continuously operated, and radiation monitoring in PIE facility has been carried out to maintain the facility safely. Inspection of the fuel assembly (F02) transported from Kori Unit 1 was performed in pool, and fuel rods extracted from the fuel assembly (J44) of Kori Unit 2 NPP were examined in hot cell. A part of deteriorated pipe line of drinking water was exchanged for stainless steel pipe to prevent leaking accidents. Halon gas system was also installed in the exhausting blower room for fire fighting. And IAEA inspection camera for safeguard of nuclear materials was fixed at the wall in pool area. Radiation monitoring system were improved to display the area radioactive value at CRT monitor in health physics control room. And automatic check system for battery and emergency diesel generator was developed to measure the voltage and current of them. The performance test of oxide thickness measuring device installed in hot cell for irradiated fuel rod and improvement of the device were performed, and good measuring results using standard sample were obtained. The safeguard inspection of nuclear materials and operation inspection of the facility were carried out through the annual operation inspection, quarterly IAEA inspection and quality assurance auditing. 26 tabs., 43 figs., 14 refs. (Author) .new

Current status of irradiation facilities in JRR-3 and JRR-4

International Nuclear Information System (INIS)

Hori, Naohiko; Wada, Shigeru; Sasajima, Fumio; Kusunoki, Tsuyoshi

2006-01-01

The Department of Research Reactor has operated two research reactors, JRR-3 and JRR-4. These reactors were constructed in the Tokai Research Establishment. Many researchers and engineers use these joint-use facilities. JRR-3 is a light water moderated and cooled, pool type research reactor using low-enriched silicide fuel. JRR-3's maximum thermal power is 20MW. JRR-3 has nine vertical irradiation holes for RI production, nuclear fuels and materials irradiation at reactor core area. JRR-3 has many kinds of irradiation holes in a heavy water tank around the reactor core. These are two hydraulic rabbit irradiation facilities, two pneumatic rabbit irradiation facilities, one activation analysis irradiation facilities, one uniform irradiation facility, one rotating irradiation facility and one capsule irradiation facility. JRR-3 has nine horizontal experimental holes, that are used by many kinds of neutron beam experimental facilities using these holes. JRR-4 is a light water moderated and cooled, swimming pool type research reactor using low-enriched silicide fuel. JRR-4's maximum thermal power is 3.5MW. JRR-4 has five vertical irradiation tubes at reactor core area, three capsule irradiation facilities, one hydraulic rabbit irradiation facility, and one pneumatic rabbit irradiation facility. JRR-4 has a neutron beam hole, and it has used neutron beam experiments, irradiations for activation analysis and medical neutron irradiations. (author)

New facility for post irradiation examination of neutron irradiated beryllium

International Nuclear Information System (INIS)

Ishitsuka, Etsuo; Kawamura, Hiroshi

1995-01-01

Beryllium is expected as a neutron multiplier and plasma facing materials in the fusion reactor, and the neutron irradiation data on properties of beryllium up to 800 degrees C need for the engineering design. The acquisition of data on the tritium behavior, swelling, thermal and mechanical properties are first priority in ITER design. Facility for the post irradiation examination of neutron irradiated beryllium was constructed in the hot laboratory of Japan Materials Testing Reactor to get the engineering design data mentioned above. This facility consist of the four glove boxes, dry air supplier, tritium monitoring and removal system, storage box of neutron irradiated samples. Beryllium handling are restricted by the amount of tritium;7.4 GBq/day and 60 Co;7.4 MBq/day

Probabilistic safety assessment for food irradiation facility

International Nuclear Information System (INIS)

Solanki, R.B.; Prasad, M.; Sonawane, A.U.; Gupta, S.K.

2012-01-01

Highlights: ► Different considerations are required in PSA for Non-Reactor Nuclear Facilities. ► We carried out PSA for food irradiation facility as a part of safety evaluation. ► The results indicate that the fatal exposure risk is below the ‘acceptable risk’. ► Adequate operator training and observing good safety culture would reduce the risk. - Abstract: Probabilistic safety assessment (PSA) is widely used for safety evaluation of Nuclear Power Plants (NPPs) worldwide. The approaches and methodologies are matured and general consensus exists on using these approaches in PSA applications. However, PSA applications for safety evaluation for non-reactor facilities are limited. Due to differences in the processes in nuclear reactor facilities and non-reactor facilities, the considerations are different in application of PSA to these facilities. The food irradiation facilities utilize gamma irradiation sources, X-ray machines and electron accelerators for the purpose of radiation processing of variety of food items. This is categorized as Non-Reactor Nuclear Facility. In this paper, the application of PSA to safety evaluation of food irradiation facility is presented considering the ‘fatality due to radiation overexposure’ as a risk measure. The results indicate that the frequency of the fatal exposure is below the numerical acceptance guidance for the risk to the individual. Further, it is found that the overall risk to the over exposure can be reduced by providing the adequate operator training and observing good safety culture.

CERN IRRADIATION FACILITIES.

Science.gov (United States)

Pozzi, Fabio; Garcia Alia, Ruben; Brugger, Markus; Carbonez, Pierre; Danzeca, Salvatore; Gkotse, Blerina; Richard Jaekel, Martin; Ravotti, Federico; Silari, Marco; Tali, Maris

2017-09-28

CERN provides unique irradiation facilities for applications in dosimetry, metrology, intercomparison of radiation protection devices, benchmark of Monte Carlo codes and radiation damage studies to electronics. © The Author 2017. Published by Oxford University Press. All rights reserved. For Permissions, please email: journals.permissions@oup.com.

International standards and agreements in food irradiation

International Nuclear Information System (INIS)

Cetinkaya, N.

2004-01-01

Full text: The economies of both developed and developing countries have been effected by their exported food and agricultural products. Trading policies of food and agricultural products are governed by international agreement as well as national regulations. Trade in food and agricultural commodities may be affected by both principal Agreements within the overall World Trade Organization (WTO) Agreement, though neither specifically refers to irradiation or irradiated foods. The principal Agreements are the Technical Barriers to Trade (TBT) Agreement and the Sanitary and Phyto sanitary (SPS) Agreement. The SPS of the WTO requires governments to harmonize their sanitary and phyto sanitary measures on as wide basis as possible. Related standards, guidelines and recommendations of international standard setting bodies such as the Codex Alimentarius Commission (food safety); the International Plant Protection Convention (IPPC) (plant health and quarantine); and International Office of Epizootic (animal health and zoo noses) should be used in such a harmonization. International Standards for Phyto sanitary Measures (ISPM) no.18 was published under the IPPC by FAO (April 2003, Rome-Italy). ISPM standard provides technical guidance on the specific procedure for the application of ionizing radiation as a phyto sanitary treatment for regulated pests or articles. Moreover, Codex Alimentarius Commission, Codex General Standard for Irradiated Foods (Stand 106-1983) and Recommended International Code of Practice were first published in 1983 and revised in March 2003. Scope of this standard applies to foods processed by ionizing radiation that is used in conjunction with applicable hygienic codes, food standards and transportation codes. It does not apply to foods exposed to doses imparted by measuring instruments used for inspection purposes. Codex documents on Principles and Guidelines for the Import/Export Inspection and Certification of Foods have been prepared to guide

The present situation of the irradiation application industry and irradiation facilities in Japan

International Nuclear Information System (INIS)

Mizusawa, K.; Baba, T.

2003-01-01

The irradiation application industry and irradiation facilities in Japan have been making slow but steady progress for the past 2-3 years. Beside conventional applications, new ones such as carbon fibers and membrane filters have come into the market. There are a lot of new applications about to emerge. PE tubing, already is in the European market, is being evaluated by end users in Japan. Cleaning of dioxin in exhaust gas was successfully tested at a pilot plant. Cross-linked PTFE and polyamide are waiting customers' evaluations as an engineering plastic. Surface cross-linking of artificial polycarbonate teeth has yielded remarkable experimental results. Cross-linking of polycaprolactone will be useful for biodegradable products. Being aware of the future growth of irradiation industry, contract service providers opened new facilities or increased their capability. Beside in-house facilities, there are now three Co-60 facilities and nine EB facilities available for contract irradiation in Japan

Food irradiation: Gamma processing facilities

Energy Technology Data Exchange (ETDEWEB)

Kunstadt, P. [MDS Nordion International, 447 March Road. Kanata, Ontario, K2K148 (Canada)

1997-12-31

The number of products being radiation processed is constantly increasing and today include such diverse items as medical disposable, fruits and vegetables, bulk spices, meats, sea foods and waste effluents. Not only do the products differ but also many products, even those within the same groupings, require different minimum and maximum radiation doses. These variations create many different requirements in the irradiator design. The design of Cobalt-60 radiation processing facilities is well established for a number of commercial applications. Installations in over 40 countries, with some in operation since the early 1960s, are testimony to the fact that irradiator design, manufacture, installation and operation is a well established technology. However, in order to design gamma irradiators for the preservation of foods one must recognize those parameters typical to the food irradiation process as well as those systems and methods already well established in the food industry. This paper discusses the basic design concepts for gamma food irradiators. They are most efficient when designed to handle a limited product density range at an established dose. Safety of Cobalt-60 transport, safe facility operation principles and the effect of various processing parameters on economics, will also be discussed. (Author)

Food irradiation: Gamma processing facilities

Energy Technology Data Exchange (ETDEWEB)

Kunstadt, P [MDS Nordion International, 447 March Road. Kanata, Ontario, K2K148 (Canada)

1998-12-31

The number of products being radiation processed is constantly increasing and today include such diverse items as medical disposable, fruits and vegetables, bulk spices, meats, sea foods and waste effluents. Not only do the products differ but also many products, even those within the same groupings, require different minimum and maximum radiation doses. These variations create many different requirements in the irradiator design. The design of Cobalt-60 radiation processing facilities is well established for a number of commercial applications. Installations in over 40 countries, with some in operation since the early 1960s, are testimony to the fact that irradiator design, manufacture, installation and operation is a well established technology. However, in order to design gamma irradiators for the preservation of foods one must recognize those parameters typical to the food irradiation process as well as those systems and methods already well established in the food industry. This paper discusses the basic design concepts for gamma food irradiators. They are most efficient when designed to handle a limited product density range at an established dose. Safety of Cobalt-60 transport, safe facility operation principles and the effect of various processing parameters on economics, will also be discussed. (Author)

Food irradiation: Gamma processing facilities

International Nuclear Information System (INIS)

Kunstadt, P.

1997-01-01

The number of products being radiation processed is constantly increasing and today include such diverse items as medical disposable, fruits and vegetables, bulk spices, meats, sea foods and waste effluents. Not only do the products differ but also many products, even those within the same groupings, require different minimum and maximum radiation doses. These variations create many different requirements in the irradiator design. The design of Cobalt-60 radiation processing facilities is well established for a number of commercial applications. Installations in over 40 countries, with some in operation since the early 1960s, are testimony to the fact that irradiator design, manufacture, installation and operation is a well established technology. However, in order to design gamma irradiators for the preservation of foods one must recognize those parameters typical to the food irradiation process as well as those systems and methods already well established in the food industry. This paper discusses the basic design concepts for gamma food irradiators. They are most efficient when designed to handle a limited product density range at an established dose. Safety of Cobalt-60 transport, safe facility operation principles and the effect of various processing parameters on economics, will also be discussed. (Author)

Idaho National Engineering Laboratory irradiation facilities and their applications

International Nuclear Information System (INIS)

Gupta, V.P.; Herring, J.S.; Korenke, R.E.; Harker, Y.D.

1986-05-01

Although there is a growing need for neutron and gamma irradiation by governmental and industrial organizations in the United States and in other countries, the number of facilities providing such irradiations are limited. At the Idaho National Engineering Laboratory, there are several unique irradiation facilities producing high neutron and gamma radiation environments. These facilities could be readily used for nuclear research, materials testing, radiation hardening studies on electronic components/circuitry and sensors, and production of neutron transmutation doped (NTD) silicon and special radioisotopes. In addition, a neutron radiography unit, suitable for examining irradiated materials and assemblies, is also available. This report provides a description of the irradiation facilities and the neutron radiography unit as well as examples of their unique applications

Startup of the Whiteshell irradiation facility

International Nuclear Information System (INIS)

Barnard, J.W.; Stanley, F.W.

1989-01-01

Recently, a 10-MeV, 1-kW electron linear accelerator was installed in a specially designed irradiation facility at the Whiteshell Nuclear Research Establishment. The facility was designed for radiation applications research in the development of new radiation processes up to the pilot scale level. The accelerator is of advanced design. Automatic startup via computer control makes it compatible with industrial processing. It has been operated successfully as a fully integrated electron irradiator for a number of applications including curing of plastics and composites, sterilization of medical disposables and animal feed irradiation. We report here on our experience during the first six months of operation. (orig.)

Startup of the whiteshell irradiation facility

Science.gov (United States)

Barnard, J. W.; Stanley, F. W.

1989-04-01

Recently, a 10-MeV, 1-kW electron linear accelerator was installed in a specially designed irradiation facility at the Whiteshell Nuclear Research Establishment. The facility was designed for radiation applications research in the development of new radiation processes up to the pilot scale level. The accelerator is of advanced design. Automatic startup via computer control makes it compatible with industrial processing. It has been operated successfully as a fully integrated electron irradiator for a number of applications including curing of plastics and composites, sterilization of medical disposables and animal feed irradiation. We report here on our experience during the first six months of operation.

The construction of irradiated material examination facility

International Nuclear Information System (INIS)

Ro, Seung Gy; Lee, Key Soon; Herr, Young Hoi

1990-03-01

A detail design of the examination process, the hot cell facility and the annexed facility of the irradiated material examination facility (IMEF) which will be utilized to examine and evaluate physical and mechanical properties of neutron-irradiated materials, has been performed. Also a start-up work of the underground structure construction has been launched out. The project management and tasks required for the license application were duly carried out. The resultant detail design data will be used for the next step. (author)

Design, Fabrication, and Initial Operation of a Reusable Irradiation Facility

International Nuclear Information System (INIS)

Heatherly, D.W.; Thoms, K.R.; Siman-Tov, I.I.; Hurst, M.T.

1999-01-01

A Heavy-Section Steel Irradiation (HSSI) Program project, funded by the US Nuclear Regulatory Commission, was initiated at Oak Ridge National Laboratory to develop reusable materials irradiation facilities in which metallurgical specimens of reactor pressure vessel steels could be irradiated. As a consequence, two new, identical, reusable materials irradiation facilities have been designed, fabricated, installed, and are now operating at the Ford Nuclear Reactor at the University of Michigan. The facilities are referred to as the HSSI-IAR facilities with the individual facilities being designated as IAR-1 and IAR-2. This new and unique facility design requires no cutting or grinding operations to retrieve irradiated specimens, all capsule hardware is totally reusable, and materials transported from site to site are limited to specimens only. At the time of this letter report, the facilities have operated successfully for approximately 2500 effective full-power hours

New multipurpose gamma-irradiation facility

Energy Technology Data Exchange (ETDEWEB)

Huebner, G

1985-01-01

In the past 3 years much work has been done in the G.D.R. on food irradiation. The experiments have shown that this treatment gives favourable results in many products such as spices, onions, potatoes, chicken, animal feeds, fodder yeast, drugs and vaccines. Economic aspects of food irradiation require the effective use of an irradiation plant and cobalt-60. Therefore, a new multipurpose irradiation facility was developed, applicable as an onion irradiator with a capacity of about 15 ton/h and for the simultaneous irradiation of different products (spices, animal feed, chicken, etc.) in closed product boxes with a size of 1.2 m x 1.0 m x 1.2 m. A microcomputer controls the transport of product boxes around the gamma sources.

Design of special facility for liquor irradiation

International Nuclear Information System (INIS)

Yao Shibin; Chen Zigen

1989-01-01

The design principle, physical scheme, technological process, construction and safety features of a special facility used for irradiating liquors is briefly described. 0.925 x 10 15 Bq cobalt source is used and the irradiation capacity for liquors approaches 10 t per day. The facility bears advantages of simple in construction, easy to operate, safe, reliable and efficient in source utilization

Performance of Shiva as a laser fusion irradiation facility

International Nuclear Information System (INIS)

Speck, D.R.; Bliss, E.S.; Glaze, J.A.; Johnson, B.C.; Manes, K.R.; Ozarski, R.G.; Rupert, P.R.; Simmons, W.W.; Swift, C.D.; Thompson, C.E.

1979-01-01

Shiva is a 20 beam Nd:Glass Laser and Target Irradiation Facility at the Lawrence Livermore Laboratory. The laser system and integrated target facility evolved during the last year from a large, untested, experimental laser system to a target irradiation facility which has provided significant laser driven inertial confinement fusion data. The operation of the facility is discussed

Progress towards a new Canadian irradiation-research facility

International Nuclear Information System (INIS)

Lee, A.G.; Lidstone, R.F.

1993-01-01

As reported at the second meeting of the International Group on Research Reactors, Atomic Energy of Canada Limited (AECL) is evaluating its options for future irradiation facilities. During the past year significant progress has been made towards achieving consensus on the irradiation requirements for AECL's major research programs and interpreting those requirements in terms of desirable characteristics for experimental facilities in a research reactor. The next stage of the study involves identifying near-term and long-term options for irradiation-research facilities to meet the requirements. The near-term options include assessing the availability of the NRU reactor and the capabilities of existing research reactors. The long-term options include developing a new irradiation-research facility by adapting the technology base for the MAPLE-X10 reactor design. Because materials testing in support of CANDU power reactors dominates AECL's irradiation requirements, the new reactor concept is called the MAPLE Materials Testing Reactor (MAPLE-MTR). Parametric physics and engineering studies are in progress on alternative MAPLE-MTR configurations to assess the capabilities for the following types of test facilities: - fast-neutron sites, that accommodate materials-irradiation assemblies, - small-diameter vertical fuel test loops that accommodate multielement assemblies, - large-diameter vertical fuel test loops, each able to hold one or more CANDU fuel bundles, - horizontal test loops, each able to hold full-size CANDU fuel bundles or small-diameter multi-element assemblies, and - horizontal beam tubes

Radiation facilities and irradiation technology for food irradiation

International Nuclear Information System (INIS)

Sunaga, Hiromi

2005-01-01

Progress made during these 30 years in the field of radiation treatment of food is reviewed by describing features of the process including elementary processes, quality control of the products and the dosimetric techniques widely employed. The Co-60 gamma-ray irradiation facilities to be used for radiation-sterilization of medical supplies and food preservation are presented. For electron beam irradiation, accelerators for processing with the energy from 0.3 to 10 MeV are generally employed. The electron-guns, the method of acceleration such as rectification, types of acceleration as Cockcroft-Walton, dynamitron, or linear acceleration and X-ray producing facility, with various countermeasures for safety management, are briefly explained. The concepts of dose and traceability are given. The dosimeters including reference dosimeter and routine ones with validation are explained. (S. Ohno)

Development of the irradiation facilities for silicon neutron doping in France

International Nuclear Information System (INIS)

Breant, P.; Cherruau, F.; Genthon, J.P.

1980-08-01

Irradiation facilities for silicon irradiations in France may be classified in two categories: on the one hand the devices directly implemented in the light water of α swimming-pool reactor and on the other hand the devices implemented in a neutronic medium -heavy water here- providing a high value of the thermal to fast neutron flux ratio. The tools used in France for silicon neutron doping are recapitulated according to this classification in tables, with their main characteristics; in addition it is specified that all existing facilities are instrumented with ingot rotation, flux monitoring, automatic time integration and are associated with handling, storage, cleaning, decontamination and activity control equipment. Finally, concerning the irradiation capacities given in these tables, it is pointed out that they are realistic and present capacities, for presently running devices and according to the way they are used on an average; that is to say that they take into account the real average dimensions of the ingot supplied and not the maximum possible loading with the maximum diameters. Further extensions of capacity are possible if need be by the installation of supplementary standard irradiation modules in the pools. Particular attention will given to the new developments: -new irradiaton facilities with a high Oth/Or ratio being developed in the new research reactor ORPHEE: - developments in the OSIRIS H 2 O reactor. In particular and in connection with the facilities developped in OSIRIS, neutronic problems typical and swimming-pool reactors will be contemplated and the adopted solutions given

UTN's gamma irradiation facility: design and concept

International Nuclear Information System (INIS)

Mohamad Noor Mohamad Yunus

1986-01-01

UTN is building a multipurpose gamma irradiation facility which compromises of research and pilot scale irradiation cells in The Fifth Malaysia Plan. The paper high-lights the basic futures of the facility in terms of its design and selection including layout sketches. Plant performances and limitations are discussed. Plants safety is briefly highlighted in block diagrams. Lastly, a typical specification brief is tabled in appendix for reference purposes. (author)

User Support of Electron Irradiation Facility

International Nuclear Information System (INIS)

Park, S. H.; Cha, H. K.; Lee, B. C.

2007-06-01

The KAERI (Korean Atomic Energy Research Institute) high-power electron beam irradiation facility, operating at the energies between 0.3 MeV and 10 MeV,has provided irradiation services to users in industries, universities, and institutes via 'Project of utilization and cooperation of users of a large research facility' since 2004. A great attraction of many researchers, almost 750 persons so far according to surveys, to e-beam irradiation technology as well as the growth of participants on Workshop on Electron Beam Applications from 121 to 176 indicate the increase of demands of irradiation service. Comparing to the cases of advanced nations in this area, such as America, Japan, China, and Russia, Korea is relatively much behind in radiation technology. It is mainly due to the lack of governmental supports and investments. Active support and investment on construction and operation of electron beam user facilities would be principal factors on developments of advanced technologies. In this project, we would like to satisfy users' requests by developing the effective managing and operating system for prompt services, processes, and QA and to ultimately assist users to create additional new results, by maximizing the utilization of all available resources and activating the developments of technologies of electron beam processing

IRASM - A multipurpose irradiation facility in Romania

International Nuclear Information System (INIS)

Ponta, C.C.; Moise, I.V.; Bratu, E.

1998-01-01

A multipurpose irradiation facility is under construction at IPNE, Bucharest, under the IAEA T.C. Project: ROM/8/011. It will be the first industrial facility in Romania. This paper presents the philosophy standing behind the design, the short and long term managing plans. Some dose calculations are added in the view of using the empty spaces in the irradiation room for cultural heritage conservation. An economic study is presented aiming to provide basic estimations for further management strategy. At the start the facility will be a state enterprise. The implications, advantages and disadvantages of this situation are discussed

Radiation safety of gamma and electron irradiation facilities

International Nuclear Information System (INIS)

1992-01-01

There are currently some 160 gamma irradiation facilities and over 600 electron beam facilities in operation throughout virtually all Member States of the IAEA. The most widespread uses of these facilities are for the sterilization of medical and pharmaceutical products, the preservation of foodstuffs, polymer synthesis and modification, and the eradication of insect infestation. The safety record of this industry has been very good. Nevertheless, there is a potential for accidents with serious consequences. Gamma and electron beam facilities produce very high dose rates during irradiation, so that a person accidentally present in the irradiation chamber can receive a lethal dose within minutes or seconds. Precautions against uncontrolled entry must therefore be taken. Furthermore, gamma irradiation facilities contain large amounts of radioactivity and if the mechanism for retracting the source is damaged, the source may remain exposed, inhibiting direct access to carry out remedial work. Contamination can result from corroded or damaged sources, and decontamination can be very expensive. These aspects clearly indicate the need to achieve a high degree of safety and reliability in the facilities. This can be accomplished by effective quality control together with careful design, manufacture, installation, operation and decommissioning. The guidance in this Safety Series publication is intended for competent authorities responsible for regulating the use of radiation sources as well as the manufacturers, suppliers, installers and users of gamma and electron beam facilities. 20 refs, 6 figs

Fusion Materials Irradiation Test Facility: a facility for fusion-materials qualification

International Nuclear Information System (INIS)

Trego, A.L.; Hagan, J.W.; Opperman, E.K.; Burke, R.J.

1983-01-01

The Fusion Materials Irradiation Test Facility will provide a unique testing environment for irradiation of structural and special purpose materials in support of fusion power systems. The neutron source will be produced by a deuteron-lithium stripping reaction to generate high energy neutrons to ensure damage similar to that of a deuterium-tritium neutron spectrum. The facility design is now ready for the start of construction and much of the supporting lithium system research has been completed. Major testing of key low energy end components of the accelerator is about to commence. The facility, its testing role, and the status and major aspects of its design and supporting system development are described

National Low-Temperature Neutron-Irradiation Facility

International Nuclear Information System (INIS)

Coltman, R.R. Jr.; Klabunde, C.E.; Young, F.W. Jr.

1983-08-01

The Materials Sciences Division of the United States Department of Energy will establish a National Low Temperature Neutron Irradiation Facility (NLTNIF) which will utilize the Bulk Shielding Reactor (BSR) located at Oak Ridge National Laboratory. The facility will provide high radiation intensities and special environmental and testing conditions for qualified experiments at no cost to users. This report describes the planned experimental capabilities of the new facility

The PIREX proton irradiation facility

Energy Technology Data Exchange (ETDEWEB)

Victoria, M. [Association EURATOM, Villigen (Switzerland)

1995-10-01

The proton Irradiation Experiment (PIREX) is a materials irradiation facility installed in a beam line of the 590 MeV proton accelerator at the Paul Scherrer Institute. Its main purpose is the testing of candidate materials for fusion reactor components. Protons of this energy produce simultaneously displacement damage and spallation products, amongst them helium and can therefore simulate any possible synergistic effects of damage and helium, that would be produced by the fusion neutrons.

The PIREX proton irradiation facility

International Nuclear Information System (INIS)

Victoria, M.

1995-01-01

The proton Irradiation Experiment (PIREX) is a materials irradiation facility installed in a beam line of the 590 MeV proton accelerator at the Paul Scherrer Institute. Its main purpose is the testing of candidate materials for fusion reactor components. Protons of this energy produce simultaneously displacement damage and spallation products, amongst them helium and can therefore simulate any possible synergistic effects of damage and helium, that would be produced by the fusion neutrons

Post irradiation examinations cooperation and worldwide utilization of facilities

International Nuclear Information System (INIS)

Karlsson, Mikael

2009-01-01

Status of post irradiation examinations in Studsvik's facilities, cooperation and worldwide utilization of facilities, was described. Studsvik cooperate with irradiation facilities, as Halden, CEA and JAEA, as well as other hot cell facilities (examples, PSI, ITU and NFD) universities (example, the Royal Institute of Technology in Sweden) in order to be able to provide everything asked for by the nuclear community. Worldwide cooperation for effective use of expensive and highly specialized facilities is important, and the necessity of cooperation will be more and more recognized in the future. (author)

New irradiation facilities at the Australian national medical cyclotron

International Nuclear Information System (INIS)

Parcell, S.K.; Arnott, D.W.; Conard, E.M.

1999-01-01

Two new irradiation facilities have been developed at the National Medical Cyclotron for radionuclide production. The first relocates PET irradiations from the cyclotron vault to a dedicated PET beam room, to improve accessibility and reduce radiation exposures associated with target maintenance. This new facility consists of a beam line to transport 16-30 MeV proton beams from the cyclotron to 1 of 8 PET targets mounted on a target rack. The target rack has increased the number of targets available for production and experimentation. The second is a completely independent solid target irradiation facility for SPECT. This facility consists of a beam line to transport 26-30 MeV proton beams from the cyclotron to a dedicated beam room containing one solid target station. A new pneumatic target transfer system was also developed to transport the solid target to and from the existing chemistry hot cells. The beam line and target components are operated under the control of a dedicated PLC with a PC based user interface. The development and some technical aspects of these new irradiation facilities are discussed here. (author)

Low temperature irradiation facility at Kyoto University Reactor (KUR)

International Nuclear Information System (INIS)

Atobe, Kozo; Okada, Moritami; Yoshida, Hiroyuki; Kodaka, Hisao; Miyata, Kiyomi.

1977-01-01

A new refrigeration system has been substituted to the low temperature irradiation facility at KUR instead of the previous one, since April in 1975. The model 1204 CTi He liquifier was designed to be modified for the refrigerator with the capacity of 30 watts at 10 K. The refrigeration capacity of 38 watts at 10 K was defined using a special cryostat and transfer-tubes, and the lowest temperature of about 18 K was measured using the irradiation loop without reactor operation. The reconstructed facility enables us to hold the many specimens simultaneously in the sample chamber of the irradiation loop at about 25 K during reactor operation of 5 MW. The irradiation dose has been reached about 6.6 x 10 16 n sub(f)/cm 2 and 6.1 x 10 17 n sub(th)/cm 2 with the normal reactor operation cycle of up to 77 hours. The stable operation condition of the machine and the special safety system for the refrigeration system enable us to maintain easily the facility with a constant operation condition for such a long time irradiation. Many kinds of low temperature neutron irradiation experiments are carried out using the facility, which techniques are partially reported. (auth.)

Study on increasing commercial benefits of 60Co irradiation facilities

International Nuclear Information System (INIS)

Yang Shuizi; Qi Huanjiang; Xei Tong

2004-01-01

Estimating commercial benefits of irradiation facilities adopts commercial benefits coefficient. The effect factors are the utilization rate of irradiation energy (E), the consistency of irradiation facilities (Ci), the utilization rate of time (T), the utilization rate of space, the minimum efficient adsorption dose (Dmin), the irradiation adsorption dose uriformity (U), the sale (S), the running cost (C) et. al, and E, Ci, S, C are main in all factors. (authors)

Installation of the water environment irradiation facility for the IASCC research under the BWR irradiation environment (1)

International Nuclear Information System (INIS)

Okada, Yuji; Magome, Hirokatsu; Hanawa, Hiroshi; Ohmi, Masao; Kanno, Masaru; Iida, Kazuhiro; Ando, Hitoshi; Shibata, Mitsunobu; Yonekawa, Akihisa; Ueda, Haruyasu

2013-10-01

In Japan Atomic Energy Agency, in order to solve the problem in the long-term operation of a light water reactor, preparation which does the irradiation experiment of light-water reactor fuel and material is advanced. JMTR stopped after the 165th operation cycle in August 2006, and is advancing renewal of the irradiation facility towards re-operation. This material irradiation test facility and power ramping test facility for doing the neutron irradiation test of the fuel and material for light water reactors is scheduled to be manufactured and installed between the 2008 fiscal year and the 2012 fiscal year. This report summarizes manufacture and installation of the material irradiation test facility for IASCC research carried out from the 2008 fiscal year to the 2010 fiscal year. (author)

Technical Safety Requirements for the Gamma Irradiation Facility (GIF)

CERN Document Server

Mahn, J A E M J G

2003-01-01

This document provides the Technical Safety Requirements (TSR) for the Sandia National Laboratories Gamma Irradiation Facility (GIF). The TSR is a compilation of requirements that define the conditions, the safe boundaries, and the administrative controls necessary to ensure the safe operation of a nuclear facility and to reduce the potential risk to the public and facility workers from uncontrolled releases of radioactive or other hazardous materials. These requirements constitute an agreement between DOE and Sandia National Laboratories management regarding the safe operation of the Gamma Irradiation Facility.

Questionnaire survey and technical guideline of blood irradiation on medical facilities

International Nuclear Information System (INIS)

Matsumoto, Mitsuhiro; Hasegawa, Hironori; Okumura, Masahiko; Sonoda, Tatsuo; Osada, Koji.

1997-01-01

We know that transfusion-associated graft versus host disease (TA-GVHD) is a serious side effect associated with blood transfusion and the onset is independent on the immunological conditions of patients. We have only prophylactic treatment against TA-GVHD. The most reliable method is to irradiate the blood for transfusion. In Japanese medical facilities, however, the risk of TA-GVHD is poorly understood and actual conditions of the blood irradiation are unclear. We sent a questionnaire to randomly selected 426 medical facilities in Japan, which had the department of radiology, to investigate the actual conditions of blood irradiation for transfusion and the problems on the irradiation dose measurement of the external apparatus for blood irradiation. The questionnaire involved 19 questions about the blood irradiation for transfusion. The survey took place for one month (June 1-June 30, 1995). Replies were obtained from a total of 306 medical facilities (72%). The results showed that blood irradiation was done by several methods in the 75% of the medical facilities, and the external irradiation apparatus was used in 83%. Some problems were shown, including irradiation period, cost of the irradiation, the operating procedure of the apparatus, requested number of the irradiation, and the request after usual hours. There was no significant problem on the irradiation dose, irradiation method, etc. We also sent a questionnaire to 74 facilities of the Red Cross Blood Center, in which the frequency of blood irradiation have increased since May, 1976. The X-ray apparatus as the external irradiation apparatus has practical advantages; lower cost, compact and out of the legal control on the ionizing radiation, however, it has some problems on the uniformity of the absorption dose when a single X-ray tube-type apparatus is used. We discuss about the possible onset of TA-GVHD or other accidents by the incorrect irradiation of the blood preparations. (K.H.)

Omega: A 24-beam UV irradiation facility

International Nuclear Information System (INIS)

Richardson, M.C.; Beich, W.; Delettrez, J.

1985-01-01

The authors report on the characterization and performance of the 24-beam Omega laser facility under full third harmonic (351-nm) upconversion. This system provides for the first time a multibeam laser facility for the illumination of spherical targets with UV laser light in symmetric irradiation conditions with energies in the kilojoule range. This facility is capable of providing sufficient irradiation uniformity to test concepts of direct drive laser fusion with UV-driven ablation targets. The results of initial studies of ablatively driven DT-fueled glass microballoon targets will be described. The 24-beam Omega Nd:phosphate glass facility is capable of providing at 1054 nm output powers in excess of 10 TW in short ( 10 4 full system shots to date) irradiation facility with beam synchronism of approx. =3 psec, beam placement accuracy on target of 10 μm, and interbeam energy variance of approx. =2%. From measured target plane intensity distributions, overall illumination uniformity with tangentially focused beams is estimated to be approx. =5%. In 1984, a symmetric set of six beams was upconverted to 351-nm radiation using the polarization-mismatch scheme developed by Craxton. Monolithic cells of 20-cm clear aperture containing both frequency and doubler and tripler type II KDP crystals in index-matching propylene carbonate liquid were incorporated to output of six of the Omega beams with a full set of UV beam diagnostics

Irradiation facilities at the Los Alamos Meson Physics Facility

International Nuclear Information System (INIS)

Sandberg, V.

1990-01-01

The irradiation facilities for testing SSC components and detector systems are described. Very high intensity proton, neutron, and pion fluxes are available with beam kinetic energies of up to 800 MeV. 4 refs., 12 figs., 2 tabs

The proceedings of 1993-workshop on 'development and application of facilities for low temperature irradiation as well as controlled irradiation'

International Nuclear Information System (INIS)

Kuramoto, Eiichi; Okada, Moritami

1993-03-01

This is the proceedings of 1992-workshop of the working group on 'Development and Application of Facilities for Low Temperature Irradiation as well as Controlled Irradiation' held at the Research Reactor Institute of Kyoto University on February 23 and 24, 1993. In this workshop until now, studies on irradiation effects in many materials irradiated at lower and higher temperatures have been reported. It has been clearly defined that a careful choice of irradiation conditions is most important. At the present time, a setting plan of exactly controlled irradiation facility, which is able to irradiate with higher temperatures, is in progress. On the other hand, a plan of vertical low temperature irradiation facility has not yet been performed for lack of funds. In last year, a middle scale plan of low temperature irradiation facility, which is possible to irradiate a fast-neutron dose above 10 17 n/cm 2 at about 5K, was proposed in this workshop. In this proceedings, the advanced facility is required to construct to the KUR as soon as possible by many of the workshop members. (author)

Irradiation facilities on the TRIGA-SSR thermal column

Energy Technology Data Exchange (ETDEWEB)

Roth, C; Aioanei, L; Preda, M; Gugiu, D [Institute for Nuclear Research, Pitesti (Romania); Garlea, I; Kelerman, C; Garlea, C [SENDRA ' Nuclear Technologies' ltd. Bucharest (Romania)

2004-07-01

The development of thermal and intermediate energy neutron irradiation facilities at the steady state core of the Romanian TRIGA Reactor is described. The reference thermal neutron irradiation facility consists of a dry spherical cavity placed into the graphite thermal column of the SSR core and the intermediate energy neutron irradiation facility is a {sigma}{sigma} system located into the thermal flux cavity. The implementation of the irradiation facilities into the under-water thermal column represented an important challenge from the standpoint of instrumentation solutions. The neutron flux and spectrum measurements were performed using foil activation techniques and fission rate measurements by sealed fission chambers, followed by spectrum unfolding procedure. The absolute fission reaction measurements, using calibrated fission chambers, allow the neutron flux density unit transfer from international reference neutron fields. The MCNP-4C code package was used for neutron spectrum computations in the thermal flux cavity and in the {sigma}{sigma} system. The neutron characterization program demonstrates the accuracy of the spectrum characteristics and neutron flux densities reported to the local monitoring system count rates. Some discrepancies, as compared to other similar facilities, were identified and discussed. These are caused by thermal column particularities: the presence of a water layer between the graphite cells (thermal neutron absorption) and smaller geometrical dimensions (neutron escape phenomena). Based on these results the metrological certification process, according to Romanian metrological laws requirements, is now in progress. (nevyjel)

Development of new irradiation facility for BWR safety research

International Nuclear Information System (INIS)

Okada, Yuji; Magome, Hirokatsu; Iida, Kazuhiro; Hanawa, Hiroshi; Ohmi, Masao

2013-01-01

In JAEA (Japan Atomic Energy Agency), about the irradiation embrittlement of the reactor pressure vessel and the stress corrosion cracking of reactor core composition apparatus concerning the long-term use of the light water reactor (BWR), in order to check the influence of the temperature, pressure, and water quality, etc on BWR condition. The water environmental control facility which performs irradiation assisted stress corrosion-cracking (IASCC) evaluation under BWR irradiation environment was fabricated in JMTR (Japan Materials Testing Reactor). This report is described the outline of manufacture of the water environmental control facility for doing an irradiation test using the saturation temperature capsule after JMTR re-operation. (author)

Reconstruction of exposures to the public from a cobalt-60 irradiator facility

International Nuclear Information System (INIS)

Chapman, T.E.; Scherpelz, R.I.

1992-01-01

A study was performed for the US Department of Energy (DOE) to assess the radiation exposure received by the public from the operation of a cobalt-60 irradiator facility. Located south of Davis, California, at the former Laboratory for Energy-Related Health Research, the facility was an indoor-outdoor gamma irradiator operated for the DOE by the University of California, Davis. From 1970 to 1985, outdoor radiation exposure experiments conducted at the facility resulted in environmental radiation doses of 80 to 120 mSv per year along the facility's perimeter fence. Comprehensive environmental monitoring was not performed in the adjacent, uncontrolled areas and personnel who occupied these areas were not routinely monitored for radiation exposure. Because of incomplete environmental monitoring data, computer modeling was required to reconstruct the environmental dose rates present when the facility was in operation. Personnel occupancy times for the adjacent areas were determined from population statistics, historical records, and personal interviews. The potential dose equivalents calculated for the individuals who lived or worked in neighboring areas ranged from 0.02 to 3.6 mSv per year. These exposures, some of which exceed the current DOE standard of 1 mSv/y, were less than the DOE regulatory limit of 5 mSv/y for exposure to the public that was in effect when the facility was in operation

The BLAIRR Irradiation Facility Hybrid Spallation Target Optimization

Energy Technology Data Exchange (ETDEWEB)

Simos N.; Hanson A.; Brown, D.; Elbakhshawn, M.

2016-04-11

BLAIRR STUDY STATUS OVERVIEW Beamline Complex Evaluation/Assessment and Adaptation to the Goals Facility Radiological Constraints ? Large scale analyses of conventional facility and integrated shield (concrete, soil)Target Optimization and Design: Beam-target interaction optimization Hadronic interaction and energy deposition limitations Single phase and Hybrid target concepts Irradiation Damage Thermo-mechanical considerations Spallation neutron fluence optimization for (a) fast neutron irradiation damage (b) moderator/reflector studies, (c) NTOF potential and optimization (d) mono-energetic neutron beam

Positive ion irradiation facility

International Nuclear Information System (INIS)

Braby, L.A.

1985-01-01

Many questions about the mechanisms of the response of cells to ionizing radiation can best be investigated using monoenergetic heavy charged particle beams. Questions of the role of different types of damage in the LET effect, for example, are being answered by comparing repair kinetics for damage induced by electrons with that produced by helium ions. However, as the models become more sophicated, the differences between models can be detected only with more precise measurements, or by combining high- and low-LET irradiations in split-dose experiments. The design of the authors present cell irradiation beam line has limited the authors to irradiating cells in a partial vacuum. A new way to mount the dishes and bring the beam to the cells was required. Several means of irradiating cells in mylar-bottom dishes have been used at other laboratories. For example at the RARAF Facility, the dual ion experiments are done with the dish bottom serving as the beam exit window but the cells are in a partial vacuum to prevent breaking the window. These researchers have chosen instead to use the dish bottom as the beam window and to irradiate the entire dish in a single exposure. A special, very fast pumping system will be installed at the end of the beam line. This system will make it possible to irradiate cells within two minutes of installing them in the irradiation chamber. In this way, the interaction of electron and ion-induced damage in Chlamydomonas can be studied with time between doses as short as 5 minutes

Development of a quality system for a contract irradiation facility

International Nuclear Information System (INIS)

Siyakus, G.

2002-01-01

The use of Industrial Irradiation Systems, in order to process medical supplies and food commodities, has almost 50 years experiences in the world. The food irradiation process has been approved by more than 40 countries around the world and it has been endorsed or supported by numerous national and international organizations and professional groups. Today, radiation sterilization of medical supplies is the most preferred technology in almost every developed country. Other applications: such as waste and flue gas treatment, polymer processing are also put into practice in wider range than before. Higher capital cost compared to the operation cost, the nature of continuous decay of the radiation sources used to obtain gamma rays, obligate the owners of gamma facilities to operate systems based on the 24 hours a day and 7 days per week. On the other hand, higher throughput capacity and economical brake point for profitability, force irradiation companies to offer service for the varied products of the companies. Industrial irradiation facilities providing services for varied companies by irradiating different kind of commodities so called contract irradiator or multipurpose irradiator and most of the irradiation facilities, particularly gamma irradiators running in different locations of the World, operates as contract irradiators. The radiation facilities are considered as a part of the manufacturing process, and must conform to the pertinent general Code of Good Manufacturing Practice (GMP) which has been declared by the principal producer. Customers of these facilities may have petitions, such as irradiation temperature, dose rate, minimal and maximal doses; storage conditions before and after irradiation. Design parameters related to the dose rate, product size, density and weight, irradiation and storage temperatures are the main limitations. Varied process conditions can be easily applied in the laboratory may set forth difficulties in industrial processes

IRRAD: The New 24GeV/c Proton Irradiation Facility at CERN

CERN Document Server

Gkotse, Blerina; Moll, Michael; Ravotti, Federico

2016-01-01

The proton and mixed-field irradiation facilities at the CERN PS East Area (known as IRRAD1 and IRRAD2), have been heavily exploited for irradiation of particle detectors, electronic components and materials since 1992. With the increasing demand of irradiation experiments, and in view of the High-Luminosity upgrade of the CERN Large Hadron Collider (HL-LHC), these facilities suffered of a number of unpleasant restrictions such as the space availability, the maximum achievable particle flux and several access constraints. In the framework of the AIDA project, an upgrade of these facilities was carried out during the Long Shutdown 1 (LS1) of the CERN accelerator complex. The new combined East Area IRRADiation facility (EA-IRRAD) started the commissioning in October 2014. While the new proton facility (IRRAD) continue to be mainly devoted to the radiation hardness studies for the High Energy Physics community, the new mixed-field facility (CHARM) mainly hosts irradiation experiments for the validation of electr...

Defocusing beam line design for an irradiation facility at the TAEA SANAEM Proton Accelerator Facility

Science.gov (United States)

Gencer, A.; Demirköz, B.; Efthymiopoulos, I.; Yiğitoğlu, M.

2016-07-01

Electronic components must be tested to ensure reliable performance in high radiation environments such as Hi-Limu LHC and space. We propose a defocusing beam line to perform proton irradiation tests in Turkey. The Turkish Atomic Energy Authority SANAEM Proton Accelerator Facility was inaugurated in May 2012 for radioisotope production. The facility has also an R&D room for research purposes. The accelerator produces protons with 30 MeV kinetic energy and the beam current is variable between 10 μA and 1.2 mA. The beam kinetic energy is suitable for irradiation tests, however the beam current is high and therefore the flux must be lowered. We plan to build a defocusing beam line (DBL) in order to enlarge the beam size, reduce the flux to match the required specifications for the irradiation tests. Current design includes the beam transport and the final focusing magnets to blow up the beam. Scattering foils and a collimator is placed for the reduction of the beam flux. The DBL is designed to provide fluxes between 107 p /cm2 / s and 109 p /cm2 / s for performing irradiation tests in an area of 15.4 cm × 21.5 cm. The facility will be the first irradiation facility of its kind in Turkey.

Currently developing opportunities in food irradiation and modern irradiation facilities

International Nuclear Information System (INIS)

Wanke, R.

1997-01-01

I. Factor currently influencing advancing opportunities for food irradiation include: heightened incidence and awareness of food borne illnesses and causes. Concerns about ensuring food safety in international as well as domestic trade. Regulatory actions regarding commonly used fumigants/pesticides e.g. Me Br. II. Modern irradiator design: the SteriGenics M ini Cell . A new design for new opportunities. Faster installation of facility. Operationally and space efficient. Provides local o nsite control . Red meat: a currently developing opportunity. (Author)

Revision of the recommended international general standard for irradiated foods and of the recommended international code of practice for the operation of radiation facilities used for the treatment of foods

International Nuclear Information System (INIS)

1981-11-01

In view of the findings and statements of the Joint FAO/IAEA/WHO Expert Committee on the Wholesomeness of Irradiated Food, convened in Geneva from 27 October to 3 November 1980, a Consultation Group, convened in Geneva from 1 to 3 July 1981 suggested the revision of the Recommended International General Standard for Irradiated Foods and of the Recommended International Code of Practice for the Operation of Radiation Facilities. The proposed changes are given and justified and the revised wording of the documents presented

Facilities for studying radiation damage in nonmetals during irradiation

International Nuclear Information System (INIS)

Levy, P.W.

1984-08-01

Two facilities have been developed for making optical absorption, luminescence and other measurements on a single sample before, during and after irradiation. One facility uses 60 Co gamma rays and the other 0.5 to 3 MeV electrons from an accelerator. Optical relays function as spectrophotometers, luminescenc detectors, etc. All radiation sensitive components are outside of walk-in irradiation chambers; all measurement control and data recording is computerized. Irradiations are made at controlled temperatures between 5K and 900 0 C. The materials studied include glasses, quartz, alkali halides (especially natural rock salt), organic crystals, etc. As determined from color center measurements the damage formation rate in all materials studied at 25 0 C or above is strongly temperature dependent. The defect concentration during irradiation is usually much greater than that measured after irradiation. The fraction of defects annealing after irradiation and the annealing rate usually increases as the irradiation temperature increases. The completed studies demonstrate that, in most cases, the extent of maximum damage and the damage formation and annealing kinetics can be determined only by making measurements during irradiation

Monte Carlo studies for irradiation process planning at the Portuguese gamma irradiation facility

International Nuclear Information System (INIS)

Oliveira, C.; Salgado, J.; Botelho, M.L.M. Luisa; Ferreira, L.M.

2000-01-01

The paper describes a Monte Carlo study for planning the irradiation of test samples for microbiological validation of distinct products in the Portuguese Gamma Irradiation Facility. Three different irradiation geometries have been used. Simulated and experimental results are compared and good agreement is observed. It is shown that Monte Carlo simulation improves process understanding, predicts absorbed dose distributions and calculates dose uniformity in different products. Based on these results, irradiation planning of the product can be performed

The Advanced Test Reactor Irradiation Facilities and Capabilities

International Nuclear Information System (INIS)

S. Blaine Grover; Raymond V. Furstenau

2007-01-01

The Advanced Test Reactor (ATR) is one of the world's premiere test reactors for performing long term, high flux, and/or large volume irradiation test programs. The ATR is a very versatile facility with a wide variety of experimental test capabilities for providing the environment needed in an irradiation experiment. These different capabilities include passive sealed capsule experiments, instrumented and/or temperature-controlled experiments, and pressurized water loop experiment facilities. The ATR has enhanced capabilities in experiment monitoring and control systems for instrumented and/or temperature controlled experiments. The control systems utilize feedback from thermocouples in the experiment to provide a custom blended flowing inert gas mixture to control the temperature in the experiments. Monitoring systems have also been utilized on the exhaust gas lines from the experiment to monitor different parameters, such as fission gases for fuel experiments, during irradiation. ATR's unique control system provides axial flux profiles in the experiments, unperturbed by axially positioned control components, throughout each reactor operating cycle and over the duration of test programs requiring many years of irradiation. The ATR irradiation positions vary in diameter from 1.6 cm (0.625 inches) to 12.7 cm (5.0 inches) over an active core length of 122 cm (48.0 inches). Thermal and fast neutron fluxes can be adjusted radially across the core depending on the needs of individual test programs. This paper will discuss the different irradiation capabilities available and the cost/benefit issues related to each capability. Examples of different experiments will also be discussed to demonstrate the use of the capabilities and facilities at ATR for performing irradiation experiments

Currently developing opportunities in food irradiation and modern irradiation facilities

Energy Technology Data Exchange (ETDEWEB)

Wanke, R [Director Business Development. SteriGenics International Inc. 17901 East Warren Avenue No. 4, Detroit, Michigan 48224-1333 (United States)

1998-12-31

I. Factor currently influencing advancing opportunities for food irradiation include: heightened incidence and awareness of food borne illnesses and causes. Concerns about ensuring food safety in international as well as domestic trade. Regulatory actions regarding commonly used fumigants/pesticides e.g. Me Br. II. Modern irradiator design: the SteriGenics {sup M}ini Cell{sup .} A new design for new opportunities. Faster installation of facility. Operationally and space efficient. Provides local {sup o}nsite control{sup .} Red meat: a currently developing opportunity. (Author)

Currently developing opportunities in food irradiation and modern irradiation facilities

Energy Technology Data Exchange (ETDEWEB)

Wanke, R. [Director Business Development. SteriGenics International Inc. 17901 East Warren Avenue No. 4, Detroit, Michigan 48224-1333 (United States)

1997-12-31

I. Factor currently influencing advancing opportunities for food irradiation include: heightened incidence and awareness of food borne illnesses and causes. Concerns about ensuring food safety in international as well as domestic trade. Regulatory actions regarding commonly used fumigants/pesticides e.g. Me Br. II. Modern irradiator design: the SteriGenics {sup M}ini Cell{sup .} A new design for new opportunities. Faster installation of facility. Operationally and space efficient. Provides local {sup o}nsite control{sup .} Red meat: a currently developing opportunity. (Author)

Low Current Irradiation Facility at KOMAC

Energy Technology Data Exchange (ETDEWEB)

Min, Yi-Sub; Park, Sung-Kyun; Park, Jeong-Min; Cho, Yong-Sub [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2016-10-15

Korea Multi-purpose Accelerator Complex (KOMAC) is branched off from Korea Atomic Energy Research Institute (KAERI). The 100 MeV linear proton accelerator as well as the various types of the ion accelerator have been operated and developed in KOMAC. The operation of these accelerators included in the KOMAC site should be approved by Nuclear Safety and Security Committee (NSSC). To aims at the operation in 2017, a research facility to irradiate low current beam has been prepared. The radiation safety analysis was performed again to adopt with the change. As a result of these changes, an easy access into the facility will be got to. This paper introduces the activity in terms of the radiation safety for these accelerator operations. Radiation analysis was performed depending on the planned changes, and it was confirmed that there is no effect by the changes. This facility is expected to be made the best use at a field which could be irradiated with proton beam which has an energy up to 100 MeV and current up to 10 nA.

Fusion Materials Irradiation Test Facility: experimental capabilities and test matrix

International Nuclear Information System (INIS)

Opperman, E.K.

1982-01-01

This report describes the experimental capabilities of the Fusion Materials Irradiation Test Facility (FMIT) and reference material specimen test matrices. The description of the experimental capabilities and the test matrices has been updated to match the current single test cell facility ad assessed experimenter needs. Sufficient detail has been provided so that the user can plan irradiation experiments and conceptual hardware. The types of experiments, irradiation environment and support services that will be available in FMIT are discussed

Innovations to increase throughput of the multipurpose irradiation facility

Energy Technology Data Exchange (ETDEWEB)

Cabalfin, Estelita G; Lanuza, Luvimina G; Maningas, Aurelio L; Solomon, Haydee M [Irradiation Services Unit, Nuclear Services and Training Division, Philippine Nuclear Research Institute, Quezon City (Philippines)

1998-07-01

With the installation and operation of the PNRI [Philippine Nuclear Research Institute] multipurpose irradiation facility, several local industries are now aware of, and in fact using gamma radiation for sterilization or decontamination of medical and pharmaceutical products, packaging materials and for food preservation. However, the multipurpose irradiation facility has limited capacity and capability, since this was designed as a pilot scale irradiator for research and development. To meet the increasing demand of gamma irradiation service, a new product handling system was locally designed, fabricated and installed. Performance, in terms of total loading and more importantly, radiation dose distribution of the new product handling system, was evaluated. An increase in product throughput was realized effectively with the new product handling system. (Author)

Innovations to increase throughput of the multipurpose irradiation facility

International Nuclear Information System (INIS)

Cabalfin, Estelita G.; Lanuza, Luvimina G.; Maningas, Aurelio L.; Solomon, Haydee M.

1998-01-01

With the installation and operation of the PNRI [Philippine Nuclear Research Institute] multipurpose irradiation facility, several local industries are now aware of, and in fact using gamma radiation for sterilization or decontamination of medical and pharmaceutical products, packaging materials and for food preservation. However, the multipurpose irradiation facility has limited capacity and capability, since this was designed as a pilot scale irradiator for research and development. To meet the increasing demand of gamma irradiation service, a new product handling system was locally designed, fabricated and installed. Performance, in terms of total loading and more importantly, radiation dose distribution of the new product handling system, was evaluated. An increase in product throughput was realized effectively with the new product handling system. (Author)

Installation of the water environment irradiation facility for the IASCC research under the BWR/PWR irradiation environment (2)

International Nuclear Information System (INIS)

Magome, Hirokatsu; Okada, Yuji; Hanawa, Hiroshi; Sakuta, Yoshiyuki; Kanno, Masaru; Iida, Kazuhiro; Ando, Hitoshi; Yonekawa, Akihisa; Ueda, Haruyasu; Shibata, Mitsunobu

2014-07-01

In Japan Atomic Energy Agency, in order to solve the problem in the long-term operation of a light water reactor, preparation which does the irradiation experiment of light-water reactor fuel and material was advanced. JMTR stopped after the 165th operation cycle in August 2006, and is advancing renewal of the irradiation facility towards re-operation. The material irradiation test facility was installed from 2008 fiscal year to 2012 fiscal year in JMTR. This report summarizes manufacture and installation of the material irradiation test facility for IASCC research carried out from 2012 to 2014 in the follow-up report reported before (JAEA-Technology 2013-019). (author)

Irradiation Facilities of the Takasaki Advanced Radiation Research Institute

Directory of Open Access Journals (Sweden)

Satoshi Kurashima

2017-03-01

Full Text Available The ion beam facility at the Takasaki Advanced Radiation Research Institute, the National Institutes for Quantum and Radiological Science and Technology, consists of a cyclotron and three electrostatic accelerators, and they are dedicated to studies of materials science and bio-technology. The paper reviews this unique accelerator complex in detail from the viewpoint of its configuration, accelerator specification, typical accelerator, or irradiation technologies and ion beam applications. The institute has also irradiation facilities for electron beams and 60Co gamma-rays and has been leading research and development of radiation chemistry for industrial applications in Japan with the facilities since its establishment. The configuration and utilization of those facilities are outlined as well.

Facility for gamma irradiations of cultured cells at low dose rates: design, physical characteristics and functioning

International Nuclear Information System (INIS)

Esposito, Giuseppe; Anello, Pasquale; Pecchia, Ilaria; Tabocchini, Maria Antonella; Campa, Alessandro

2016-01-01

We describe a low dose/dose rate gamma irradiation facility (called LIBIS) for in vitro biological systems, for the exposure, inside a CO_2 cell culture incubator, of cells at a dose rate ranging from few μGy/h to some tens of mGy/h. Three different "1"3"7Cs sources are used, depending on the desired dose rate. The sample is irradiated with a gamma ray beam with a dose rate uniformity of at least 92% and a percentage of primary 662 keV photons greater than 80%. LIBIS complies with high safety standards. - Highlights: • A gamma irradiation facility for chronic exposures of cells was set up at the Istituto Superiore di Sanità. • The dose rate uniformity and the percentage of primary 662 keV photons on the sample are greater than 92% and 80%, respectively. • The GEANT4 code was used to design the facility. • Good agreement between simulation and experimental dose rate measurements has been obtained. • The facility will allow to safely investigate different issues about low dose rate effects on cultured cells.

Neutronics analysis of International Fusion Material Irradiation Facility (IFMIF). Japanese contributions

International Nuclear Information System (INIS)

Oyama, Yukio; Noda, Kenji; Kosako, Kazuaki.

1997-10-01

In fusion reactor development for demonstration reactor, i.e., DEMO, materials tolerable for D-T neutron irradiation are absolutely required for both mechanical and safety point of views. For this requirement, several kinds of low activation materials were proposed. However, experimental data by actual D-T fusion neutron irradiation have not existed so far because of lack of fusion neutron irradiation facility, except fundamental radiation damage studies at very low neutron fluence. Therefore such a facility has been strongly requested. According to agreement of need for such a facility among the international parties, a conceptual design activity (CDA) of International Fusion Material Irradiation Facility (IFMIF) has been carried out under the frame work of the IEA-Implementing Agreement. In the activity, a neutronics analysis on irradiation field optimization in the IFMIF test cell was performed in three parties, Japan, US and EU. As the Japanese contribution, the present paper describes a neutron source term as well as incident deuteron beam angle optimization of two beam geometry, beam shape (foot print) optimization, and dpa, gas production and heating estimation inside various material loading Module, including a sensitivity analysis of source term uncertainty to the estimated irradiation parameters. (author)

Flux and energy deposition distribution studies inside the irradiation room of the portuguese 60Co irradiation facility

International Nuclear Information System (INIS)

Portugal, Luis; Oliveira, Carlos

2008-01-01

Full text: In December 2003 the irradiator of the Portuguese 60 Co irradiation facility, UTR, was replenished. Eighteen new sources were loaded and the older ones (156) were rearranged. The result was an irradiator with about 10.2 P Bq of total activity. The active area of the irradiator has also increased. Now it uses twenty five of the thirty tubes of the source rack, nine more than in the previous geometry. This facility was designed mainly for sterilisation of medical devices. However it is also used for the irradiation of other products such as cork stoppers, plastics and a limited number of food and feed. The purpose of this work is to perform dosimetric studies inside the irradiation room of a 60 Co irradiation facility, particularly, the flux and energy deposition distributions. The MCNPX code was used for the simulation of the facility. The track average mesh tally capabilities of MCNPX were used to plot the photon flux and energy deposition distributions. This tool provides a fast way for flux and energy deposition mapping. The absorbed dose distribution near the walls of the irradiation room was also calculated. Instead of using meshtallys as before, the average absorbed dose inside boxes lined with the walls was determined and afterwards a plot of its distribution was made. The absorbed dose rates obtained ranged from 5 to 500 Gy.h -1 depending on material being irradiated in process and the location on the wall. These positions can be useful for fixed irradiation purposes. Both dosimetric studies were done considering two different materials being irradiated in the process: cork stoppers and water, materials with quite different densities (0.102 and 1 g.cm-3, respectively). These studies showed some important characteristics of the radiation fields inside the irradiation room, namely its spatial heterogeneity. Tunnelling and shadow effects were enhanced when the product boxes increases its density. Besides a deeper dosimetric understanding of the

Cobalt 60 commercial irradiation facilities

International Nuclear Information System (INIS)

West, G.

1985-01-01

The advantage of using cobalt 60 for ionizing treatment is that it has excellent penetration. Gamma plants are also very efficient, in as much as there is very little mechanical or electrical equipment in a gamma irradiation facility. The average efficiency of a gamma plant is usually around 95% of all available processing time

42 CFR 493.1101 - Standard: Facilities.

Science.gov (United States)

2010-10-01

... 42 Public Health 5 2010-10-01 2010-10-01 false Standard: Facilities. 493.1101 Section 493.1101... (CONTINUED) STANDARDS AND CERTIFICATION LABORATORY REQUIREMENTS Facility Administration for Nonwaived Testing § 493.1101 Standard: Facilities. (a) The laboratory must be constructed, arranged, and maintained to...

Construction plan of ion irradiation facility in JAERI

International Nuclear Information System (INIS)

Tanaka, Ryuichi

1987-01-01

The Takasaki Radiation Chemistry Research Establishment of Japan Atomic Energy Research Institute (JAERI) started the construction of an ion irradiation facility to apply ion beam to the research and development of radiation resistant materials for severe environment, the research on biotechnology and new functional materials. This project was planned as ion beam irradiation becomes an effective means for the research on fundamental physics and advanced technology, and the national guideline recently emphasizes the basic and pioneering field in research and development. This facility comprises an AVF cyclotron with an ECR ion source (maximum proton energy: 90 MeV), a 3 MV tandem accelerator, a 3 MV single end type Van de Graaf accelerator and a 400 kV ion implanter. In this report, the present status of planning the accelerators and the facility to be constructed, the outline of research plan, the features of the accelerators, and the beam characteristics are described. In this project, the research items are divided into the materials for space environment, the materials for nuclear fusion reactors, biotechnology, new functional materials, and ion beam technology. The ion beams required for the facility are microbeam, pulsed beam, multiple beam, neutron beam and an expanded irradiation field. (Kako, I.)

Fusion Materials Irradiation Test Facility

International Nuclear Information System (INIS)

Kemp, E.L.; Trego, A.L.

1979-01-01

A Fusion Materials Irradiation Test Facility is being designed to be constructed at Hanford, Washington, The system is designed to produce about 10 15 n/cm-s in a volume of approx. 10 cc and 10 14 n/cm-s in a volume of 500 cc. The lithium and target systems are being developed and designed by HEDL while the 35-MeV, 100-mA cw accelerator is being designed by LASL. The accelerator components will be fabricated by US industry. The total estimated cost of the FMIT is $105 million. The facility is scheduled to begin operation in September 1984

Automatically controlled facilities for irradiation of silicon crystals at the Rossendorf Research Reactor

International Nuclear Information System (INIS)

Ross, R.

1988-01-01

This report describes the facilities for neutron transmutation doping of silicon in GDR. The irradiation of silicon single crystals began at Rossendorf in 1978 with simple equipment. Only a small amount of silicon could be irradiated in it. The fast increasing need of NTD-silicon made it necessary to design and construct new and better facilities. The new facilities are capable of irradiating silicon from 2'' to 3'' in diameter. The irradiation process takes place automatically with the assistance of a computer. Material produced has an axial homogeneity of ± 7%. Irradiation riggs, techniques, irradiation control and quality control are discussed. (author). 4 figs

Gamma irradiation for sewage treatment at US army facilities

International Nuclear Information System (INIS)

Van den Berg, A.J.; Hollis, H.D.; Musselman, H.D.; Woodbridge, D.D.

1975-01-01

The US Army Corps of Engineers has been sponsoring research for many years on the use of gamma irradiation for disinfection and sterilization of sewage plant effluents. Initial research was directed to laboratory experiments using sterile solutions to determine the effects of gamma irradiation on E. coli, M-pyogenes and M-smegmatis organisms, and on the chemical constituents of sewage such as phenols, surfactants and pesticides. The results of the initial research warranted further study using municipal sewage secondary effluent as test samples. Current research is directed towards investigating the effects of radiation on the constituents of sewage sludge and on the cyst stage of the amoebic protozoa. Consideration has been given by the Corps to the management of waste-waters by disposal on land. Legal and medical reasons dictate that the plant effluents be sterilized before being used as fertilizers and soil conditioners. Gamma radiation from isotopic sources appears to be the best source of sterilizing energy for Army waste-water disposal. The Corps of Engineers is considering the construction of an experimental gamma irradiation pilot facility to validate laboratory experimental work and to establish design criteria for operating plants. The data obtained will provide a basis for performing detailed cost effectiveness studies on gamma irradiation as a method to treat secondary plant effluent. In addition, optimization work will be conducted to determine where in the sewage treatment cycle the use of gamma irradiation will produce the best results in meeting current and anticipated standards. (author)

Proposal for an irradiation facility at the TAEK SANAEM Proton Accelerator Facility

Science.gov (United States)

Demirköz, B.; Gencer, A.; Kiziloren, D.; Apsimon, R.

2013-12-01

Turkish Atomic Energy Authority's (TAEK's) Proton Accelerator Facility in Ankara, Turkey, has been inaugurated in May 2012 and is under the process of being certified for commercial radio-isotope production. Three of the four arms of the 30 MeV cyclotron are being used for radio-isotope production, while the fourth is foreseen for research and development of novel ideas and methods. The cyclotron can vary the beam current between 12 μA and 1.2 mA, sufficient for irradiation tests for semiconductor materials, detectors and devices. We propose to build an irradiation facility in the R&D room of this complex, open for use to the international detector development community.

Fast-neutron dosimetry in the seed-irradiation facility, ASTRA reactor, Seibersdorf

International Nuclear Information System (INIS)

Ahnstroem, G.; Burtscher, A.; Casta, J.

1967-01-01

An important part of the co-ordinated programme on the neutron irradiation of seeds has been the construction of a fast-neutron irradiation facility for swimming-pool reactors. This facility was installed around 70 cm from the core in the ASTRA reactor swimming-pool at the end of December, 1966. Also, for this programme a pair of constant potential ionization chambers have been constructed at the Institute of Biochemistry, Stockholm University. These chambes are of the type described in the technical annex and are the same size as the seed-irradiation vials to be used in the seed-irradiation container (diam. =15 mm, length = 60 mm). Some preliminary dosimetry experiments were undertaken to test the irradiation facility and the ionization chambers, and to investigate the usefulness of the dosimetry instructions in the Technical Annex. The results of these experiments are discussed in this paper. 3 refs, 6 figs, 7 tabs

Lessons learned from accidents in industrial irradiation facilities

International Nuclear Information System (INIS)

1996-01-01

Use of ionizing radiation in medicine, industry and research for technical development continues to increase throughout the world. One application with a high growth rate is irradiation suing high energy gamma photons and electron beams. There are currently more than 160 gamma irradiation facilities and over 600 electron beam facilities in operation in almost all IAEA Member States. The most common uses of these facilities are to sterilize medical and pharmaceutical products, to preserve foodstuffs, to synthesize polymers and to eradicate insects. Although this industry has a good safety record, there is a potential for accidents with serious consequences to human health because of the high dose rates produced by these sources. Fatal accidents have occurred at installations in both developed and developing countries. Such accidents have prompted a review of several accidents, including five with fatalities, by a team of manufacturers, regulatory authorities and operating organizations. Having looked closely at the circumstances of each accident and the apparent deficiencies in design, safety and regulatory systems and personnel performance, the team made a number of recommendations on the ways in which the safety of irradiators can be improved. The findings of extensive research pertaining to the lessons that can be learned from irradiator accidents are presented. This publication is intended for manufacturers, regulatory authorities and operating organizations dealing with industrial irradiators. It was drafted by J.E. Glen, United States Nuclear Regulatory Commission, United States of America, and P. Zuniga-Bello, Consejo Nacional de Ciencia y Technologia, Mexico

Gamma irradiation facility: Evaluation of operational modes

International Nuclear Information System (INIS)

Adesanmi, C.A.; Ali, M.S.; Shonowo, O.A.; Akueche, E.C.; Sadare, O.O.; Mustapha, T.K.; Yusuf, U.; Inyanda, A.K.

2007-01-01

The multipurpose Gamma Irradiation Facility (GIF) at the Nuclear Technology Centre (NTC), Sheda Science and Technology Complex (SHETSCO), Abuja, Nigeria is designed as a semi-commercial plant with facilities for research and development (R and D). The design takes into account the different needs of the various research applications which require a wide dose range, a variety of techniques, different product sizes, shapes, mass, volume, densities and types. Programmable doses are used for food irradiation (0.04 - 10 kGy), biological seed mutation breeding and sterile insect technique (STI) (0.01- 5 kGy) sterilization of medical, pharmaceutical and cosmetic products and packages (up to 25 kGy) and cross-linking of polymers (up to 100 kGy). The six different modes of operations (sample elevator, stationary, swiveling, 2-path inner lane and 2-path outer lane and 4-path line) were evaluated. The dose range, mass range and range of irradiation time practicable were established and advantages for radiation processing of food and industrial products were enumerated for the six modes of operations for the first time

Irradiation facilities at the advanced neutron source

International Nuclear Information System (INIS)

West, C.D.

1992-01-01

The Advanced Neutron Source (ANS) is a facility, centered around a new 330MW(f) heavy-water cooled and reflected research reactor, proposed for construction at Oak Ridge. The main scientific justification for the new source is the United States' need for increased capabilities in neutron scattering and other neutron beam research, but the technical objectives of the project also cater for the need to replace the irradiation facilities at the aging High Flux Isotope Reactor and to provide other research capabilities to the scientific community. This document provides a description of the ANS facilities

The Codex standard and code for irradiated foods

International Nuclear Information System (INIS)

Erwin, L.

1985-01-01

A brief background on the work by the Codex Alimentarius Commission on irradiated foods is given. An Australian model food standard for irradiated foods, based on the Codex standard, is being developed

γ irradiation facility at ENEA-Casaccia Centre (Rome)

International Nuclear Information System (INIS)

Baccaro, S.; Cecilia, A.; Pasquali, A.

2005-09-01

A description of Calliope γ irradiation plant of ENEA-Casaccia Centre (Rome) is presented in this paper. In particular the main characteristics of the irradiation facility necessary to define time and irradiation procedure are summarised. The plant is equipped with dosimetric services that evaluate absorbed doses in materials during irradiation. Dosimetric techniques used are Fricke, RedPerspex and alanine-ESR dosimetries. In the first case, absorbed dose is determined by chemical changes induced in a solution by irradiation and the second method uses the optical density increase induced in dosimeter by irradiation. The last method is based on the analysis of the free radical concentration induced in α-alanine amino-acid during irradiation. The paper provides also a simulation of the γ radiation field inside the irradiation cell realised by using FLUKA code, which includes a good description of the electromagnetic physics down to about 0.1 KeV [it

Dosimetry and operation of irradiation facilities

International Nuclear Information System (INIS)

Vidal, P.E.

1985-01-01

The industrial use of ionizing radiation has required, from the very first, the measurement of delivered and absorbed doses; hence the necessity of providing dosimetric systems. Laboratories, scientists, industries and potential equipment manufacturers have all collaborated in this new field of activity. Dosimetric intercomparisons have been made by each industry at their own facilities and in collaboration with specialists, national organizations and the IAEA. Dosimetry has become a way of ensuring that treatment by irradiation has been carried out in accordance with the rules. It has become in effect assurance of quality. Routine dosimetry should determine a maximum and minimum dose. Numerous factors play a part in dosimetry. Industry is currently in possession of routine dosimetric systems that are sufficiently accurate, fairly easy to handle and reasonable in cost, thereby satisfying all the requirements of industry and the need for control. Dosimetry is important in the process of marketing irradiated products. The operator of an industrial irradiation facility bases his dosimetry on comparison with reference systems. Research aimed at simplifying the practice of routine dosimetry should be continued. New physical and chemical techniques will be incorporated into systems already in use. The introduction of microcomputers into the operation of radiation facilities has increased the value of dosimetry and made the conditions of treatment more widespread. Stress should be placed on research in several areas apart from reference systems, for example: dosimetric systems at temperatures from +8 deg. C to -45 deg. C, over the dose range 100 krad to a little more than 1 Mrad, liquids and fluidized solids carried at high speed through ducts, thin-film liquids circulating at a high flow rate, and various other problems. (author)

Synthetic multi-element standards: a good tool for calibration and quality control of irradiation facilities used for neutron activation analysis

International Nuclear Information System (INIS)

Vermaercke, P.

2007-01-01

Neutron activation analysis (NAA) is a physical technique used for the absolute measurement of the concentration of substances in solids and liquids. The method uses neutron irradiation which is commonly realised using a nuclear reactor in order to activate (make radioactive) different isotopes of the elements present in the sample. The radionuclides produced in this way emit gamma-rays that are characteristic of the elements present in the sample. Using gamma-ray spectrometry these radionuclides can then be identified and quantified, and hence their concentration in the sample can be determined. Although NAA is a straightforward method it requires a sound control of the many physical parameters involved to obtain accurate results and to guarantee a set accuracy in routine analysis. The accuracy of NAA depends on the specific measurement method used. One can perform NAA in a relative way by co-irradiating a known standard and the unknown sample in the same conditions and by comparing the ratio of gamma-rays they emit. Relative NAA has limited applicability since it requires reference standards with a comparable composition as the unknown. A more generally applicable method is the k0-NAA method. In the k0-NAA method all measurements are relative to the element Au resulting in 198Au when irradiated. The k0-NAA method further relies on the fact that the neutron energy spectrum produced in a given position in the reactor can be parameterised with two parameters: the shape factor of the epithermal neutron flux, indicating the deviation of the epithermal neutron spectrum from the ideal 1/E shape approximated by a 1/E1+a distribution, with E the neutron energy; f: the thermal-to-epithermal neutron flux ratio. The parameters f and a are characteristic for the irradiation facility (reactor and irradiation channels) and may change or fluctuate in time according to the irradiation conditions. The way elements activate (become radioactive) when interacting with neutrons is

Radiation Safety of Gamma, Electron and X Ray Irradiation Facilities. Specific Safety Guide (Spanish Edition)

International Nuclear Information System (INIS)

2015-01-01

The objective of this Safety Guide is to provide recommendations on how to meet the requirements of the BSS with regard to irradiation facilities. This Safety Guide provides specific, practical recommendations on the safe design and operation of gamma, electron and X ray irradiators for use by operating organizations and the designers of these facilities, and by regulatory bodies. SCOPE. The facilities considered in this publication include five types of irradiator, whether operated on a commercial basis or for research and development purposes. This publication is concerned with radiation safety issues and not with the uses of irradiators, nor does it cover the irradiation of product or its quality management. The five types of irradiator are: - Panoramic dry source storage irradiators; - Underwater irradiators, in which both the source and the product being irradiated are under water; - Panoramic wet source storage irradiators; - Electron beam irradiation facilities, in which irradiation is performed in an area that is potentially accessible to personnel, but that is kept inaccessible during the irradiation process; - X ray irradiation facilities, in which irradiation is performed in an area that is potentially accessible to personnel, but that is kept inaccessible during the irradiation process. Consideration of non-radiation-related risks and of the benefits resulting from the operation of irradiators is outside the scope of this Safety Guide. The practices of radiotherapy and radiography are also outside the scope of this Safety Guide. Category I gamma irradiators (i.e. 'self-shielded' irradiators) are outside the scope of this Safety Guide

Final report of the HFIR [High Flux Isotope Reactor] irradiation facilities improvement project

International Nuclear Information System (INIS)

Montgomery, B.H.; Thoms, K.R.; West, C.D.

1987-09-01

The High-Flux Isotope Reactor (HFIR) has outstanding neutronics characteristics for materials irradiation, but some relatively minor aspects of its mechanical design severely limited its usefulness for that purpose. In particular, though the flux trap region in the center of the annular fuel elements has a very high neutron flux, it had no provision for instrumentation access to irradiation capsules. The irradiation positions in the beryllium reflector outside the fuel elements also have a high flux; however, although instrumented, they were too small and too few to replace the facilities of a materials testing reactor. To address these drawbacks, the HFIR Irradiation Facilities Improvement Project consisted of modifications to the reactor vessel cover, internal structures, and reflector. Two instrumented facilities were provided in the flux trap region, and the number of materials irradiation positions in the removable beryllium (RB) was increased from four to eight, each with almost twice the available experimental space of the previous ones. The instrumented target facilities were completed in August 1986, and the RB facilities were completed in June 1987

Two-faces stationary irradiation method and dosimetric considerations for radiation processing at the multipurpose gamma irradiation facility / IPEN-CNEN

International Nuclear Information System (INIS)

Santos, Paulo S.; Vasquez, Pablo A.S.

2015-01-01

Over the last ten years, the Multipurpose Gamma Irradiation Facility of the Nuclear and Energy Research Institute - IPEN/CNEN located inside the Sao Paulo University campus has been providing services on radiation processing, especially for sterilization of health care and disposable medical products as well as support to research studies on modification of physical, chemical and biological properties of several materials. Placed at the same campus operates an extremely important radiopharmaceutical production facility when almost all disposable supplies used to produce medical products as the technetium-99m are continuously sterilized by gamma radiation. Many university biomedical research laboratories specially those working with equipment for cell cultures and vaccine production also make use of the gamma sterilization. Animal feed and shavings used by certified bioteries are routinely disinfected. Alternative underwater irradiation methods were developed to meet the demand of gemstone color enhancement. Human tissues including bone, skin, amniotic membranes, tendons, and cartilage belonging to National Banks are usually irradiated too. Different kind of polymers, hydrogels, foods as well native fruits, have been irradiated in this facility. Cultural heritage objects as books, paintings and furniture are disinfected routinely by gamma radiation. The success of the implementation of radiation processing in this facility is due to research and development of irradiation and dosimetry methods suitable for each condition. In this work are presented some considerations about the distribution dose and the two-faces stationary irradiation method developed and validated for this facility. (author)

Two-faces stationary irradiation method and dosimetric considerations for radiation processing at the multipurpose gamma irradiation facility / IPEN-CNEN

Energy Technology Data Exchange (ETDEWEB)

Santos, Paulo S.; Vasquez, Pablo A.S., E-mail: psantos@ipen.br, E-mail: pavsalva@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

2015-07-01

Over the last ten years, the Multipurpose Gamma Irradiation Facility of the Nuclear and Energy Research Institute - IPEN/CNEN located inside the Sao Paulo University campus has been providing services on radiation processing, especially for sterilization of health care and disposable medical products as well as support to research studies on modification of physical, chemical and biological properties of several materials. Placed at the same campus operates an extremely important radiopharmaceutical production facility when almost all disposable supplies used to produce medical products as the technetium-99m are continuously sterilized by gamma radiation. Many university biomedical research laboratories specially those working with equipment for cell cultures and vaccine production also make use of the gamma sterilization. Animal feed and shavings used by certified bioteries are routinely disinfected. Alternative underwater irradiation methods were developed to meet the demand of gemstone color enhancement. Human tissues including bone, skin, amniotic membranes, tendons, and cartilage belonging to National Banks are usually irradiated too. Different kind of polymers, hydrogels, foods as well native fruits, have been irradiated in this facility. Cultural heritage objects as books, paintings and furniture are disinfected routinely by gamma radiation. The success of the implementation of radiation processing in this facility is due to research and development of irradiation and dosimetry methods suitable for each condition. In this work are presented some considerations about the distribution dose and the two-faces stationary irradiation method developed and validated for this facility. (author)

How to improve the irradiation conditions for the International Fusion Materials Irradiation Facility

CERN Document Server

Daum, E

2000-01-01

The accelerator-based intense D-Li neutron source International Fusion Materials Irradiation Facility (IFMIF) provides very suitable irradiation conditions for fusion materials development with the attractive option of accelerated irradiations. Investigations show that a neutron moderator made of tungsten and placed in the IFMIF test cell can further improve the irradiation conditions. The moderator softens the IFMIF neutron spectrum by enhancing the fraction of low energy neutrons. For displacement damage, the ratio of point defects to cascades is more DEMO relevant and for tritium production in Li-based breeding ceramic materials it leads to a preferred production via the sup 6 Li(n,t) sup 4 He channel as it occurs in a DEMO breeding blanket.

Development of post-irradiation test facility for domestic production of 99Mo

International Nuclear Information System (INIS)

Taguchi, Taketoshi; Yonekawa, Minoru; Kato, Yoshiaki; Kurosawa, Makoto; Nishikata, Kaori; Ishida, Takuya; Kawamata, Kazuo

2013-01-01

JMTR focus on the activation method. By carrying out the preliminary tests using irradiation facilities existing, and verification tests using the irradiation facility that has developed in the cutting-edge research and development strategic strengthening business, as irradiation tests towards the production of 99 Mo, we have been conducting research and development that can contribute to supply about 25% for 99 Mo demand in Japan and the stable supply of radiopharmaceutical. This report describes a summary of the status of the preliminary tests for the production of 99 Mo: Maintenance of test equipment in the facility in JMTR hot laboratory in preparation for research and development for the production of 99 Mo in JMTR and using MoO 3 pellet irradiated at Kyoto University Research Reactor Institute (KUR). (author)

Development of the flow control irradiation facility for JOYO

International Nuclear Information System (INIS)

Soroi, Masatoshi; Miyakawa, Shun-ichi

1998-05-01

This report describes the present situation and problems with the development of the flow control irradiation facility (FLORA). The purpose of FLORA is to run the cladding breach (RTCB) irradiation test under loss of flow conditions in the experimental fast reactor 'JOYO'. FLORA is a facility like FPTF (Fuel Performance Test Facility) plus BFTF (Breached Fuel Test Facility) in EBR-II, USA. The technical feature of FLORA is its annular linear induction pump (A-LIP), which was developed in response to a need identified through the experiences in the mechanical flow control of FPTF. We have already designed the basic system facility of FLORA for the JOYO MK-II core. However, to put FLORA to practical use in the future, we have to confirm the stability of the JOYO MK-III core condition, solve problems and improve the design. We are going to freeze and review the FLORA project, taking into consideration the fuel development situation and the research project of JOYO MK-III core. (J.P.N.)

NRI experimental facility for the testing of irradiation assisted stress corrosion cracking

International Nuclear Information System (INIS)

Ruscak, M.; Chvatal, P.; Zamboch, M.

1998-01-01

IASCC influencing reactor internals of both BWR and PWR reactors is a complex phenomenon covering influences of material structure, neutron fluence, neutron flux, chemistry of environment, gamma radiation and mechanical stress. To evaluate such degradation, tests should be performed under conditions similar to those in real structure. Nuclear Research Institute has built several experimental facilities in order to be able to test IASCC degradation of materials. Basically, reactor water loops, both PWR and BWR, could be used to model environmental conditions including gamma and neutron irradiation. Pre-irradiation can be done in irradiation channels under well controlled temperature conditions. During the experiment, in-pile conditions can be compared with those out of pile. It enables to clarify pure influence of irradiation. For testing of irradiated specimens, hot cell facility has been developed for slow strain rate tests. The paper will show all above mentioned facilities as well as some of the results observed with them. (author)

Construction of irradiated material examination facility-basic design

International Nuclear Information System (INIS)

Ro, Seung Gy; Kim, Eun Ka; Hong, Gye Won; Herr, Young Hoi; Hong, Kwon Pyo; Lee, Myeong Han; Baik, Sang Youl; Choo, Yong Sun; Baik, Seung Je

1989-02-01

The basic design of the hot cell facility which has the main purpose of doing mechanical and physical property tests of irradiated materials, the examination process, and the annexed facility has been made. Also basic and detall designs for the underground excavation work have been performed. The project management and tasks required for the license application have been carried out in due course. The facility is expected to be completed by the end of 1992, if the budgetary support is sufficient. (Author)

FMIT - the fusion materials irradiation test facility

International Nuclear Information System (INIS)

Liska, D.J.

1980-01-01

A joint effort by the Hanford Engineering Development Laboratory (HEDL) and Los Alamos Scientific Laboratory (LASL) has produced a preliminary design for a Fusion Materials Irradiation Test Facility (FMIT) that uses a high-power linear accelerator to fire a deuteron beam into a high-speed jet of molten lithium. The result is a continuous energy spectrum of neutrons with a 14-MeV average energy which can irradiate material samples to projected end-of-life levels in about 3 years, with a total accumulated fluence of 10 21 to 10 22 n/cm 2

Fusion materials irradiation test facility: description and status

International Nuclear Information System (INIS)

Trego, A.L.; Parker, E.F.; Hagan, J.W.

1982-01-01

The Fusion Materials Irradiation Test (FMIT) Facility will generate a high-flux, high-energy neutron source that will provide a fusion-like radiation environment for fusion reactor materials development. The neutrons will be produced in a nuclear stripping reaction by impinging a 35 MeV beam of deuterons from an Alvarez-type linear accelerator on a flowing lithium target. The target will be located in a test cell which will provide an irradiation volume of over 750l within which 10 cm 3 will have an average neutron flux of greater than 1.4 x 10 15 n/cm 2 -s and 500 cm 3 an average flux of greater than 2.2 by 10 14 n/cm 2- s with an expected availability factor greater than 65%. The projected fluence within the 10 cm 3 high flux region of FMIT will effect damage upon the materials test specimens to 30 dpa (displacements per atom) for each 90 day irradiation period. This irradiation flux volume will be at least 500 times larger than that of any other facility with comparable neutron energy and will fully meet the fusion materials damage research objective of 100 dpa within three years for the first round of tests

Shiva target irradiation facility

International Nuclear Information System (INIS)

Manes, K.R.; Ahlstrom, H.G.; Coleman, L.W.; Storm, E.K.; Glaze, J.A.; Hurley, C.A.; Rienecker, F.; O'Neal, W.C.

1977-01-01

The first laser/plasma studies performed with the Shiva laser system will be two sided irradiations extending the data obtained by other LLL lasers to higher powers. The twenty approximately 1 TW laser pulses will reach the target simultaneously from above and below in nested pentagonal clusters. The upper and lower clusters of ten beams each are radially polarized so that they strike the target in p-polarization and maximize absorption. This geometry introduces laser system isolation problems which will be briefly discussed. The layout and types of target diagnostics will be described and a brief status report on the facility given

Monte Carlo studies of the Portuguese gamma irradiation facility. The irradiator geometry and its influence on process parameters

International Nuclear Information System (INIS)

Oliveira, C.; Ferreira, L.; Salgado, J.

2001-01-01

The paper describes a Monte Carlo study of dose distributions, minimum dose and uniformity ratio for the Portuguese Gamma Irradiation Facility. These process parameters are calculated using the MCNP code for several irradiator geometries. The comparison of the simulated results with the experimental results carried out using Amber Perspex dosimeters in a routine process of the gamma facility for a given material composition and density reveals good agreement. The results already obtained allow to conclude that the dose uniformity is not very sensitive to the irradiator geometry for density value ρ = 0.1 and for a dynamic process. (orig.)

A new materials irradiation facility at the Kyoto university reactor

International Nuclear Information System (INIS)

Yoshiie, T.; Hayashi, Y.; Yanagita, S.; Xu, Q.; Satoh, Y.; Tsujimoto, H.; Kozuka, T.; Kamae, K.; Mishima, K.; Shiroya, S.; Kobayashi, K.; Utsuro, M.; Fujita, Y.

2003-01-01

A new materials irradiation facility with improved control capabilities has been installed at the Kyoto University Reactor (KUR). Several deficiencies of conventional fission neutron material irradiation systems have been corrected. The specimen temperature is controlled both by an electric heater and by the helium pressure in the irradiation tube without exposure to neutrons at temperatures different from the design test conditions. The neutron spectrum is varied by the irradiation position. Irradiation dose is changed by pulling the irradiation capsule up and down during irradiation. Several characteristics of the irradiation field were measured. The typical irradiation intensity is 9.4x10 12 n/cm 2 s (>0.1 MeV) and the irradiation temperature of specimens is controllable from 363 to 773 K with a precision of ±2 K

Seed irradiation facilities at TRIGA Mark II reactor

International Nuclear Information System (INIS)

Najzer, M.

1972-01-01

Fast neutrons and gamma-rays with their high and low LET respectively are excellent complementary tools for investigation of the effect of different types of mutations. TRIGA Irradiation Facility and Thermal Column Irradiation Facility were designed and installed for the first time in the TRIGA tank and thermal column respectively. The basic idea of design was the use of depleted uranium as gamma-ray and thermal neutron shield and simultaneously as thermal to fast neutron converter. Low LET radiation, due to direct and thermal neutron capture gamma-rays, is strongly attenuated while fast neutron flux is increased. GIF is made of a cadmium tube inserted in a graphite block. It is located in the central thermal column channel. The basic idea is to convert thermal neutrons to gamma-rays by capture in the cadmium

A New High-intensity Proton Irradiation Facility at the CERN PS East Area

CERN Document Server

Gkotse, B; Lima, P; Matli, E; Moll, M; Ravotti, F

2014-01-01

and IRRAD2), were heavily and successfully used for irradiation of particle detectors, electronic components and materials since 1992. These facilities operated with particle bursts - protons with momentum of 24GeV/c - delivered from the PS accelerator in “spills” of about 400ms (slow extraction). With the increasing demand of irradiation experiments, these facilities suffered from a number of restrictions such as the space availability, the maximum achievable particle flux and several access constraints. In the framework of the AIDA project, an upgrade of these facilities has been realized during the CERN long shutdown (LS1). While the new proton facility (IRRAD) will continue to be mainly devoted to the radiation hardness studies for the High Energy Physics (HEP) experimental community, the new mixed-field facility (CHARM) will mainly host irradiation experiments for the validation of electronic systems used in a...

Process control and dosimetry in a multipurpose irradiation facility

Science.gov (United States)

Cabalfin, E. G.; Lanuza, L. G.; Solomon, H. M.

1999-08-01

Availability of the multipurpose irradiation facility at the Philippine Nuclear Research Institute has encouraged several local industries to use gamma radiation for sterilization or decontamination of various products. Prior to routine processing, dose distribution studies are undertaken for each product and product geometry. During routine irradiation, dosimeters are placed at the minimum and maximum dose positions of a process load.

TRIGA out of core gamma irradiation facility

International Nuclear Information System (INIS)

Rant, J.; Pregl, G.

1988-01-01

A possibility to irradiate extended objects in a gamma field inside the shielding water tank and above the core of operating TRIGA Mark II Reactor has been investigated. The irradiation cask is shielded with Cd cover to filter out thermal neutrons. The dose rate of the gamma field strongly depends on the distance of the irradiation position above the core. At 25 cm above the core, the gamma dose rate is 2.2 Gy/s and epithermal neutron flux is ∼ 8.10 6 ncm -2 s -1 ∼ 3 as measured by TLD (CaF 2 : Mn) dosimeters and Au foils respectively. Tentative applications of the gamma irradiation facility are in the studies of radiation induced accelerated aging and within the Nuclear Power Plant Equipment Qualification Program (EQP). A complete characterization of the neutron spectrum and optimization of the 7 radiation field within the cask has still to be performed. (author)

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

International Nuclear Information System (INIS)

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

1994-01-01

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

Present and future of food irradiation in China

International Nuclear Information System (INIS)

Chen Hao; Cai Jiming; Pan Pingchuan; Liu Ge

2006-01-01

The treatment of foods and agricultural products by irradiation technology in China has become an increasingly accepted practice and has been recognized as a public health intervention measure for controling pathogenic microbes and pests on foods since early 1980s. This paper gives an outline on the history and the current status of food irradiation in China, including the research interest, commercial application, public acceptance, regulations and hygienic standards of irradiated foods, and the irradiation facilities for food irradiation. The newly finished or scheduled irradiation facilities in China up to 2007 are introduced. And problems with the food irradiation studies, especially in analysis of food quality during irradiation, the implementation of GMP and HACCP in the food irradiation production and harmonization of food irradiation regulations with international standards, are also discussed. (authors)

Gamma Irradiation Facility at Sandia National Laboratories, Albuquerque, New Mexico. Final environmental assessment

International Nuclear Information System (INIS)

1995-11-01

The US Department of Energy (DOE) has prepared an environmental assessment (EA) on the proposed construction and operation of a new Gamma Irradiation Facility (GIF) at Sandia National Laboratories/New Mexico (SNL/NM). This facility is needed to: enhance capabilities to assure technical excellence in nuclear weapon radiation environments testing, component development, and certification; comply with all applicable ES and H safeguards, standards, policies, and regulations; reduce personnel radiological exposure to comply with ALARA limits in accordance with DOE orders and standards; consolidate major gamma ray sources into a central, secured area; and reduce operational risks associated with operation of the GIF and LICA in their present locations. This proposed action provides for the design, construction, and operation of a new GIF located within TA V and the removal of the existing GIF and Low Intensity Cobalt Array (LICA). The proposed action includes potential demolition of the gamma shield walls and removal of equipment in the existing GIF and LICA. The shielding pool used by the existing GIF will remain as part of the ACRR facility. Transportation of the existing 60 Co sources from the existing LICA and GIF to the new facility is also included in the proposed action. Relocation of the gamma sources to the new GIF will be accomplished by similar techniques to those used to install the sources originally

AECL hot-cell facilities and post-irradiation examination services

International Nuclear Information System (INIS)

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

1998-04-01

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

AECL hot-cell facilities and post-irradiation examination services

International Nuclear Information System (INIS)

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

1995-01-01

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

Upgrade to the Birmingham Irradiation Facility

CERN Document Server

Dervan, P; Hodgson, P; Marin- Reyes; Parker, K; Wilson, J; Baca, M

2015-01-01

The Birmingham Irradiation Facility was developed in 2013 at the University of Birmingham using the Medical Physics MC40 cyclotron. It can achieve High Luminosity LHC (HL-LHC) fluences of 10^15 (1 MeV neutron equivalent (neq)) cm^-2 in 80 s with proton beam currents of 1 μA and so can evaluate effectively the performance and durability of detector technologies and new components to be used for the HL-LHC. Irradiations of silicon sensors and passive materials can be carried out in a temperature controlled cold box which moves continuously through the homogenous beamspot. This movement is provided by a pre-configured XY-axis Cartesian robot scanning system. In 2014 the cooling system and cold box were upgraded from a recirculating glycol chiller system to a liquid nitrogen evaporative system. The new cooling system achieves a stable temperature of 50 1C in 30 min and aims to maintain sub-0 1C temperatures on the sensors during irradiations. This paper reviews the design, development, commissioning and perform...

A novel facility for 3D micro-irradiation of living cells in a controlled environment by MeV ions.

Science.gov (United States)

Mäckel, V; Meissl, W; Ikeda, T; Clever, M; Meissl, E; Kobayashi, T; Kojima, T M; Imamoto, N; Ogiwara, K; Yamazaki, Y

2014-01-01

We present a novel facility for micro-irradiation of living targets with ions from a 1.7 MV tandem accelerator. We show results using 1 MeV protons and 2 MeV He(2+). In contrast to common micro-irradiation facilities, which use electromagnetic or electrostatic focusing and specially designed vacuum windows, we employ a tapered glass capillary with a thin end window, made from polystyrene with a thickness of 1-2 μm, for ion focusing and extraction. The capillary is connected to a beamline tilted vertically by 45°, which allows for easy immersion of the extracted ions into liquid environment within a standard cell culture dish. An inverted microscope is used for simultaneously observing the samples as well as the capillary tip, while a stage-top incubator provides an appropriate environment for the samples. Furthermore, our setup allows to target volumes in cells within a μm(3) resolution, while monitoring the target in real time during and after irradiation.

Planning a 60Co irradiation facility for fruit preservation

International Nuclear Information System (INIS)

Yuan, H.C.

1978-01-01

A conceptual design for a conveyor system is proposed for use in fruit irradiation. The seasonal nature of the fruit harvest requires that the 60 Co source inventory should be sufficient to meet the demand at peak season, but this would be excessive at the beginning and towards the end of the harvest. Because of the short crop period the possibility of other irradiation services should be exploited to ensure full utilization of the facility. For successful extension of fruit shelf-life rigid practices in pre-irradiation treatment are essential and careful packaging is indispensable to the operation of the irradiator. Based on the time required for construction and equipment supply, a period of 18 months should be assumed for completion of the project. (author)

Calculation of displacement and helium production at the Clinton P. Anderson Los Alamos Meson Physics Facility (LAMPF) irradiation facility

International Nuclear Information System (INIS)

Wechsler, M.S.; Davidson, D.R.; Greenwood, L.R.; Sommer, W.F.

1984-01-01

CT: Differential and total displacement and helium production rates are calculated for copper irradiated by spallation neutrons and 760 MeV protons at the Clinton P. Anderson Los Alamos Meson Physics Facility (LAMPF). The calculations are performed using the SPECTER and VNMTC computer codes, the latter being specially designed for spallation radiation damage calculations. For comparison, similar SPECTER calculations are also described for irradiation of copper in EBR-II and RTNS-II. The results indicate substantial contributions to the displacement and helium production rates due to neutrons in the high-energy tail (above 20 MeV) of the LAMPF spallation neutron spectrum. Still higher production rates are calculated for irradiations in the direct proton beam. These results will provide useful background information for research to be conducted at a new irradiation facility at LAMPF

Proceedings of 1991-workshops of the working group on 'Development and application of facilities for low temperature irradiation as well as controlled irradiation'

International Nuclear Information System (INIS)

Kuramoto, Eiichi; Okada, Moritami

1992-09-01

This is the proceedings of 1991-workshops of the working group on 'Development and Application of Facilities for Low Temperature Irradiation as well as Controlled Irradiation' held at the Research Reactor Institute of Kyoto University on July 25, 1991 and on February 28, 1992. In the present proceedings, it is emphasized that the study of radiation damages in various materials must be performed under carefully controlled irradiation conditions (irradiation temperature, neutron spectrum and so forth) during reactor irradiations. Especially, it is pointed out that a middle scale reactor such as KUR is suitable for the precise control of neutron spectra. Several remarkable results, which are made through experiments using the Low Temperature Irradiation Facility in KUR (KUR-LTL), are reported. Also, possible advanced research programs are discussed including the worldwide topics on the radiation damages in metals, semi-conductors and also insulators. Further, the present status of KUR-LTL is reported and the advanced plan of the facility is proposed. (author)

In-cell facility for performing mechanical-property tests on irradiated cladding

International Nuclear Information System (INIS)

Yaggee, F.L.; Haglund, R.C.; Mattas, R.F.

1978-11-01

A new facility was developed for testing cladding sections of LWR fuel rods. This facility and the accompanying test procedures have improved the level of in-cell mechanical-testing capabilities, making them comparable to existing capabilities for unirradiated cladding. The new facility is currently being used to study the susceptibility of irradiated Zircaloy cladding from LWR fuel rods to iodine stress-corrosion cracking. Preliminary testing results indicate a systematic effect of temperature, stress and irradiation on the susceptibility of annealed and stress-relieved Zircaloy-2. Experimental data obtained to date are being used to develop a stress-corrosion cracking model for LWR fuel rod failure. SEM examination of the undisturbed fracture surface of specimens that failed by pinhole leakage provides useful information on crack propagation and morphology

Breathing new life into your production irradiator the case for reinvesting in your facility

International Nuclear Information System (INIS)

Aube, Robert; Wynnyk, Mike

2002-01-01

This paper focuses on one of the important technology issues facing the gamma processing industry today: that of strategically planning for extending the useful life of a production irradiator. Production irradiator owners are typically faced with the difficult question of whether or not to significantly reinvest in their facilities after 15-20 years of service. At this point in time the irradiator has likely provided many years of safe, reliable service and has paid for itself many times over. As the equipment ages, it may become less reliable, due to wear and maintenance practices, and more costly to operate. The cost of refurbishing the equipment may be significant and the downtime required to complete the refurbishment is also likely to be a challenge. This makes it essential to present a clear and rational justification for reinvesting in the facility. There has been a growing trend in recent years for irradiator owners to refurbish or upgrade their facilities. This trend is driven by the need to keep the facilities operating efficiently and safely as well as by the desire to take advantage of advancements that have occurred in the technology over the years. These advancements can enhance equipment efficiency, improve operational effectiveness and maintain or exceed quality assurance requirements. This paper illustrates the value of reinvesting in irradiator facilities, and highlights the significant benefits derived

Capsule safety analysis of PRTF irradiation facility

International Nuclear Information System (INIS)

Suwarto

2013-01-01

Power Ramp Test Facility (PRTF) is an irradiation facility used for fuel testing of power reactor. PRTF has a capsule which is a test fuel rod container. During operation, pressurized water of 160 bars flows through in the capsule. Due to the high pressure it should be analyzed the impact of the capsule on reactor core safety. This analysis has purpose to calculate the ability of capsule pressure capacity. The analysis was carried out by calculating pressure capacity. From the calculating results it can be concluded that the capsule with pressure capacity of 438 bars will be safe to prevent the operation pressure of PRTF. (author)

Design, fabrication and installation of irradiation facilities

Energy Technology Data Exchange (ETDEWEB)

Sim, Bong Shick; Kim, Y. S.; Lee, C. Y. and others

1999-03-01

The principal contents of this project are to design, fabricate and install the steady-state fuel test loop in HANARO for nuclear technology development. Procurement and fabrication of main equipment, licensing and technical review for fuel test loop have been performed during 2 years(1997, 1998) for this project. Following contents are described in the report. - Procurement and fabrication of the equipment, piping for OPS - IPS manufacture - License - Technical review and evaluation of the FTL facility. As besides, as these irradiation facilities will be installed in HANARO, review of safety concern, discussion with KINS for licensing and review ofHANARO interface have been performed respectively. (author)

Defocusing beam line design for an irradiation facility at the TAEA SANAEM Proton Accelerator Facility

CERN Document Server

Gencer, A.; Efthymiopoulos, I.; Yiğitoğlu, M.

2016-01-01

Electronic components must be tested to ensure reliable performance in high radiation environments such as Hi-Limu LHC and space. We propose a defocusing beam line to perform proton irradiation tests in Turkey. The Turkish Atomic Energy Authority SANAEM Proton Accelerator Facility was inaugurated in May 2012 for radioisotope production. The facility has also an R&D room for research purposes. The accelerator produces protons with 30 MeV kinetic energy and the beam current is variable between View the MathML source10μA and View the MathML source1.2mA. The beam kinetic energy is suitable for irradiation tests, however the beam current is high and therefore the flux must be lowered. We plan to build a defocusing beam line (DBL) in order to enlarge the beam size, reduce the flux to match the required specifications for the irradiation tests. Current design includes the beam transport and the final focusing magnets to blow up the beam. Scattering foils and a collimator is placed for the reduction of the beam ...

IFMIF [International Fusion Materials Irradiation Facility], an accelerator-based neutron source for fusion components irradiation testing: Materials testing capabilities

International Nuclear Information System (INIS)

Mann, F.M.

1988-08-01

The International Fusion Materials Irradiation Facility (IFMIF) is proposed as an advanced accelerator-based neutron source for high-flux irradiation testing of large-sized fusion reactor components. The facility would require only small extensions to existing accelerator and target technology originally developed for the Fusion Materials Irradiation Test (FMIT) facility. At the extended facility, neutrons would be produced by a 0.1-A beam of 35-MeV deuterons incident upon a liquid lithium target. The volume available for high-flux (>10/sup 15/ n/cm/sup 2/-s) testing in IFMITF would be over a liter, a factor of about three larger than in the FMIT facility. This is because the effective beam current of 35-MeV deuterons on target can be increased by a factor of ten to 1A or more. Such an increase can be accomplished by funneling beams of deuterium ions from the radio-frequency quadruple into a linear accelerator and by taking advantage of recent developments in accelerator technology. Multiple beams and large total current allow great variety in available testing. For example, multiple simultaneous experiments, and great flexibility in tailoring spatial distributions of flux and spectra can be achieved. 5 refs., 2 figs., 1 tab

The proposed irradiation facility and applications

International Nuclear Information System (INIS)

Singson, C.C.; Navarro, Q.O.

As early as 1972, the Philippine Atomic Energy Commission proposed the setting up of a radiation facility for the sterilization of medical products. A result of a market survey with the assistance of an IAEA expert was conducted to determine the market potential for such venture. With the Food Terminal, Inc. (FTI) a government agro-industrial fair which explored the economic benefits of project, encouraging results have been obtained with finances from FAO and IAEA. The proposed pilot plant will serve as a multi purpose facility for the sterilization of medical and laboratory products, irradiation of food and agricultural produce and manufacture of wood plastic compositions for the textile and furniture industries. With the benefits derived from the said project, it is hoped that its early installation be pushed through. (author)

Improvement of the High Fluence Irradiation Facility at the University of Tokyo

Energy Technology Data Exchange (ETDEWEB)

Murakami, Kenta, E-mail: murakami@tokai.t.u-tokyo.ac.jp [Nuclear Professional School, School of Engineering, The University of Tokyo, 2-22 Shirakata-Shirane, Tokai-mura, Ibaraki 319-1188 (Japan); Iwai, Takeo, E-mail: iwai@med.id.yamagata-u.ac.jp [Faculty of Medicine, Yamagata University, 2-2-2 Iida-Nishi, Yamagata, Yamagata-shi 990-9585 (Japan); Abe, Hiroaki, E-mail: abe.hiroaki@n.t.u-tokyo.ac.jp [Nuclear Professional School, School of Engineering, The University of Tokyo, 2-22 Shirakata-Shirane, Tokai-mura, Ibaraki 319-1188 (Japan); Sekimura, Naoto, E-mail: sekimura@n.t.u-tokyo.ac.jp [Department of Nuclear Engineering and Management, School of Engineering, The University of Tokyo, 7-3-1, Tokyo, Hongo, Bunkyo, 113-8656 (Japan)

2016-08-15

This paper reports the modification of the High Fluence Irradiation Facility at the University of Tokyo (HIT). The HIT facility was severely damaged during the 2011 earthquake, which occurred off the Pacific coast of Tohoku. A damaged 1.0 MV tandem Cockcroft-Walton accelerator was replaced with a 1.7 MV accelerator, which was formerly used in another campus of the university. A decision was made to maintain dual-beam irradiation capability by repairing the 3.75 MV single-ended Van de Graaff accelerator and reconstructing the related beamlines. A new beamline was connected with a 200 kV transmission electron microscope (TEM) to perform in-situ TEM observation under ion irradiation.

A discussion on establishment of GIP management system for food irradiation facilities

International Nuclear Information System (INIS)

Lu Jiang; Shi Hua; Li Ruisong; Li Shurong; Zhou Hongjie; Ha Yiming

2005-01-01

This article analyses the hazard factors and selects Critical Control Point (CCP) for food irradiation process (including staff, facilities and processing) using HACCP version. The principles and method of GIP system for food irradiation plant are also discussed. (authors)

Industrial gamma irradiation facility with a wet storage source in Syrian Arab Republic

International Nuclear Information System (INIS)

Othman, I.; Moussa, A.; Stepanov, D.G.; Ermakov, V.

1998-01-01

A gamma radiation facility was built in Damascus, Syria. The plant (ROBO) is a Co-60 wet storage, batch/continuous facility with nominal capacity of 1.85x10 16 Bq. The initial activity is 3.7x10 15 Bq. The ratio of maximum absorbed dose to the minimum one within irradiated materials is around 1.3+/-0.03. The irradiator consists of two sections to select required sources for irradiation. Two pools were constructed. The main pool will serve as biological shield for the main sources frame. The second pool will host a fixed circular frame to be used as calibration source or to irradiate small samples to low doses. The conveyor consists of a chain facility moving along trucks. A repair section is provided on the conveyor route in the load-unload area for carrying out inspection, repair, etc. The trucks are holed with a rectangular frames. Loading, unloading and rearrangement of the products is carried out automatically. This mechanism is carried out by seven pneumatic cylinders, lifting devices and roller conveyors. Many safety features were included: push-back platform, followed by pit used as a physical barrier. Interlocks are connected to the platform, pit cover and to ionization chambers. In case of power failure or any overriding of interlocks, the irradiator comes to emergency dropping. Ventilation system, fire system, emergency power and closed water purification system are indicated on control panel. The facility will be utilized for medical products sterilization, research and calibration

Food irradiation 2009

International Nuclear Information System (INIS)

Narvaiz, Patricia

2009-01-01

Food irradiation principles; its main applications, advantages and limitations; wholesomeness, present activities at Ezeiza Atomic Centre; research coordinated by the International Atomic Energy Agency; capacity building; and some aspects on national and international regulations, standards and commercialization are briefly described. At present 56 countries authorize the consumption of varied irradiated foods; trade is performed in 32 countries, with about 200 irradiation facilities. Argentina pioneered nuclear energy knowledge and applications in Latin America, food irradiation included. A steady growth of food industrial volumes treated in two gamma facilities can be observed. Food industry and producers show interest towards new facilities construction. However, a 15 years standstill in incorporating new approvals in the Argentine Alimentary Code, in spite of consecutive request performed either by CNEA or some food industries restricts, a wider industrial implementation, which constitute a drawback to future regional commercialization in areas such as MERCOSUR, where Brazil since 2000 freely authorize food irradiation. Besides, important chances in international trade with developed countries will be missed, like the high fresh fruits and vegetables requirements United States has in counter-season, leading to convenient sale prices. The Argentine food irradiation facilities have been designed and built in the country. Argentina produces Cobalt-60. These capacities, unusual in the world and particularly in Latin America, should be protected and enhanced. Being the irradiation facilities scarce and concentrated nearby Buenos Aires city, the possibilities of commercial application and even research and development are strongly limited for most of the country regions. (author) [es

NRX and NRU reactor research facilities and irradiation and examination charges

International Nuclear Information System (INIS)

1960-08-01

This report details the irradiation and examination charges on the NRX and NRU reactors at the Chalk River Nuclear Labs. It describes the NRX and NRU research facilities available to external users. It describes the various experimental holes and loops available for research. It also outlines the method used to calculate the facilities charges and the procedure for applying to use the facilities as well as the billing procedures.

Practice for dosimetry in gamma irradiation facilities for food processing. 2. ed.

International Nuclear Information System (INIS)

2004-01-01

This practice outlines the installation qualification program for an irradiator and the dosimetric procedures to be followed during operational qualification, performance qualification, and routine processing in facilities that process food with ionizing radiation from radionuclide gamma sources to ensure that product has been treated within a predetermined range of absorbed dose. Other procedures related to operational qualification, performance qualification, and routine processing that may influence absorbed dose in the product are also discussed. Information about effective or regulatory dose limits for food products is not within the scope of this practice (see ASTM Guides F 1355, F 1356, F 1736, and F 1885). This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use

Towards a Unified Environmental Monitoring, Control and Data Management System for Irradiation Facilities: the CERN IRRAD Use Case

CERN Document Server

Gkotse, Blerina; Jouvelot, Pierre; Matli, Emanuele; Pezzullo, Giuseppe; Ravotti, Federico

2017-01-01

The qualification of materials, electronic components and equipment for the CERN High Energy Physics experiments and beyond requires testing against possible radiation effects. These quite complex tests are performed by specialized teams working in irradiation facilities such as IRRAD, the Proton Irradiation Facility at CERN. Building upon the details of the overall irradiation control, monitoring, and logistical systems of IRRAD as a use case, we introduce the motivations for and general architecture of its new data management framework, currently under development at CERN. This infrastructure is intended to allow for the seamless and comprehensive handling of IRRAD irradiation experiments and to help manage all aspects of the facility. Its architecture, currently focused on the specific requirements of the IRRAD facility, is intended to be upgraded to a general framework that could be used in other irradiation facilities within the radiation effects community, as well as for other applications.

Description of the PIE facility for research reactors irradiated fuels in CNEA

International Nuclear Information System (INIS)

Bisca, A.; Coronel, R.; Homberger, V.; Quinteros, A.; Ratner, M.

2002-01-01

The PIE Facility (LAPEP), located at the Ezeiza Atomic Center (CAE), was designed to carry out destructive and non-destructive post-irradiation examinations (PIE) on research and power reactor spent fuels, reactor internals and other irradiated materials, and to perform studies related with: Station lifetime extension; Fuel performance; Development of new fuels; and Failures and determination of their causes. LAPEP is a relevant facility where research and development can be carried out. It is worth mentioning that in this facility the PIE corresponding to the Surveillance Program for the Atucha I Nuclear Power Plant (CNA-1) were successfully performed. Materials testing during the CNA-1 repair and the study of failures in fuel element plugs of the Embalse Nuclear Power Plant (CNE) were also performed. (author)

Dosimetry in Thermal Neutron Irradiation Facility at BMRR

Directory of Open Access Journals (Sweden)

Hu J.-P.

2016-01-01

Full Text Available Radiation dosimetry for Neutron Capture Therapy (NCT has been performed since 1959 at Thermal Neutron Irradiation Facility (TNIF of the three-megawatt light-water cooled Brookhaven Medical Research Reactor (BMRR. In the early 1990s when more effective drug carriers were developed for NCT, in which the eye melanoma and brain tumors in rats were irradiated in situ, extensive clinical trials of small animals began using a focused thermal neutron beam. To improve the dosimetry at irradiation facility, a series of innovative designs and major modifications made to enhance the beam intensity and to ease the experimental sampling at BMRR were performed; including (1 in-core fuel addition to increase source strength and balance flux of neutrons towards two ports, (2 out of core moderator remodeling, done by replacing thicker D2O tanks at graphite-shutter interfacial areas, to expedite neutron thermalization, (3 beam shutter upgrade to reduce strayed neutrons and gamma dose, (4 beam collimator redesign to optimize the beam flux versus dose for animal treatment, (5 beam port shielding installation around the shutter opening area (lithium-6 enriched polyester-resin in boxes, attached with polyethylene plates to reduce prompt gamma and fast neutron doses, (6 sample holder repositioning to optimize angle versus distance for a single organ or whole body irradiation, and (7 holder wall buildup with neutron reflector materials to increase dose and dose rate from scattered thermal neutrons. During the facility upgrade, reactor dosimetry was conducted using thermoluminescent dosimeters TLD for gamma dose estimate, using ion chambers to confirm fast neutron and gamma dose rate, and by the activation of gold-foils with and without cadmium-covers, for fast and thermal neutron flux determination. Based on the combined effect from the size and depth of tumor cells and the location and geometry of dosimeters, the measured flux from cadmium-difference method was 4–7

Dosimetry in Thermal Neutron Irradiation Facility at BMRR

Energy Technology Data Exchange (ETDEWEB)

Hu, J. P. [Brookhaven National Lab. (BNL), Upton, NY (United States); Holden, N. E. [Brookhaven National Lab. (BNL), Upton, NY (United States); Reciniello, R. N.

2014-05-23

Radiation dosimetry for Neutron Capture Therapy (NCT) has been performed since 1959 at Thermal Neutron Irradiation Facility (TNIF) of the three-megawatt light-water cooled Brookhaven Medical Research Reactor (BMRR). In the early 1990s when more effective drug carriers were developed for NCT, in which the eye melanoma and brain tumors in rats were irradiated in situ, extensive clinical trials of small animals began using a focused thermal neutron beam. To improve the dosimetry at irradiation facility, a series of innovative designs and major modifications made to enhance the beam intensity and to ease the experimental sampling at BMRR were performed; including (1) in-core fuel addition to increase source strength and balance flux of neutrons towards two ports, (2) out of core moderator remodeling, done by replacing thicker D₂O tanks at graphite-shutter interfacial areas, to expedite neutron thermalization, (3) beam shutter upgrade to reduce strayed neutrons and gamma dose, (4) beam collimator redesign to optimize the beam flux versus dose for animal treatment, (5) beam port shielding installation around the shutter opening area (lithium-6 enriched polyester-resin in boxes, attached with polyethylene plates) to reduce prompt gamma and fast neutron doses, (6) sample holder repositioning to optimize angle versus distance for a single organ or whole body irradiation, and (7) holder wall buildup with neutron reflector materials to increase dose and dose rate from scattered thermal neutrons. During the facility upgrade, reactor dosimetry was conducted using thermoluminescent dosimeters TLD for gamma dose estimate, using ion chambers to confirm fast neutron and gamma dose rate, and by the activation of gold-foils with and without cadmium-covers, for fast and thermal neutron flux determination. Based on the combined effect from the size and depth of tumor cells and the location and geometry of dosimeters, the measured flux from cadmium-difference method was 4 - 7

Final safety analysis report for the irradiated fuels storage facility

International Nuclear Information System (INIS)

Bingham, G.E.; Evans, T.K.

1976-01-01

A fuel storage facility has been constructed at the Idaho Chemical Processing Plant to provide safe storage for spent fuel from two commercial HTGR's, Fort St. Vrain and Peach Bottom, and from the Rover nuclear rocket program. The new facility was built as an addition to the existing fuel storage basin building to make maximum use of existing facilities and equipment. The completed facility provides dry storage for one core of Peach Bottom fuel (804 elements), 1 1 / 2 cores of Fort St. Vrain fuel (2200 elements), and the irradiated fuel from the 20 reactors in the Rover program. The facility is designed to permit future expansion at a minimum cost should additional storage space for graphite-type fuels be required. A thorough study of the potential hazards associated with the Irradiated Fuels Storage Facility has been completed, indicating that the facility is capable of withstanding all credible combinations of internal accidents and pertinent natural forces, including design basis natural phenomena of a 10,000 year flood, a 175-mph tornado, or an earthquake having a bedrock acceleration of 0.33 g and an amplification factor of 1.3, without a loss of integrity or a significant release of radioactive materials. The design basis accident (DBA) postulated for the facility is a complete loss of cooling air, even though the occurrence of this situation is extremely remote, considering the availability of backup and spare fans and emergency power. The occurrence of the DBA presents neither a radiation nor an activity release hazard. A loss of coolant has no effect upon the fuel or the facility other than resulting in a gradual and constant temperature increase of the stored fuel. The temperature increase is gradual enough that ample time (28 hours minimum) is available for corrective action before an arbitrarily imposed maximum fuel centerline temperature of 1100 0 F is reached

An industrial 60Co gamma irradiation facility in China

International Nuclear Information System (INIS)

Jin Yongling; Zhou Ruiying; Wang Binglin

1990-01-01

The radiation processing has developed very fast in China since 1980. There are more than 100 of 60 Co radiation facilities having been set up. Majority of them was with relatively small capacity and was used mainly for the laboratory study. An industrial radiation facility has been established and put into operation in Beijing Radiation Application Center (BRAC) recently. The project was based on the research works of irradiation technology during the period of 1980-1985. The main pre-research work was radiation sterilization of medical products and food irradiation. This work has obtained an award from State Commission of Science and Technology. The Commission has arranged the construction of an industrial sterilization plant for medical products as a major import project. The project has also been supported by IAEA as project CPR/8/002. The project includes a plant of production of 100,000,000 needles per year, a plant of production of 50,000,000 syringes per year and an automatic irradiation plant. All three parts have been set up now. The maximum capacity of 60 Co sources is 3.7 x 10 16 Bq, the first-time-loaded source is 12.21 x 10 15 Bq. (author)

Irradiation facilities for materials research: IFMIF and small scale installations

International Nuclear Information System (INIS)

Perlado, J. M.; Victoria, M.

2007-01-01

The research of advance materials in nuclear fields such as new fission reactors (Generation-IV), Accelerator Driven Systems for Transmutation of Radioactive Wastes and Nuclear Fusion, is becoming very much common in the types of low activation and radiation resistant Materials. Ferritic-Martensitic Steels (based in 9-12 Cr) with or without Oxide Dispersion Techniques (Ytria Nanoparticles), Composites materials are becoming the new generation to answer requirements of high temperature, high radiation resistance of structural materials. Special dedication is appearing in general research programmes to this area of Materials. The understanding of their final performance needs a wider knowledge of the mechanisms of radiation damage in these materials from the atomistic scale to the macroscopic responses. New extensive campaigns are being funded to irradiate from simple elements to model alloys and finally the complex materials themselves. That sequence and its state of art will be presented One clear technique for that understanding is the Multi scale Modelling which includes simulation techniques from quantum mechanics, molecular dynamics, defects diffusion, mesoscopic modelling and finally the macroscopic constitutive relations for macroscopic analysis. However, in each one of these steps is necessary a systematic and well established program of experiments that combines the irradiation and the very detailed analysis with techniques such as Transmission Electron Microscope, Positron Annihilation, SIMS, Atom Probe, Nanoindebntation. A key aspect that wants to be presented in this work is the state of art and discussion of Irradiation Facilities for Materials studies. Those facilities goes from ion implantation sources, small accelerator, Experimental Reactors such High Flux Reactor, sophisticated Triple Beams Sources as JANNUS in France to generate at the same time displacements-hydrogen-helium, and projected very large neutron installation such as IFMIF. The role to

Neutron-irradiation facilities at the Intense Pulsed Neutron Source-I for fusion magnet materials studies

International Nuclear Information System (INIS)

Brown, B.S.; Blewitt, T.H.

1982-01-01

The decommissioning of reactor-based neutron sources in the USA has led to the development of a new generation of neutron sources that employ high-energy accelerators. Among the accelerator-based neutron sources presently in operation, the highest-flux source is the Intense Pulsed Neutron Source (IPNS), a user facility at Argonne National Laboratory. Neutrons in this source are produced by the interaction of 400 to 500 MeV protons with either of two 238 U target systems. In the Radiation Effects Facility (REF), the 238 U target is surrounded by Pb for neutron generatjion and reflection. The REF has three separate irradiation thimbles. Two thimbles provide irradiation temperatures between that of liquid He and several hundred degrees centigrade. The third thimble operates at ambient temperature. The large irradiation volume, the neutron spectrum and flux, the ability to transfer samples without warm up, and the dedication of the facilities during the irradiation make this ideally suited for radiation damage studies on components for superconducting fusion magnets. Possible experiments for fusion magnet materials are discussed on cyclic irradiation and annealing of stabilizers in a high magnetic field, mechanical tests on organic insulation irradiated at 4 K, and superconductors measured in high fields after irradiation

A spallation-based irradiation test facility for fusion and future fission materials

CERN Document Server

Samec, K; Kadi, Y; Luis, R; Romanets, Y; Behzad, M; Aleksan, R; Bousson, S

2014-01-01

The EU’s FP7 TIARA program for developing accelerator-based facilities has recently demonstrated the unique capabilities of a compact and powerful spallation source for irradiating advanced nuclear materials. The spectrum and intensity of the neutron flux produced in the proposed facility fulfils the requirements of the DEMO fusion reactor for ITER, ADS reactors and also Gen III / IV reactors. Test conditions can be modulated, covering temperature from 400 to 550°C, liquid metal corrosion, cyclical or static stress up to 500 MPa and neutron/proton irradiation damage of up to 25 DPA per annum. The entire “TMIF” facility fits inside a cube 2 metres on a side, and is dimensioned for an accelerator beam power of 100 kW, thus reducing costs and offering great versatility and flexibility.

Nonreactor nuclear facilities: standards and criteria guide

International Nuclear Information System (INIS)

Brynda, W.J.; Junker, L.; Karol, R.C.; Lobner, P.R.; Goldman, L.A.

1981-09-01

This guide is a source document that identifies standards, codes, and guides that address the nuclear safety considerations pertinent to nuclear facilities as defined in DOE Order 5480.1, Chapter V, Safety of Nuclear Facilities. The guidance and criteria provided are directed toward areas of safety usually addressed in a Safety Analysis Report. The areas of safety include, but are not limited to, siting, principal design criteria and safety system design guidelines, radiation protection, accident analysis, and quality assurance. The guide is divided into two sections: general guidelines and appendices. Those guidelines that are broadly applicable to most nuclear facilities are presented in the general guidelines. These general guidelines may have limited applicability to subsurface facilities such as waste repositories. Guidelines specific to the various types or categories of nuclear facilities are presented in the appendices. These facility-specific appendices provide guidelines and identify standards and criteria that should be considered in addition to, or in lieu of, the general guidelines

DECOMMISSIONING THE BROOKHAVEN NATIONAL LABORATORY BUILDING 830 GAMMA IRRADIATION FACILITY.

Energy Technology Data Exchange (ETDEWEB)

BOWERMAN, B.S.; SULLIVAN, P.T.

2001-08-13

The Building 830 Gamma Irradiation Facility (GIF) at Brookhaven National Laboratory (BNL) was decommissioned because its design was not in compliance with current hazardous tank standards and its cobalt-60 sources were approaching the end of their useful life. The facility contained 354 stainless steel encapsulated cobalt-60 sources in a pool, which provided shielding. Total cobalt-60 inventory amounted to 24,000 Curies when the sources were shipped for disposal. The decommissioning project included packaging, transport, and disposal of the sources and dismantling and disposing of all other equipment associated with the facility. Worker exposure was a major concern in planning for the packaging and disposal of the sources. These activities were planned carefully according to ALARA (As Low As Reasonably Achievable) principles. As a result, the actual occupational exposures experienced during the work were within the planned levels. Disposal of the pool water required addressing environmental concerns, since the planned method was to discharge the slightly contaminated water to the BNL sewage treatment plant. After the BNL evaluation procedure for discharge to the sewage treatment plant was revised and reviewed by regulators and BNL's Community Advisory Council, the pool water was discharged to the Building 830 sanitary system. Because the sources were sealed and the pool water contamination levels were low, most of the remaining equipment was not contaminated; therefore disposal was straightforward, as scrap metal and construction debris.

A 14 MeV neutron irradiation facility with an automated fast cyclic pneumatic

International Nuclear Information System (INIS)

Montgomery, M.T.; Yoho, M.D.; Biegalski, S.R.; Landsberger, S.; Welch, L.

2016-01-01

This work details the design criteria, construction, controls, and optimization of the 14 MeV neutron irradiation facility at the University of Texas, built with the motivation of performing neutron activation analysis on samples with short half-lives. The facility couples a D-T neutron generator with a pneumatic transfer system capable of transit of approximately one second between source and detector, while the cyclic automated nature allows for many irradiation/count trials with any number of samples, translating to significantly improved counting statistics. (author)

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

Energy Technology Data Exchange (ETDEWEB)

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

1995-10-01

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

The prospect of food irradiation and the contribution of radiation chemistry to enact the hygienic safety standard of irradiated foods

International Nuclear Information System (INIS)

Wu Jilan; Yuan Rongyao

1986-01-01

Now, it is said that we are at the dawn of food irradiation application both nationally and internationally. However, referring to the acceptability of customers the labeling of irradiated foods has been a nightmare to the food processors. On the other hand the recommended international standard has the shortcomings of thinking in absolute terms. In this paper a proposal which puts special emphasis on enacting hygienic safety standard of individual irradiated food is recommended. The hygienic safety standard of the irradiated food may be classified in three classes: 1) its hygienic safety standard is similar to that of common food; 2) the maximum permissible quantities of harmful compounds induced by radiation must be controlled; and 3) the quantity of unique radiolysis products may by dutermined. Radiation chemistry plays an important role in enacting the hygienic safety standard of irradiated foods. For international cooperation in this field some suggestions are made

Dose mapping of the multi-purpose gamma irradiation facility

Energy Technology Data Exchange (ETDEWEB)

Cabalfin, E G; Lanuza, L G; Villamater, D T [Irradiation Services, Nuclear Services and Training Division, Philippine Nuclear Research Institute, Quezon City (Philippines)

1989-12-01

In radiation processing, reliable dosimetry constitutes a very important part of process control and quality assurance. Radiation dosimetry is the only acceptable method to guarantee that the irradiated product has undergone the correct radiation treatment. In preparation therefore, for the routine operation of the newly installed multi-purpose gamma irradiation facility at the Philippine Nuclear Research Institute (PNRI), dose mapping distribution studies were undertaken. Results of dose distribution in air as well as in dummy product are presented. The effects of product bulk density, product geometry and product to source distance on minimum absorbed dose and uniformity ratio have been determined. (Author).

Dose mapping of the multi-purpose gamma irradiation facility

International Nuclear Information System (INIS)

Cabalfin, E.G.; Lanuza, L.G.; Villamater, D.T.

1989-01-01

In radiation processing, reliable dosimetry constitutes a very important part of process control and quality assurance. Radiation dosimetry is the only acceptable method to guarantee that the irradiated product has undergone the correct radiation treatment. In preparation therefore, for the routine operation of the newly installed multi-purpose gamma irradiation facility at the Philippine Nuclear Research Institute (PNRI), dose mapping distribution studies were undertaken. Results of dose distribution in air as well as in dummy product are presented. The effects of product bulk density, product geometry and product to source distance on minimum absorbed dose and uniformity ratio have been determined. (Author)

An automatic device for sample insertion and extraction to/from reactor irradiation facilities

International Nuclear Information System (INIS)

Alloni, L.; Venturelli, A.; Meloni, S.

1990-01-01

At the previous European Triga Users Conference in Vienna,a paper was given describing a new handling tool for irradiated samples at the L.E.N.A plant. This tool was the first part of an automatic device for the management of samples to be irradiated in the TRIGA MARK ii reactor and successively extracted and stored. So far sample insertion and extraction to/from irradiation facilities available on reactor top (central thimble,rotatory specimen rack and channel f),has been carried out manually by reactor and health-physics operators using the ''traditional'' fishing pole provided by General Atomic, thus exposing reactor personnel to ''unjustified'' radiation doses. The present paper describes the design and the operation of a new device, a ''robot''type machine,which, remotely operated, takes care of sample insertion into the different irradiation facilities,sample extraction after irradiation and connection to the storage pits already described. The extraction of irradiated sample does not require the presence of reactor personnel on the reactor top and,therefore,radiation doses are strongly reduced. All work from design to construction has been carried out by the personnel of the electronic group of the L.E.N.A plant. (orig.)

A re-evaluation of physical protection standards for irradiated HEU fuel

International Nuclear Information System (INIS)

Lyman, Edwin; Kuperman, Alan

2002-01-01

In the post-September 11 era, it is essential to reconsider all the assumptions upon which the physical protection systems of the past were based and determine whether these assumptions are still appropriate in light of the current terrorist threat. For instance, the U.S. Nuclear Regulatory Commission definition of a 'formula quantity' of special nuclear material is derived from the belief that a terrorist plot to carry out multiple coordinated attacks on different facilities with the goal of acquiring enough SNM for a nuclear weapon is incredible. This assumption has clearly been proven wrong by the September 11 attacks. Another standard that needs to be revisited is the 'self-protection' threshold that determines whether or not an item containing SNM is considered to be 'irradiated' for physical protection purposes. The current value of this threshold, 1 Sv/hr unshielded at 1 meter, is of questionable value as a deterrent to determined terrorists who would be willing to sustain long-term injury as long as they could accomplish their near-term goals. A more credible threshold would be set at a level that would have a high likelihood of disabling the perpetrators before they could complete their mission. Most irradiated nonpower reactor fuels would be unable to meet such a standard. This raises serious questions about the adequacy of the level of physical protection applied today to the large inventories of irradiated HEU fuels now scattered in storage sites around the world. The absence of a coherent global policy for dealing with these materials has created a situation rife with vulnerabilities that terrorists could exploit. The international community, now seized with concern about unused stockpiles of unirradiated HEU fuels around the world, also needs to appreciate the dangers posed by lightly irradiated spent fuels as well. A U.S. proposal to import Russian HEU for supplying U.S. nonpower reactors will only prolong this situation This paper will review policy

Design Standards for School Art Facilities

Science.gov (United States)

National Art Education Association, 2015

2015-01-01

"Design Standards for School Art Facilities" is an invaluable resource for any school or school district looking to build new facilities for the visual arts or renovate existing ones. Discover detailed information about spaces for the breadth of media used in the visual arts. Photographs illustrate all types of features including…

An irradiation facility with a horizontal beam for radiobiological studies

International Nuclear Information System (INIS)

Czub, J.; Adamus, T.; Banas, D.

2006-01-01

A facility with a horizontal beam for radiobiological experiments with heavy ions has been designed and constructed at the Heavy Ion Laboratory in Warsaw University. The facility is optimal to investigate the radiobiological effects of charged heavy particles on a cellular or molecular level as the plateau of the Bragg curve as well as in the Bragg peak. The passive beam spread out by a thin scattering foil provides a homogeneous irradiation field over an area of at least 1 x 1 cm 2 . For in vitro irradiation of biological samples the passive beam spreading combined with the x - y mechanical scanning of the irradiated sample was found to be an optimum solution. Using x - y step motor, the homogenous beam of ions with the energy loss range in the cells varied from 1 MeV/μm to 200 keV/μm is able to cover a 6 cm in diameter Petri dish that holds the biological samples. Moreover on-line fluence monitoring based on single-particle counting is performed to determine the dose absorbed by cells. Data acquisition system for dosimetry and ion monitoring based on a personal computer is described. (author)

MANUAL OF STANDARDS FOR REHABILITATION CENTERS AND FACILITIES.

Science.gov (United States)

CANIFF, CHARLES E.; AND OTHERS

A 5-YEAR PROJECT TO SPECIFY STANDARDS OF REHABILITATION CENTERS AND FACILITIES RESULTED IN THREE PUBLICATIONS. THIS MANUAL INCLUDES THE CHARACTERISTICS AND GOALS OF REHABILITATION FACILITIES. THE STANDARDS FOR ORGANIZATION, SERVICES THAT SHOULD BE PROVIDED, PERSONNEL INCLUDED, RECORDS AND REPORTS, FISCAL MANAGEMENT, AND THE PHYSICAL PLANT ARE…

Irradiation and experimental facilities at Dhruva

International Nuclear Information System (INIS)

Chakrabarty, Kunal; Mondal, Samir

2006-01-01

Research reactors are utilized to produce radioisotopes and offer irradiation facilities for testing various nuclear materials such as fuel and structural materials. Apart from providing large volume of neutron source for carrying out a variety of experiments, the research reactor forms the basic training ground for grooming up scientists and engineers for the various aspects of nuclear programme. Dhruva one of the high flux research reactors offers a maximum neutron flux level of 1.8 x 10 14 n/cm 2 /sec. It uses natural metallic uranium fuel with aluminium cladding and heavy water as coolant, moderator and reflector

X-ray microbeam stand-alone facility for cultured cells irradiation

Energy Technology Data Exchange (ETDEWEB)

Bożek, Sebastian, E-mail: sebastian.bozek@yahoo.com [Jagiellonian University Medical College, Department of Pharmaceutical Biophysics, Krakow (Poland); Bielecki, Jakub; Wiecheć, Anna; Lekki, Janusz; Stachura, Zbigniew; Pogoda, Katarzyna; Lipiec, Ewelina; Tkocz, Konrad; Kwiatek, Wojciech M. [Institute of Nuclear Physics Polish Academy of Sciences, PL-31342 Krakow (Poland)

2017-03-01

Highlights: • An X-ray microbeam line for irradiation of living cultured cells was constructed. • A step by step explanation of working principles with engineering details, procedures and calculations is presented. • A model of beam and cell interaction is presented. • A method of uniform irradiation of living cells with an exact dose per a cell is presented. • Results of preliminary experiments are presented. - Abstract: The article describes an X-ray microbeam standalone facility dedicated for irradiation of living cultured cells. The article can serve as an advice for such facilities construction, as it begins from engineering details, through mathematical modeling and experimental procedures, ending up with preliminary experimental results and conclusions. The presented system consists of an open type X-ray tube with microfocusing down to about 2 μm, an X-ray focusing system with optical elements arranged in the nested Kirckpatrick-Baez (or Montel) geometry, a sample stand and an optical microscope with a scientific digital CCD camera. For the beam visualisation an X-ray sensitive CCD camera and a spectral detector are used, as well as a scintillator screen combined with the microscope. A method of precise one by one irradiation of previously chosen cells is presented, as well as a fast method of uniform irradiation of a chosen sample area. Mathematical models of beam and cell with calculations of kerma and dose are presented. The experiments on dose-effect relationship, kinetics of DNA double strand breaks repair, as well as micronuclei observation were performed on PC-3 (Prostate Cancer) cultured cells. The cells were seeded and irradiated on Mylar foil, which covered a hole drilled in the Petri dish. DNA lesions were visualised with γ-H2AX marker combined with Alexa Fluor 488 fluorescent dye.

Conceptual design of a conveyor system for the Philippine multipurpose cobalt-60 gamma irradiation facility

International Nuclear Information System (INIS)

Borras, A.M.

1992-01-01

The Multipurpose Cobalt-60 Gamma Irradiation Facility at the PNRI presently utilizes the batch irradiation method using turntables to rotate the product boxes. The target materials or products are being carried manually or with the use of pushcart through the personnel maze. This paper presents a conceptual design for the best suitable product-handling or conveyor system for the Philippine Multipurpose Cobalt-60 Gamma Irradiation Facility. The main irradiation conveyor line shall be a 55 cm x 200 cm slat-type conveyor made of SUS 304 material that could be operated in a semi-batch continuous flow and/or shuffle-dwell method with a tact-time range of 10 min to 7 h. The products can be irradiated in a single direction, two-pass, two-sided method. (auth.). 11 refs.; 4 figs.; 2 tabs

Developing standardized facility contingency plans

International Nuclear Information System (INIS)

Davidson, D.A.

1993-01-01

Texaco consists of several operating departments that are, in effect, independent companies. Each of these departments is responsible for complying with all environmental laws and regulations. This includes the preparation by each facility to respond to an oil spill at that location. For larger spills, however, management of the response will rest with corporate regional response teams. Personnel from all departments make up the regional teams. In 1990, Congress passed the Oil Pollution Act. In 1991, the US Coast Guard began developing oil spill response contingency plan regulations, which they are still working on. Meanwhile, four of the five west coast states have also passed laws requiring contingency plans. (Only Hawaii has chosen to wait and see what the federal regulations will entail). Three of the states have already adopted regulations. Given these laws and regulations, along with its corporate structure, Texaco addressed the need to standardize local facility plans as well as its response organization. This paper discusses how, by working together, the Texaco corporate international oil spill response staff and the Texaco western region on-scene commander developed: A standard contingency plan format crossing corporate boundaries and meeting federal and state requirements. A response organization applicable to any size facility or spill. A strategy to sell the standard contingency plan and response organization to the operating units

7 CFR 205.271 - Facility pest management practice standard.

Science.gov (United States)

2010-01-01

... 7 Agriculture 3 2010-01-01 2010-01-01 false Facility pest management practice standard. 205.271... Requirements § 205.271 Facility pest management practice standard. (a) The producer or handler of an organic facility must use management practices to prevent pests, including but not limited to: (1) Removal of pest...

A proton irradiation test facility for space research in Ankara, Turkey

Science.gov (United States)

Gencer, Ayşenur; Yiǧitoǧlu, Merve; Bilge Demirköz, Melahat; Efthymiopoulos, Ilias

2016-07-01

Space radiation often affects the electronic components' performance during the mission duration. In order to ensure reliable performance, the components must be tested to at least the expected dose that will be received in space, before the mission. Accelerator facilities are widely used for such irradiation tests around the world. Turkish Atomic Energy Authority (TAEA) has a 15MeV to 30MeV variable proton cyclotron in Ankara and the facility's main purpose is to produce radioisotopes in three different rooms for different target systems. There is also an R&D room which can be used for research purposes. This paper will detail the design and current state of the construction of a beamline to perform Single Event Effect (SEE) tests in Ankara for the first time. ESA ESCC No.25100 Standard Single Event Effect Test Method and Guidelines is being considered for these SEE tests. The proton beam kinetic energy must be between 20MeV and 200MeV according to the standard. While the proton energy is suitable for SEE tests, the beam size must be 15.40cm x 21.55cm and the flux must be between 10 ^{5} p/cm ^{2}/s to at least 10 ^{8} p/cm ^{2}/s according to the standard. The beam size at the entrance of the R&D room is mm-sized and the current is variable between 10μA and 1.2mA. Therefore, a defocusing beam line has been designed to enlarge the beam size and reduce the flux value. The beam line has quadrupole magnets to enlarge the beam size and the collimators and scattering foils are used for flux reduction. This facility will provide proton fluxes between 10 ^{7} p/cm ^{2}/s and 10 ^{10} p/cm ^{2}/s for the area defined in the standard when completed. Also for testing solar cells developed for space, the proton beam energy will be lowered below 10MeV. This project has been funded by Ministry of Development in Turkey and the beam line construction will finish in two years and SEE tests will be performed for the first time in Turkey.

A spallation-based irradiation test facility for fusion and future fission materials

International Nuclear Information System (INIS)

Samec, K.; Fusco, Y.; Kadi, Y.; Luis, R.; Romanets, Y.; Behzad, M.; Aleksan, R.; Bousson, S.

2014-01-01

The EU's FP7 TIARA program for developing accelerator-based facilities has recently demonstrated the unique capabilities of a compact and powerful spallation source for irradiating advanced nuclear materials. The spectrum and intensity of the neutron flux produced in the proposed facility fulfils the requirements of the proposed DEMO fusion reactor, ADS reactors and also Gen III / IV reactors. Test conditions can be modulated, covering temperature from 400 to 550 deg. C, liquid metal corrosion, cyclical or static stress up to 500 MPa and neutron/proton irradiation damage of up to 25 DPA per annum over a volume occupying one litre. The entire 'TMIF' facility fits inside a cube 2 metres on a side, and is dimensioned for an accelerator beam power of 100 kW, thus reducing costs and offering great versatility and flexibility. (authors)

New facilities in Japan materials testing reactor for irradiation test of fusion reactor components

International Nuclear Information System (INIS)

Kawamura, H.; Sagawa, H.; Ishitsuka, E.; Sakamoto, N.; Niiho, T.

1996-01-01

The testing and evaluation of fusion reactor components, i.e. blanket, plasma facing components (divertor, etc.) and vacuum vessel with neutron irradiation is required for the design of fusion reactor components. Therefore, four new test facilities were developed in the Japan Materials Testing Reactor: an in-pile functional testing facility, a neutron multiplication test facility, an electron beam facility, and a re-weldability facility. The paper describes these facilities

Nonreactor nuclear facilities: Standards and criteria guide

International Nuclear Information System (INIS)

Brynda, W.J.; Scarlett, C.H.; Tanguay, G.E.; Lobner, P.R.

1986-09-01

This guide is a source document that identifies standards, codes, and guides that address the nuclear safety considerations pertinent to nuclear facilities as defined in DOE 5480.1A, Chapter V, ''Safety of Nuclear Facilities.'' The guidance and criteria provided is directed toward areas of safety usually addressed in a Safety Analysis Report. The areas of safety include, but are not limited to, siting, principal design criteria and safety system design guidelines, radiation protection, accident analysis, conduct of operations, and quality assurance. The guide is divided into two sections: general guidelines and appendices. Those guidelines that are broadly applicable to most nuclear facilities are presented in the general guidelines. Guidelines specific to the various types or categories of nuclear facilities are presented in the appendices. These facility-specific appendices provide guidelines and identify standards and criteria that should be considered in addition to, or in lieu of, the general guidelines. 25 figs., 62 tabs

Development of the IFJ single ion hit facility for cells irradiation

International Nuclear Information System (INIS)

Veselov, O.; Polak, W.; Ugenskiene, R.; Hajduk, R.; Lebed, K.; Lekki, J.; Horwacik, T.; Dutkiewicz, E.M.; Maranda, S.; Pieprzyca, T.; Sarnecki, C.; Stachura, Z.; Szklarz, Z.; Styczen, J.

2005-12-01

In recent years a single ion hit facility (SIHF) has been constructed at the IFJ ion microprobe. The setup is used for the precise irradiations of living cells by a controlled number of ions. The facility allows investigations in various aspects of biomedical research, such as adaptive response, bystander effect, inverse dose-rate effect, low-dose hypersensitivity, etc. Those investigations have two very important requirements: (i) cells must be examined in their natural state and environment, i.e. without previously being killed, and preferentially, neither fixed nor stained, and (ii) a possibility of automatic irradiation of large number of cells with a computer recognition of their positions must be provided. This work presents some of the crucial features of the off-line and on-line optical systems, including self-developed software responsible for the automatic cell recognition. We also show several tests carried out to determine the efficiency of the whole setup and some segments. In conclusion, the results of our first irradiation measurements performed with living cells are demonstrated. (author)

Calculation of displacement and helium production at the LAMPF irradiation facility

International Nuclear Information System (INIS)

Davidson, D.R.; Greenwood, L.R.; Sommer, W.F.; Wechsler, M.S.

1984-01-01

Differential and total displacement and helium production rates are calculated for copper irradiated by spallation neutrons and 760 MeV protons at LAMPF. The calculations are performed using the SPECTER and VNMTC computer codes, the latter being specially designed for spallation radiation damage calculations. For comparison, similar SPECTER calculations are also described for irradiation of copper in EBR-II and RTNS-II. The results indicate substantial contributions to the displacement and helium production rates due to neutrons in the high-energy tail (above 40 MeV) of the LAMPF spallation neutron spectrum. Still higher production rates are calculated for irradiations in the direct proton beam. These results will provide useful background information for research to be conducted at a new irradiation facility at LAMPF

Use of EBR-II as a principal fast breeder reactor irradiation test facility in the U.S

International Nuclear Information System (INIS)

Staker, R.G.; Seim, O.S.; Beck, W.N.; Golden, G.H.; Walters, L.C.

1975-01-01

The EBR-II as originally designed and operated by the Argonne National Laboratory was successful in demonstrating the operation of a sodium-cooled fast breeder power plant with a closed fuel reprocessing cycle. Subsequent operation has been as an experimental facility where thousands of irradiation tests have been performed. Conversion to this application entailed the design and fabrication of special irradiation subassemblies for in-core irradiations, additions to existing facilities for out-of-core irradiations, and additions to existing facilities for out-of-core experiments. Experimental subassemblies now constitute about one third of the core, and changes in the core configuration occur about monthly, requiring neutronic and thermal-hydraulics analyses and monitoring of the reactor dynamic behavior. The surveillance programs provided a wealth of information on irradiation induced swelling and creep, in-reactor fracture behavior, and the compatibility of materials with liquid sodium. (U.S.)

National Low-Temperature Neutron Irradiation Facility (NLTNIF). The status of development

International Nuclear Information System (INIS)

Coltman, R.R. Jr.; Kerchner, H.R.; Klabunde, C.E.; Young, F.W. Jr.

1985-12-01

In May 1983, the Department of Energy authorized the establishment of a National Low-Temperature Neutron Irradiation Facility (NLTNIF) at ORNL's Bulk Shielding Reactor (BSR). The NLTNIF, which will be available for qualified experiments at no cost to users, will provide a combination of high radiation intensities and special environmental and testing conditions that have not been previously available in the US. Since the DOE authorization, work has proceeded on the design and construction of the new facility without interruption. This report describes the present status of the development of the NLTNIF and the anticipated schedule for completion and performance testing. There is a table of the major specifications and capabilities and a schematic layout of the irradiation cryostate for design and dimensioning of test and experiment assemblies

Rehabilitation of broken-down chamber for the Gammacell-220 Irradiation Facility

International Nuclear Information System (INIS)

Emi-Reynolds, G.; Banini, G.K.; Ennison, I.

1997-01-01

The broken-down chamber of the gammacell-220 irradiation facility used for the calibration of dosimeters at the National Nuclear Research has been repaired. This repair work involved the identification of suitable components for the aluminum welding capable of ensuring double welding of the inside and outside joints of the chamber. Of paramount importance is the ability of the welded joint to physically sustain the safety column which is made of 26.9 kg of reinforce lead. The wielding was also expected to ensure that the shape of the chamber is retained after installation, apart from allowing uninhibited movement of the chamber which carries samples to be taken into the belly of the gamma cell for irradiation. The Ferrous ammonium sulfate (Fricke) solution was used as the dosimetry standard to check the gamma dose after restoration of the equipment. This report presents information on the procedure and justification for undertaking the repairs of this unit. By this successful repairs and putting into operation of the Gammacell-220, the maintenance team at the Center have demonstrated their ability to undertake similar works on the Gammacell-220 in the future even to other countries in the sub-region. (author). 2 refs., 2 figs

A GIF++ Gamma Irradiation Facility at the SPS H4 Beam Line

CERN Document Server

Capéans-Garrido, M; Linssen, L; Moll, M; Rembser, C

2009-01-01

The current document describes a proposal to implement a new gamma irradiation facility, combined with a high-energy particle beam in the SPS H4 beam line in hall EHN1. This new GIF++ facility is motivated by strong needs from the LHC and sLHC detector and accelerator communities for the tests of LHC components and systems.

Implementation of high-dose chemical dosimetry for industrial facilities

International Nuclear Information System (INIS)

Conceicao, Cirilo Cezar Sant'Anna da

2006-01-01

The purpose of this work is the implementation of methodology for high dose measurements using chemical dosimeters in liquid phase, traceable to the international metrology system, and make available in the country, the standard of high-dose to industrial irradiation facilities and research irradiators, trough the quality program with comparative measurements and direct use of the standard dosimeters in routine. The use of these low cost dosimetry systems in industrial irradiation facilities, assists to the certification requirements and it can reduce the costs with dosimetry for approximately 20% of the total dosimetry costs, using these systems in routine measurements and validation process, largely substituting the imported PMMA dosimeters, among others. (author)

An estimate of radiation fields in a gamma irradiation facility using fuel elements from a swimming pool reactor

International Nuclear Information System (INIS)

Narain, Rajendra

2002-01-01

A simple gamma irradiation facility set up using a few irradiated or partially irradiated swimming pool elements can be assembled to provide a convenient facility for irradiation of small and medium sized samples for research. The paper presents results of radiation levels with an arrangement using four elements from a reactor core operating at a power of 20 MW. A maximum gamma field of higher than 1 KGy/h at locations adjacent to fuel elements with negligible neutron contamination can be achieved. (author)

Design and selection criteria of a commercial irradiation facility for spices and dry products

International Nuclear Information System (INIS)

Aggarwal, K.S.

1990-01-01

Apart from cost considerations, various factors which should be taken into consideration in design of a commercial irradiation facility for spices and dry products and the factors which a user should consider for selecting a food irradiator are discussed in brief. (author)

Uncertainty Analysis of Spectral Irradiance Reference Standards Used for NREL Calibrations

Energy Technology Data Exchange (ETDEWEB)

Habte, A.; Andreas, A.; Reda, I.; Campanelli, M.; Stoffel, T.

2013-05-01

Spectral irradiance produced by lamp standards such as the National Institute of Standards and Technology (NIST) FEL-type tungsten halogen lamps are used to calibrate spectroradiometers at the National Renewable Energy Laboratory. Spectroradiometers are often used to characterize spectral irradiance of solar simulators, which in turn are used to characterize photovoltaic device performance, e.g., power output and spectral response. Therefore, quantifying the calibration uncertainty of spectroradiometers is critical to understanding photovoltaic system performance. In this study, we attempted to reproduce the NIST-reported input variables, including the calibration uncertainty in spectral irradiance for a standard NIST lamp, and quantify uncertainty for measurement setup at the Optical Metrology Laboratory at the National Renewable Energy Laboratory.

Design, fabrication and installation of irradiation facilities

International Nuclear Information System (INIS)

Kim, Yong Sung; Lee, C. Y.; Kim, J. Y.; Chi, D. Y.; Kim, S. H.; Ahn, S. H.; Kim, S. J.; Kim, J. K.; Yang, S. H.; Yang, S. Y.; Kim, H. R.; Kim, H.; Lee, K. H.; Lee, B. C.; Park, C.; Lee, C. T.; Cho, S. W.; Kwak, K. K.; Suk, H. C.

1997-07-01

The principle contents of this project are to design, fabricate and install the steady-state fuel test loop and non-instrumented capsule in HANARO for nuclear technology development. This project will be completed in 1999, the basic and detail design, safety analysis, and procurement of main equipment for fuel test loop have been performed and also the piping in gallery and the support for IPS piping in reactor pool have been installed in 1994. In the area of non-instrumented capsule for material irradiation test, the fabrication of capsule has been completed. Procurement, fabrication and installation of the fuel test loop will be implemented continuously till 1999. As besides, as these irradiation facilities will be installed in HANARO, review of safety concern, discussion with KINS for licensing and safety analysis report has been submitted to KINS to get a license and review of HANARO interface have been performed respectively. (author). 39 refs., 28 tabs., 21 figs

Design, fabrication and installation of irradiation facilities

Energy Technology Data Exchange (ETDEWEB)

Kim, Yong Sung; Lee, C. Y.; Kim, J. Y.; Chi, D. Y.; Kim, S. H.; Ahn, S. H.; Kim, S. J.; Kim, J. K.; Yang, S. H.; Yang, S. Y.; Kim, H. R.; Kim, H.; Lee, K. H.; Lee, B. C.; Park, C.; Lee, C. T.; Cho, S. W.; Kwak, K. K.; Suk, H. C. [and others

1997-07-01

The principle contents of this project are to design, fabricate and install the steady-state fuel test loop and non-instrumented capsule in HANARO for nuclear technology development. This project will be completed in 1999, the basic and detail design, safety analysis, and procurement of main equipment for fuel test loop have been performed and also the piping in gallery and the support for IPS piping in reactor pool have been installed in 1994. In the area of non-instrumented capsule for material irradiation test, the fabrication of capsule has been completed. Procurement, fabrication and installation of the fuel test loop will be implemented continuously till 1999. As besides, as these irradiation facilities will be installed in HANARO, review of safety concern, discussion with KINS for licensing and safety analysis report has been submitted to KINS to get a license and review of HANARO interface have been performed respectively. (author). 39 refs., 28 tabs., 21 figs.

Operation of post-irradiation examination facility

Energy Technology Data Exchange (ETDEWEB)

Kim, E. G.; Jeon, Y. B.; Ku, D. S.

1996-12-01

In 1996, the post-irradiation examination(PIE) of nuclear fuels was performed as follows. It has been searched for the caution of defection of defected fuel rods of Youngkwang-4 reactor through NDT and metallographic examination that had been required by KEPCO. And in-pool inspection of Kori-1 spent fuel assembly(FO2) was carried out. HVAC system and pool water treatment system have been operated to maintain the facility safely, and electric power supply system was checked and maintained for the normal and steady supply electric power to the facility. Image processing software was developed for measurement of defection of spent fuel rods. Besides, a radiation shielding glove box was fabricated and a hot cell compressor for volume reduction of radioactive materials was fabricated and installed in hot cell. Safeguards of nuclear materials were implemented in strict accordance with the relevant Korean rules and regulations as well as the international non-proliferation regime. Also the IAEA inspection was carried out on the quarterly basis. (author). 31 tabs., 71 figs., 4 refs.

Ion-Neutron Irradiated BOR60 Sample Preparation and Characterization: Nuclear Science User Facility 2017 Milestone Report

Energy Technology Data Exchange (ETDEWEB)

Linton, Kory D. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Parish, Chad M. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Smith, Quinlan B. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

2017-09-01

This document outlines the results obtained by Oak Ridge National Laboratory (ORNL) in collaboration with the University of Michigan-led Consolidated Innovative Nuclear Research project, “Feasibility of combined ion-neutron irradiation for accessing high dose levels.” In this reporting period, neutron irradiated were prepared and shipped to the University of Michigan for subsequent ion irradiation. The specimens were returned to ORNL’s Low Activation Materials Development and Analysis facility, prepared via focused ion beam for examination using scanning/transmission electron microscopy (S/TEM), and then examined using S/TEM to measure the as-irradiated microstructure. This report briefly summarizes the S/TEM results obtained at ORNL’s Low Activation Materials Development and Analysis facility.

Transfer of test samples and wastes between post-irradiation test facilities (FMF, AGF, MMF)

International Nuclear Information System (INIS)

Ishida, Yasukazu; Suzuki, Kazuhisa; Ebihara, Hikoe; Matsushima, Yasuyoshi; Kashiwabara, Hidechiyo

1975-02-01

Wide review is given on the problems associated with the transfer of test samples and wastes between post-irradiation test facilities, FMF (Fuel Monitoring Facility), AGF (Alpha Gamma Facility), and MMF (Material Monitoring Facility) at the Oarai Engineering Center, PNC. The test facilities are connected with the JOYO plant, an experimental fast reactor being constructed at Oarai. As introductory remarks, some special features of transferring irradiated materials are described. In the second part, problems on the management of nuclear materials and radio isotopes are described item by item. In the third part, the specific materials that are envisaged to be transported between JOYO and the test facilities are listed together with their geometrical shapes, dimensions, etc. In the fourth part, various routes and methods of transportation are explained with many block charts and figures. Brief explanation with lists and drawings is also given to transportation casks and vessels. Finally, some future problems are discussed, such as the prevention of diffusive contamination, ease of decontamination, and the identification of test samples. (Aoki, K.)

Remote-handling demonstration tests for the Fusion Materials Irradiation Test (FMIT) Facility

International Nuclear Information System (INIS)

Shen, E.J.; Hussey, M.W.; Kelly, V.P.; Yount, J.A.

1982-01-01

The mission of the Fusion Materials Irradiation Test (FMIT) Facility is to create a fusion-like environment for fusion materials development. Crucial to the success of FMIT is the development and testing of remote handling systems required to handle materials specimens and maintenance of the facility. The use of full scale mock-ups for demonstration tests provides the means for proving these systems

MCNP Variance Reduction technique application for the Development Of the Citrusdal Irradiation Facility

International Nuclear Information System (INIS)

Makgae, R.

2008-01-01

A private company, Citrus Research International (CIR) is intending to construct an insect irradiation facility for the irradiation of insect for pest management in south western region of South Africa. The facility will employ a Co-60 cylindrical source in the chamber. An adequate thickness for the concrete shielding walls and the ability of the labyrinth leading to the irradiation chamber, to attenuate radiation to dose rates that are acceptably low, were determined. Two methods of MCNP variance reduction techniques were applied to accommodate the two pathways of deep penetration to evaluate the radiological impact outside the 150 cm concrete walls and steaming of gamma photons through the labyrinth. The point-kernel based MicroShield software was used in the deep penetration calculations for the walls around the source room to test its accuracy and the results obtained are in good agreement with about 15-20% difference. The dose rate mapping due to radiation Streaming along the labyrinth to the facility entrance is also to be validated with the Attila code, which is a deterministic code that solves the Discrete Ordinates approximation. This file provides a template for writing papers for the conference. (authors)

MCNP Variance Reduction technique application for the Development Of the Citrusdal Irradiation Facility

Energy Technology Data Exchange (ETDEWEB)

Makgae, R. [Pebble Bed Modular Reactor (PBMR), P.O. Box 9396, Centurion (South Africa)

2008-07-01

A private company, Citrus Research International (CIR) is intending to construct an insect irradiation facility for the irradiation of insect for pest management in south western region of South Africa. The facility will employ a Co-60 cylindrical source in the chamber. An adequate thickness for the concrete shielding walls and the ability of the labyrinth leading to the irradiation chamber, to attenuate radiation to dose rates that are acceptably low, were determined. Two methods of MCNP variance reduction techniques were applied to accommodate the two pathways of deep penetration to evaluate the radiological impact outside the 150 cm concrete walls and steaming of gamma photons through the labyrinth. The point-kernel based MicroShield software was used in the deep penetration calculations for the walls around the source room to test its accuracy and the results obtained are in good agreement with about 15-20% difference. The dose rate mapping due to radiation Streaming along the labyrinth to the facility entrance is also to be validated with the Attila code, which is a deterministic code that solves the Discrete Ordinates approximation. This file provides a template for writing papers for the conference. (authors)

HiRadMat: A high‐energy, pulsed beam, material irradiation facility

CERN Multimedia

Charitonidis, Nikolaos

2016-01-01

HiRadMat is a facility constructed in 2011, designed to provide high-intensity pulsed beams to an irradiation area where different material samples or accelerator components can be tested. The facility, located at the CERN SPS accelerator complex, uses a 440 GeV proton beam with a pulse length up to 7.2 μs and a maximum intensity up to 1E13 protons / pulse. The facility, a unique place for performing state-of-the art beam-to-material experiments, operates under transnational access and welcomes and financially supports, under certain conditions, experimental teams to perform their experiments.

Design of small-animal thermal neutron irradiation facility at the Brookhaven Medical Research Reactor

International Nuclear Information System (INIS)

Liu, H.B.

1996-01-01

The broad beam facility (BBF) at the Brookhaven Medical Research Reactor (BMRR) can provide a thermal neutron beam with flux intensity and quality comparable to the beam currently used for research on neutron capture therapy using cell-culture and small-animal irradiations. Monte Carlo computations were made, first, to compare with the dosimetric measurements at the existing BBF and, second, to calculate the neutron and gamma fluxes and doses expected at the proposed BBF. Multiple cell cultures or small animals could be irradiated simultaneously at the so-modified BBF under conditions similar to or better than those individual animals irradiated at the existing thermal neutron irradiation Facility (TNIF) of the BMRR. The flux intensity of the collimated thermal neutron beam at the proposed BBF would be 1.7 x 10 10 n/cm 2 ·s at 3-MW reactor power, the same as at the TNIF. However, the proposed collimated beam would have much lower gamma (0.89 x 10 -11 cGy·cm 2 /n th ) and fast neutron (0.58 x 10 -11 cGy·cm 2 /n th ) contaminations, 64 and 19% of those at the TNIF, respectively. The feasibility of remodeling the facility is discussed

Design of an irradiation facility with thermal, epithermal and fast neutron beams

International Nuclear Information System (INIS)

Pfister, G.; Bernnat, W.; Seidel, R.; Schatz, A.K.; Wagner, F.M.; Waschkowski, W.; Schraube, H.

1992-01-01

The main features of a neutron irradiation facility to be installed at the planned research reactor FRM-II are presented. In addition to the operational possibilities of the existing facility at the reactor FRM-I, the new facility will produce quasi-monoenergetic neutron fields and a neutron beam in the keV region whose spectrum can be modified by application of suitable filters and scatterers. For this beam, which is well suited for boron capture therapy, calculated boron reaction rates inside a phantom and an experimental verification of the calculations at the existing facility are presented. (orig.) [de

American National Standard: for facilities and medical care for on-site nuclear-power-plant radiological emergencies

International Nuclear Information System (INIS)

Anon.

1979-01-01

This standard provides guidance for first aid during an emergency and for initial medical care of those persons on-site who are overexposed to penetrating radiation (irradiated). It also provides guidance for medical care of persons contaminated with radioactive material or radionuclides who may also be irradiated or injured as a result of an accident at a nuclear power plant. It provides recommendations for facilities, supplies, equipment, and the extent of care both on-site where first aid and initial care may be provided and off-site at a local hospital where further medical and surgical care may be provided. This initial care continues until either the patient is released or admitted, or referred to another, possibly distant, medical center for definitive care. Recommendations are also provided for the transportation of patients and the training of personnel. Recommendations for specialized care are considered to be beyond the scope of this standard on emergency medical care; however, since emergency and specialized care are related, a brief discussion of specialized care is provided in the Appendix

Source rack reload of the Tunisian gamma irradiation facility using Monte Carlo method

International Nuclear Information System (INIS)

Gharbi, Foued; Kadri, Omrane

2005-01-01

This work presents a Monte Carlo study of the cylindrical source rack geometry of the tunisian gamma irradiation facility, using Ge ant code of CERN. The study investigates the question of the reload of the source rack. studied configurations consist on housing four new pencils, two in the upper and two in the lower cylinder of the source rack. global dose rate uniformity inside a ''dummy's' product for the case of routine and non routine irradiation and as function of the product bulk density was calculated for eight hypothetical configurations. the same calculation was also performed for both of the original and the ideal, but not practical configuration. It was shown that hypothetical cases produced dose uniformity variations, according to product density, that were statistically no different than the original and the ideal configurations and that reload procedure can not improve the irradiation quality inside the tunisian facility

Social responsibility at a semi-industrial irradiation plant. Experience statements of ISO 26000 implementation in a nuclear facility class I

International Nuclear Information System (INIS)

Docters, Andrea S.; Lucuix, Maria B.

2009-01-01

This presentation is located in the area of radioisotopes and radiation, CNEA. Its main scope is to describe the implementation process of the international standard ISO 26000 at an irradiation facility. This project began as such by the end of 2007 with the objectives established at the Semi-Industrial Irradiation Facility ('Planta de Irradiacion Semi-Industrial'), and it consists on establishing a systematization practice and the subsequent diffusion of its results in order to spread the experience gained. The proposed standard has seven fundamental principles which gather under the term social responsibility. This project was agreed with stake holders directly involved with the facility and it is a continuum of interrelated knowledge. The fact of starting the implementation of this international standard in a relevant facility was meant to be applied in a central activity of the CNEA. The Semi-Industrial Irradiation Facility located at the Ezeiza Atomic Center has the necessary elements for its implementation and will provide after completion of the project, information of interest in order to replicate the experience in other areas. In the case of ISO 26000 the established order is considered appropriate for its application in the same government organization 'to contribute to sustainable development, health and welfare of society'. The concept of Social Responsibility, which ends its consolidation in the nineties, is a conjunction of knowledge and developments. The idea of sustainable development-oriented concept nurtured the current concern especially about the environment, linked to the Brundtland Commission Report of the late eighties which was later accepted by the Earth Summit at Rio de Janeiro in 1992. Meanwhile, the unions through their representatives played a pivotal role in linking the environment to the social perspective and interest to society, widely accepted nowadays, on the concept that appropriate measures for the environment can be extended

Irradiation setup at the U-120M cyclotron facility

Czech Academy of Sciences Publication Activity Database

Křížek, Filip; Ferencei, Jozef; Matlocha, Tomáš; Pospíšil, Jan; Príbeli, Peter; Raskina, Valentina; Isakov, Artem; Štursa, Jan; Vaňát, Tomáš; Vysoká, K.

2018-01-01

Roč. 894, č. 6 (2018), s. 87-95 ISSN 0168-9002 R&D Projects: GA MŠk LM2015056; GA MŠk LM2015058 Institutional support: RVO:61389005 Keywords : particle irradiation facility * radiation hardness * dosimetry * single event effect * single event upset * single event transient Subject RIV: BG - Nuclear, Atomic and Molecular Physics , Colliders OBOR OECD: Nuclear physics Impact factor: 1.362, year: 2016

Implementing an environmental management system in a irradiation facility

International Nuclear Information System (INIS)

O'Doherty, James

1998-01-01

Environmental management is at different stages in the countries where there are commercial irradiation facilities. There are therefore differing perspectives on the role of an Environmental Management System, ranging from compliance with the Regulatory framework to a desire to be proactive. An effective Environmental Management System (EMS) facilitates compliance, while also providing the framework for assessment and improvement of a company's environmental impact and overall performance

Standard Guide for Preparing Characterization Plans for Decommissioning Nuclear Facilities

CERN Document Server

American Society for Testing and Materials. Philadelphia

2009-01-01

1.1 This standard guide applies to developing nuclear facility characterization plans to define the type, magnitude, location, and extent of radiological and chemical contamination within the facility to allow decommissioning planning. This guide amplifies guidance regarding facility characterization indicated in ASTM Standard E 1281 on Nuclear Facility Decommissioning Plans. This guide does not address the methodology necessary to release a facility or site for unconditional use. This guide specifically addresses: 1.1.1 the data quality objective for characterization as an initial step in decommissioning planning. 1.1.2 sampling methods, 1.1.3 the logic involved (statistical design) to ensure adequate characterization for decommissioning purposes; and 1.1.4 essential documentation of the characterization information. 1.2 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate saf...

Regulation on trading of irradiated food in Latin America

Energy Technology Data Exchange (ETDEWEB)

Mastro, N.L. Del [IPEN-CNEN/ SP, Travessa R. No. 400, Cidade Universitaria 05508-900 SP, Caixa Postal 11049, Cep 05422-970, Sao Paulo (Brazil)

1997-12-31

The International Consultative Group on food Irradiation (ICGFI) was established in 1984 under the aegis of FAO, IAEA and WHO, following the adoption by the Codex Alimentarius Commission of the Codex General Standard for Irradiated foods and the Recommended International Code of Practice for the Operation of radiation Facilities for the treatment of food. Today, several countries from South America and the Caribbean have regular representatives in the ICGFI. Some of the countries also have regulations about food irradiation: Argentina, Brazil, Chile, Costa Rica, Cuba, Mexico, Peru and Uruguay. After a meeting in Peru in April 1997, Latin American countries agreed to attempt a harmonization of national laws according to an approved regional model regulation on irradiated food. The model legislation is based on the principles of the Codex General Standard for Irradiated Foods and Recommended Code of Practice for the Operation of Radiation Facilities Used for the Treatment of Foods, as well as on the relevant recommendations of the ICGFI. The model regulation establishes the authority, objectives, scope, definitions, general requirements, facilities, control procedures, documentation inspection, labeling and also provides and advisory technological dose limit by classes of food. (Author)

Regulation on trading of irradiated food in Latin America

International Nuclear Information System (INIS)

Mastro, N.L. Del

1997-01-01

The International Consultative Group on food Irradiation (ICGFI) was established in 1984 under the aegis of FAO, IAEA and WHO, following the adoption by the Codex Alimentarius Commission of the Codex General Standard for Irradiated foods and the Recommended International Code of Practice for the Operation of radiation Facilities for the treatment of food. Today, several countries from South America and the Caribbean have regular representatives in the ICGFI. Some of the countries also have regulations about food irradiation: Argentina, Brazil, Chile, Costa Rica, Cuba, Mexico, Peru and Uruguay. After a meeting in Peru in April 1997, Latin American countries agreed to attempt a harmonization of national laws according to an approved regional model regulation on irradiated food. The model legislation is based on the principles of the Codex General Standard for Irradiated Foods and Recommended Code of Practice for the Operation of Radiation Facilities Used for the Treatment of Foods, as well as on the relevant recommendations of the ICGFI. The model regulation establishes the authority, objectives, scope, definitions, general requirements, facilities, control procedures, documentation inspection, labeling and also provides and advisory technological dose limit by classes of food. (Author)

East Area Irradiation Test Facility: Preliminary FLUKA calculations

CERN Document Server

Lebbos, E; Calviani, M; Gatignon, L; Glaser, M; Moll, M; CERN. Geneva. ATS Department

2011-01-01

In the framework of the Radiation to Electronics (R2E) mitigation project, the testing of electronic equipment in a radiation field similar to the one occurring in the LHC tunnel and shielded areas to study its sensitivity to single even upsets (SEU) is one of the main topics. Adequate irradiation test facilities are therefore required, and one installation is under consideration in the framework of the PS East area renovation activity. FLUKA Monte Carlo calculations were performed in order to estimate the radiation field which could be obtained in a mixed field facility using the slowly extracted 24 GeV/c proton beam from the PS. The prompt ambient dose equivalent as well as the equivalent residual dose rate after operation was also studied and results of simulations are presented in this report.

Operation of post-irradiation examination facility

Energy Technology Data Exchange (ETDEWEB)

Kim, Eun Ka; Park, Kwang Joon; Jeon, Yong Bum [and others; Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

1995-02-01

In 1995, the post-irradiation examination (PIE) of nuclear fuels was performed as follows. The relation between burnup and top nozzle spring force of fuel assembly was obtained by measuring the holddown spring force on the Kori-1 reactor fuel assemblies. The resonance ultrasonic test for inspection of defect and moisture in fuel rod was carried out on fuel rods of C15 and J14 assemblies, and the change of fuel rod condition by storing in pool has been analyzed on the intentionally defected fuel rods (ID-C and ID-L) as well as intact fuel rod (1-2) by NDT in ht cell. The oxide layer thickness on cladding surface of J44-L12 fuel rod was measured by NDT method and metallography to reveal the oxidation as a function of temperature in the fuel rod, and the burnup of J44 fuel assembly was measured by chemical analysis. HVAC system and pool water treatment system of the PIE facility were continuously operated for air filtration and water purification. The monitoring of radiation and pool water in PIE facility has been carried out to maintain the facility safety, and electric power supply system was checked and maintained to supply the electric power to the facility normally. The developed measurement techniques of oxide layer thickness on fuel rod cladding and holddown spring force of top nozzle in fuel assembly were applied to examine the nuclear fuels. Besides, a radiation shielding glove box was designed and a hot cell compressor for volume reduction of radioactive materials was fabricated. 19 tabs., 38 figs., 7 refs. (Author) .new.

High-energy, twelve-channel laser facility (DEFIN) for spherical irradiation of thermonuclear targets

International Nuclear Information System (INIS)

Basov, N.G.; Danilov, A.E.; Krokhin, O.N.; Kruglov, B.V.; Mikhailov, Yu.A.; Sklizkov, G.V.; Fedotov, S.I.; Fedorov, A.N.

This paper describes a high-energy, twelve-channel laser facility (DELFIN) intended for high-temperature heating of thermonuclear targets with spherical symmetry. The facility includes a neodymium-glass laser with the ultimate radiation energy of 10 kJ, a pulse length of approximately 10 -10 to 10 -9 s, beam divergence of 5 x 10 -4 radians, a vacuum chamber in which laser radiation interacts with the plasma, and a system of diagnostic instrumentation for the observation of laser beam and plasma parameters. Described are the optical scheme and construction details of the laser facility. Presented is an analysis of focusing schemes for target irradiation and described is the focusing scheme of the DELFIN facility, which is capable of attaining a high degree of spherical symmetry in irradiating targets with maximum beam intensity at the target surface of approximately 10 15 W/cm 2 . This paper examines the most important problems connected with the physical investigations of thermonuclear laser plasma and the basic diagnostic problems involved in their solution

IFMIF - International Fusion Materials Irradiation Facility Conceptual Design Activity/Interim Report

International Nuclear Information System (INIS)

Rennich, M.J.

1995-12-01

Environmental acceptability, safety, and economic viability win ultimately be the keys to the widespread introduction of fusion power. This will entail the development of radiation- resistant and low- activation materials. These low-activation materials must also survive exposure to damage from neutrons having an energy spectrum peaked near 14 MeV with annual radiation doses in the range of 20 displacements per atom (dpa). Testing of candidate materials, therefore, requires a high-flux source of high energy neutrons. The problem is that there is currently no high-flux source of neutrons in the energy range above a few MeV. The goal, is therefore, to provide an irradiation facility for use by fusion material scientists in the search for low-activation and damage-resistant materials. An accellerator-based neutron source has been established through a number of international studies and workshops' as an essential step for materials development and testing. The mission of the International Fusion Materials Irradiation Facility (IFMIF) is to provide an accelerator-based, deuterium-lithium (D-Li) neutron source to produce high energy neutrons at sufficient intensity and irradiation volume to test samples of candidate materials up to about a full lifetime of anticipated use in fusion energy reactors. would also provide calibration and validation of data from fission reactor and other accelerator-based irradiation tests. It would generate material- specific activation and radiological properties data, and support the analysis of materials for use in safety, maintenance, recycling, decommissioning, and waste disposal systems

Fuels and materials research under the high neutron fluence using a fast reactor Joyo and post-irradiation examination facilities

International Nuclear Information System (INIS)

Soga, Tomonori; Ito, Chikara; Aoyama, Takafumi; Suzuki, Soju

2009-01-01

The experimental fast reactor Joyo at Oarai Research and Development Center (ORDC) of Japan Atomic Energy Agency (JAEA) is Japan's sodium-cooled fast reactor (FR). In 2003, this reactor's upgrade to the 140MWt MK-III core was completed to increase the irradiation testing capability. The MK-III core provides the fast neutron flux of 4.0x10 15 n/cm 2 s as an irradiation test bed for improving the fuels and material of FR in Japan. Three post-irradiation examination (PIE) facilities named FMF, MMF and AGF related to Joyo are in ORDC. Irradiated subassemblies and core components are carried into the FMF (Fuel Monitoring Facility) and conducted nondestructive examinations. Each subassembly is disassembled to conduct some destructive examinations and to prepare the fuel and material samples for further detailed examinations. Fuel samples are sent to the AGF (Alpha-Gamma Facility), and material samples are sent to the MMF (Materials Monitoring Facility). These overall and elaborate data provided by PIE contribute to investigate the irradiation effect and behavior of fuels and materials. This facility complex is indispensable to promote the R and D of FR in Japan. And, the function and technology of irradiation test and PIE enable to contribute to the R and D of innovative fission or fusion reactor material which will be required to use under the high neutron exposure. (author)

External irradiation facilities open for biological studies - progress in july 2005

International Nuclear Information System (INIS)

Gaillard-Lecanu, E.; Authier, N.; Verrey, B.; Bailly, I.; Bordy, J.M.; Coffigny, H.; Cortela, L.; Duval, D.; Leplat, J.J.; Poncy, J.L.; Testard, I.; Thuret, J.Y.

2005-01-01

The Life Science Division of the Atomic Energy Commission is making an inventory of the various radiation sources accessible for investigation on the biological effects of ionizing radiation. In this field, a wide range of studies is being carried out at the Life Science Division, attempting to characterize the kind of lesions with their early biological consequences (on the various cell compartments) and their late biological consequences (deterministic or stochastic effects), in relation to the radiation type and dose, especially at low doses. Several experimental models are available: plants, bacteria, eukaryotic cells from yeast up to mammalian cells and in vivo studies, mostly on rodents, in order to characterize the somatic late effects and the hereditary effects. Due to the significant cost of these facilities, also to their specific properties (nature of the radiation, dose and dose rate, possible accuracy of the irradiation at the molecular level), the closeness is no longer the only criteria for biologists to make a choice. The current evolution is to set up irradiation infrastructures combining ionizing radiation sources themselves and specific tools dedicated to biological studies: cell or molecular biology laboratories, animal facilities. The purpose, in this new frame, is to provide biologists with the most suitable facilities, and, if possible, to change these facilities according to requirements in radiobiology. In this report, the basics of interactions of ionizing radiation with biological tissues are briefly introduced, followed by a presentation of some of the facilities available for radiobiological studies especially at CEA. This panorama is not a comprehensive one, new data will be included as they advance, whether reporting existing facilities or if a new one is developed. (authors)

Prospects of establishing food irradiation facilities in Kenya

International Nuclear Information System (INIS)

Mustapha, A.O.; Patel, J.P.; Rathore, I.V.S.; Hashim, N.O.; Kinyua, A.M.

2001-01-01

Full text: A national project of food irradiation in the country is being proposed. At present there are no facilities for food irradiation (and food irradiation research) in Kenya. This report is therefore largely comparative between the traditional and the conventional food preservation methods on the one hand and the irradiation technique on the other. The report is also based on information from other countries where food irradiation is practiced (Kawabata, 1981) or is being also contemplated (Diop et al, 1997), as well as on the relevant report of the International Atomic Energy Agency (IAEA) on this topic (IAEA, 1993). The paper presents the statement of the research problem, i.e., in Kenya large quantities of food and other farm produces go to waste annually as a result of the inadequacies of the preservation techniques currently in use. These (other) preservation techniques, although often less controversial than the irradiation techniques, have also been found to be more expensive to run when compared to irradiation techniques. Such techniques, presently employed in Kenya, include the traditional methods (e.g. sun drying, smoke and fire drying, etc.) and modern techniques such as freezing or refrigeration, lyophilization, etc., as well as application of chemicals like insecticides and fumigants. The latter combines the disadvantages of high costs with environmental pollution and associated health risks. In this preliminary research, aimed at studying the prospects of a national food irradiation project, the following food items that are selected for their importance to the economy of the country, include potatoes, rice, maize, coffee, tea, various fruits, fish and meat. The paper also explores the economic feasibility as well as the human and technological requirements of establishing a commercial food irradiation plant, with aim of assessing the applicability of food irradiation as alternative or a complimentary approach for preservation technique in

Performance studies under high irradiation of resistive bulk-micromegas chambers at the CERN Gamma Irradiation Facility

CERN Document Server

Sidiropoulou, Ourania; Bortfeldt, J; Farina, E; Iengo, P; Longo, L; Sidiropoulou, O; Wotschack, J

2017-01-01

Radiation studies on several resistive bulk-Micromegas chambers produced at CERN will be viewed in this document. Two resistive bulk-Micromegas chambers have been installed at the CERN Gamma Irradiation Facility (GIF++) exposed to an intense gamma irradiation with the aim of evaluating the detector behaviour under high irradiation and carrying out a long-term age- ing study. The chambers under study have an active area of 10 x 10 cm 2 , a strip pitch of 400 m m , an ampli- fication gap of 128 m m , and a drift gap of 5 mm. The results on the detector performance as a function of the photon flux up to 44 MHz/cm 2 will be shown as well as the ageing properties as function of the integrated charge and the current intensity and its stability with time. In addition, the results of the efficiency measurements before, during, and after the irradiation will also be presented as a function of the amplification voltage at which the chambers are operated.

Dose rate determinations in the Portuguese Gamma Irradiation Facility: Monte Carlo simulations and measurements

International Nuclear Information System (INIS)

Oliveira, C.; Salgado, J.; Ferro de Carvalho, A.

2000-01-01

A simulation study of the Portuguese Gamma Irradiation Facility, UTR, has been carried out using the MCNP code. The work focused on the optimisation of the dose distribution inside the irradiation cell, dose calculations inside irradiated samples and dose calculations in critical points for protection purposes. Calculations were carried out at points inside and outside the irradiation cell, where different behaviour was expected (distance from the source, radiation absorption and scattering in irradiator structure and walls). The contributions from source, irradiator structure, sample material, carriers, walls, ceiling and floor to the photon spectra and air kerma at those points are reported and discussed. Air kerma measurements were also carried out using an ionisation chamber. Good agreement was found between experimental and calculated air kermas. (author)

Neutron irradiation facilities for fission and fusion reactor materials studies

International Nuclear Information System (INIS)

Rowcliffe, A.F.

1985-01-01

The successful development of energy-conversion machines based upon nuclear fission or fusion reactors is critically dependent upon the behavior of the engineering materials used to construct the full containment and primary heat extraction systems. The development of radiation damage-resistant materials requires irradiation testing facilities which reproduce, as closely as possible, the thermal and neutronic environment expected in a power-producing reactor. The Oak Ridge National Laboratory (ORNL) reference core design for the Center for Neutron Research (CNR) reactor provides for instrumented facilities in regions of both hard and mixed neutron spectra, with substantially higher fluxes than are currently available. The benefits of these new facilities to the development of radiation damage resistant materials are discussed in terms of the major US fission and fusion reactor programs

Evaluate of environment quality for γ irradiation facilities using fuzzy comprehensive judgment method

International Nuclear Information System (INIS)

Ha Yiming

2002-01-01

The environment quality of Jining Irradiation Centre new γ radiation facility was evaluated by fuzzy comprehensive judgment method. The result showed that the place of γ radiation facility was well and the measures of radiate shelter and environment protect were effective. The environment quality of its area was not obvious change and the result of environment evaluation was first-rate

Gamma exposure rate estimation in irradiation facilities of nuclear research reactors

International Nuclear Information System (INIS)

Daoud, Adrian

2009-01-01

There are experimental situations in the nuclear field, in which dose estimations due to energy-dependent radiation fields are required. Nuclear research reactors provide such fields under normal operation or due to radioactive disintegration of fission products and structural materials activation. In such situations, it is necessary to know the exposure rate of gamma radiation the different materials under experimentation are subject to. Detectors of delayed reading are usually used for this purpose. Direct evaluation methods using portable monitors are not always possible, because in some facilities the entrance with such devices is often impracticable and also unsafe. Besides, these devices only provide information of the place where the measurement was performed, but not of temporal and spatial fluctuations the radiation fields could have. In this work a direct evaluation method was developed for the 'in-situ' gamma exposure rate for the irradiation facilities of the RA-1 reactor. This method is also applicable in any similar installation, and may be complemented by delayed evaluations without problem. On the other hand, it is well known that the residual effect of radiation modifies some properties of the organic materials used in reactors, such as density, colour, viscosity, oxidation level, among others. In such cases, a correct dosimetric evaluation enables in service estimation of material duration with preserved properties. This evaluation is for instance useful when applied to lubricating oils for the primary circuit pumps in nuclear power plants, thus minimizing waste generation. In this work the necessary elements required to estimate in-situ time and space integrated dose are also established for a gamma irradiated sample in an irradiation channel of a nuclear facility with zero neutron flux. (author)

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

International Nuclear Information System (INIS)

Israr, M.; Shami, Qamar-ud-din; Pervez, S.

1997-11-01

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

NEW IRRADIATION RESEARCH FACILITIES AT THE ARMY NATICK LABORATORIES

Energy Technology Data Exchange (ETDEWEB)

Cooper, R. D.; Brynjolfsson, A.

1963-03-15

New facilities built by the U. S. Army for research on the preservation of food by ionizing radiation consist of a food processing and packaging facility and a radiation sources laboratory with two powerful low-energy radiation sources. One is a 1.3 million-curie Co/sup 60/ source consisting of 98 tubes each containing four doubly encapsulated Co/sup 60/ slugs. The second source is an electron linear accelerator with energy variable between 2 and 32 Mev. Research with the Co/sup 60/ source is concentrated on investigation of macroscopic and microscopic dose distribution in different materials irradiated with Co/sup 60/ gamma rays. Research with the linear accelerator is concentrated on dosimetry and photonuclear reactions. (A.G.W.)

FiBi - A French network of facilities for irradiation in biology: The organisation of the network and the research opportunities associated

International Nuclear Information System (INIS)

Gaillard-Lecanu, E.; Coffigny, H.; Poncy, J.L.; Authier, N.; Verrey, B.; Bailly, I.; Baldacchino, G.; Bordy, J.M.; Carriere, M.; Leplat, J.J.; Pin, S.; Pommeret, S.; Thuret, J.Y.; Renault, J.P.; Cortella, I.; Duval, D.; Khodja, H.; Testard, I.

2006-01-01

The Life Science Division of the Atomic Energy Commission has developed a national network of available irradiation facilities for biological studies. One aim is to optimise the irradiation of biological samples, through a compendium of existing facilities allowing for the preserving and the irradiation of these samples in good conditions, and for providing an appropriate and reliable dosimetry. Given the high cost of the facilities and their specialization (nature and precision of irradiation on a cell scale, dose and dose rate), closeness is no longer the only criteria of choice for biologists. Development is leaning towards the implementation of irradiation platforms gathering irradiation tools associated with specific methods belonging to biology: cell culture, molecular biology and even animal care houses. The aim is to be able to offer biologists the most appropriate experimental tools, and to modify them according to the changing needs of radiobiology. This work is currently in progress and the database is still not exhaustive and shall be implemented as and when new documents are drawn up and new facilities are opened. (author)

Influence of different irradiation facilities on the response of radioprotection devices

International Nuclear Information System (INIS)

Heeren de Oliveira, A.

1984-05-01

An EIC 1 extrapolation chamber, flushed with a methan based tissue equivalent gas is presented. This measuring device serves as a reference instrument to calibrate in tissue absorbed dose beta beams from different irradiation facilities; point radioactive sources, sources used with beam flattening filters, large area sources simulated by moving a point source. The source to detector distance has to be greater than 3 cm, requiring a transfer dosemeter for smaller distances. Influence of these different irradiation geometries has been studied on several radioprotection instruments (babyline, individual dosemeter, ionisation chamber), using three radionucleides: 147 Pm, 204 Tl, 90 Sr + 90 Y [fr

Proposal and Evaluation of Subordinate Standard Solar Irradiance Spectra: Preprint

Energy Technology Data Exchange (ETDEWEB)

Habte, Aron M [National Renewable Energy Laboratory (NREL), Golden, CO (United States); Wilbert, Stefan [German Aerospace Center (DLR); Jessen, Wilko [German Aerospace Center (DLR); Gueymard, Chris [Solar Consulting Services; Polo, Jesus [CIEMAT; Bian, Zeqiang [China Meteorological Administration; Driesse, Anton [Photovoltaic Performance Labs; Marzo, Aitor [University of Antofagasta; Armstrong, Peter [Masdar Institute of Science & Technology; Vignola, Frank [University of Oregon; Ramirez, Lourdes [CIEMAT

2018-04-12

This paper introduces a concept for global tilted irradiance (GTI) subordinate standard spectra to supplement the current standard spectra used in solar photovoltaic applications as defined in ASTM G173 and IEC60904. The proposed subordinate standard spectra correspond to atmospheric conditions and tilt angles that depart significantly from the main standard spectrum, and they can be used to more accurately represent various local conditions. For the definition of subordinate standard spectra cases with an elevation 1.5 km above sea level, the question arises whether the air mass should be calculated including a pressure correction or not. This study focuses on the impact of air mass used in standard spectra, and it uses data from 29 locations to examine which air mass is most appropriate for GTI and direct normal irradiance (DNI) spectra. Overall, it is found that the pressure-corrected air mass of 1.5 is most appropriate for DNI spectra. For GTI, a non-pressure-corrected air mass of 1.5 was found to be more appropriate.

Simulation for evaluation of the multi-ion-irradiation Laboratory of TechnoFusion facility and its relevance for fusion applications

International Nuclear Information System (INIS)

Jimenez-Rey, D.; Mota, F.; Vila, R.; Ibarra, A.; Ortiz, Christophe J.; Martinez-Albertos, J.L.; Roman, R.; Gonzalez, M.; Garcia-Cortes, I.; Perlado, J.M.

2011-01-01

Thermonuclear fusion requires the development of several research facilities, in addition to ITER, needed to advance the technologies for future fusion reactors. TechnoFusion will focus in some of the priority areas identified by international fusion programmes. Specifically, the TechnoFusion Area of Irradiation of Materials aims at surrogating experimentally the effects of neutron irradiation on materials using a combination of ion beams. This paper justifies this approach using computer simulations to validate the multi-ion-irradiation Laboratory. The planned irradiation facility will investigate the effects of high energetic radiations on reactor-relevant materials. In a second stage, it will also be used to analyze the performance of such materials and evaluate newly designed materials. The multi-ion-irradiation Laboratory, both triple irradiation and high-energy proton irradiation, can provide valid experimental techniques to reproduce the effect of neutron damage in fusion environment.

Dismantling of Irradiation Facility Selfshielded of Investigation Model MPX- γ-25M

International Nuclear Information System (INIS)

Soguero, D.; Rapado, M.; Prieto, E.; Desdin, L.; Guerra, M.; Castillo, J.

2011-01-01

In this paper is described the dismantling a category I selfshielded gamma irradiation facility model MPX - γ - 25M. The following specific objectives were established: a) identify aspects of the insurance contract, human and technical resources b) assess the radiological situation of the process and c) analyze potential radiological extraordinary events in each step of the process, ensuring appropriate responses, based on an evaluation of process safety. The assessment of radiological events can serve as a reference for addressing the process of dismantling other similar irradiators. (Author)

Calculation of damage function of Al{sub 2}O{sub 3} in irradiation facilities for fusion reactor applications

Energy Technology Data Exchange (ETDEWEB)

Mota, F., E-mail: fernando.mota@ciemat.es [Laboratorio Nacional de Fusión por Confinamiento Magnético – CIEMAT, 28040 Madrid (Spain); Ortiz, C.J., E-mail: christophe.ortiz@ciemat.es [Laboratorio Nacional de Fusión por Confinamiento Magnético – CIEMAT, 28040 Madrid (Spain); Vila, R., E-mail: rafael.vila@ciemat.es [Laboratorio Nacional de Fusión por Confinamiento Magnético – CIEMAT, 28040 Madrid (Spain); Casal, N., E-mail: natalia.casal@ciemat.es [Laboratorio Nacional de Fusión por Confinamiento Magnético – CIEMAT, 28040 Madrid (Spain); García, A., E-mail: angela.garcia@ciemat.es [Laboratorio Nacional de Fusión por Confinamiento Magnético – CIEMAT, 28040 Madrid (Spain); Ibarra, A., E-mail: Angel.ibarra@ciemat.es [Laboratorio Nacional de Fusión por Confinamiento Magnético – CIEMAT, 28040 Madrid (Spain)

2013-11-15

A rigorous material testing program is essential for the development of the nuclear fusion world program. In particular, it is very important to predict the generation of the displacement damage in materials, because the irradiation intensity expected in fusion conditions is such that the performance of materials and components under these extreme conditions is unknown. To study the damage produced by neutrons in materials of interest for fusion, a specific computational methodology was developed. Neutron fluxes expected in different irradiation facilities (International Fusion Materials Irradiation Facility [IFMIF] and DEMO-HCLL) and in different irradiation spots were obtained with particles transport codes (McDeLicious, MCNP). The energy differential cross sections of primary knock-on atoms were calculated using the NJOY code. Resulting data were input into the Monte Carlo code MARLOWE to calculate the corresponding displacements (i.e., interstitials (I) and vacancies (V)). However, the number of Frenkel pairs created during irradiation strongly depends on the recombination radius between interstitials and vacancies. This parameter corresponds to the minimum distance below which instantaneous recombination occurs. Mainly, the influence of such parameter on the damage function in Al{sub 2}O{sub 3} was assessed in this report. The displacements per atom values calculated as a function of the recombination radius considered are compared to experimental data to determine the most appropriate capture radius. In addition, the damage function and damage dose generated at different experimental irradiation facilities are compared with those expected in DEMO. The conclusion is that both IFMIF and TechnoFusión (future triple beam ion accelerator to emulate fusion neutron irradiation effects in materials) facilities are suited to perform relevant irradiation experiments for the design of DEMO.

Microdosimetric measurements in the thermal neutron irradiation facility of LENA reactor

International Nuclear Information System (INIS)

Colautti, P.; Moro, D.; Chiriotti, S.; Conte, V.; Evangelista, L.; Altieri, S.; Bortolussi, S.; Protti, N.; Postuma, I.

2014-01-01

A twin TEPC with electric-field guard tubes has been constructed to be used to characterize the BNCT field of the irradiation facility of LENA reactor. One of the two mini TEPC was doped with 50 ppm of 10 B in order to simulate the BNC events occurring in BNCT. By properly processing the two microdosimetric spectra, the gamma, neutron and BNC spectral components can be derived with good precision (∼6%). However, direct measurements of 10 B in some doped plastic samples, which were used for constructing the cathode walls, point out the scarce accuracy of the nominal 10 B concentration value. The influence of the Boral ® door, which closes the irradiation channel, has been measured. The gamma dose increases significantly (+51%) when the Boral ® door is closed. The crypt-cell-regeneration weighting function has been used to measure the quality, namely the RBE µ value, of the radiation field in different conditions. The measured RBE µ values are only partially consistent with the RBE values of other BNCT facilities. - Highlights: • A counter with two mini TEPCs, both equipped with electrical-field guard tubes, has been constructed. • The microdosimetric spectrum of the LENA-reactor irradiation vane has been studied. • The radiation-field quality (RBE) assessment confirms that the D n /D tot ratio is not an accurate parameter to characterize the BNCT radiation field

A new apparatus at hyper irradiation research facility at the Atomic Research Center, University of Tokyo

International Nuclear Information System (INIS)

Shibata, Hiromi; Iwai, Takeo; Narui, Makoto; Omata, Takao

1996-01-01

In the hyper irradiation research facility at the Atomic Research Center, the University of Tokyo, following apparatuses were newly installed for accelerator relating apparatus on 1995 fiscal year; 1) Hyper ion microbeam analysis apparatus, 2) Fourier conversion infrared microscopy, 3) Pico second two-dimensional fluorescence measuring apparatus, 4) Femto second wave-length reversible pulse laser radiation apparatus, and others. In addition to double irradiation, pulse beam irradiation experiment and so forth characteristic in conventional hyper irradiation research apparatus, upgrading of material irradiation experiments using these new apparatuses are intended. (G.K.)

A new apparatus at hyper irradiation research facility at the Atomic Research Center, University of Tokyo

Energy Technology Data Exchange (ETDEWEB)

Shibata, Hiromi; Iwai, Takeo; Narui, Makoto; Omata, Takao [Tokyo Univ. (Japan). Research Center for Nuclear Science and Technology

1996-12-01

In the hyper irradiation research facility at the Atomic Research Center, the University of Tokyo, following apparatuses were newly installed for accelerator relating apparatus on 1995 fiscal year; (1) Hyper ion microbeam analysis apparatus, (2) Fourier conversion infrared microscopy, (3) Pico second two-dimensional fluorescence measuring apparatus, (4) Femto second wave-length reversible pulse laser radiation apparatus, and others. In addition to double irradiation, pulse beam irradiation experiment and so forth characteristic in conventional hyper irradiation research apparatus, upgrading of material irradiation experiments using these new apparatuses are intended. (G.K.)

MYRRHA, A Flexible Fast Spectrum Irradiation Facility. Current Status of Design

International Nuclear Information System (INIS)

Baeten, Peter; Fernandez, Rafaël; De Bruyn, Didier; Van den Eynde, Gert; Leysen, Paul; Aït Abderrahim, Hamid; Castelliti, Diego

2011-01-01

R and D program in support of MYRRHA: • Several R&D required for MYRRHA components: - LBE corrosion; - O 2 control in LBE; - Irradiated material properties. • Experimental facilities foreseen in the near future in support of MYRRHA at SCK•CEN premacies: - E-SCAPE: Thermal-hydraulic pool facility with 1:6 scale ratio with MYRRHA; - Liliputter: Pump test loop; - COMPLOT: Isothermal hydraulic loop representing one fuel channel/IPS at full high; - PHX mock-up testing concept, fouling, flow-induced vibrations, (SGTR)…; • Experimental facilities foreseen in the near future in support of MYRRHA at SCK•CEN premacies (continued): - Safety/control rod; - Fuel bundle; - Target window; - Component test pool; - Fuel loader; - Robotic arm; • All experiments planned to be finished before 2016

Staged deployment of the International Fusion Materials Irradiation Facility

International Nuclear Information System (INIS)

Takeuchi, H.; Sugimoto, M.; Nakamura, H.

2001-01-01

The International Fusion Materials Irradiation Facility (IFMIF) employs an accelerator based D-Li intense neutron source as defined in the 1995-96 Conceptual Design Activity (CDA) study. In 1999, IEA mandated a review of the CDA IFMIF design for cost reduction without change to its original mission. This objective was accomplished by eliminating the previously assumed possibility of potential upgrade of IFMIF beyond the user requirements. The total estimated cost was reduced from $797.2 M to $487.8 M. An option of deployment in 3 stages was also examined to reduce the initial investment and annual expenditures during construction. In this scenario, full performance is achieved gradually with each interim stage as follows. 1st Stage: 20% operation for material selection for ITER breeding blanket, 2nd Stage: 50% operation to demonstrate materials performance of a reference alloy for DEMO, 3rd Stage: full performance operation ( 2MW/m 2 at 500cm 3 ) to obtain engineering data for potential DEMO materials under irradiation up to 100-200 dpa. In summary, the new, reduced cost IFMIF design and staged deployment still satisfies the original mission. The estimated cost of the 1st Stage facility is only $303.6 M making it financially much more attractive. Currently, IFMIF Key Element Technology Phase (KEP) is underway to reduce the key technology risk factors. (author)

High Exposure Facility Technical Description

Energy Technology Data Exchange (ETDEWEB)

Carter, Gregory L.; Stithem, Arthur R.; Murphy, Mark K.; Smith, Alex K.

2008-02-12

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

Status of ANSI standards on decommissioning of nuclear reprocessing facilities

International Nuclear Information System (INIS)

Graham, H.B.

1975-01-01

A definition of decommissioning is given, and the preparation of ANSI Standard, ''General Design Criteria for Nuclear Reprocessing Facilities'' (N101.3) is discussed. A Eurochemic report, entitled ''The Shutdown of Reprocessing Facilities--Results of Preliminary Studies on the Installations Belonging to Eurochemic,'' was used in the preparation of this standard. (U.S.)

Environmental monitoring standardization of effluent from nuclear fuel cycle facilities in China

International Nuclear Information System (INIS)

Gao Mili

1993-01-01

China has established some environmental monitoring standards of effluent from nuclear fuel cycle facilities. Up to date 33 standards have been issued; 10 to be issued; 11 in drafting. These standards cover sampling, gross activities measurement, analytical methods and management rules and so on. They involve with almost all nuclear fuel cycle facilities and have formed a complete standards system. By the end of the century, we attempt to draft a series of analytical and determination standards in various environmental various medium, they include 36 radionuclides from nuclear fuel cycle facilities. (3 tabs.)

Application of an experimental irradiation facility type K-120 for the radiation treatment of agricultural products in large quantity

International Nuclear Information System (INIS)

Stenger, V.; Foeldiak, G.; Horvath, I.; Hargittai, P.; Bartfai, Cs.

1979-01-01

During experimental and pilot irradiation carried out by the 60 Co irradiation facility type K-120 of the Institute of Isotopes of the Hungarian Academy of Sciences an irradiation technology for the treatment of agricultural and food products of considerable density has been developed. Applying transport containers of commercial size the intermittent radiation treatment of great quantity products was made possible with homogeneous dose distribution. The radiation technical characteristics, the utilization coefficient and the capacity of the facility for every agricultural product were calculated. (author)

Dosimetry of blood irradiator - 2000

International Nuclear Information System (INIS)

Mhatre, Sachin G.V.; Shinde, S.H.; Bhat, R.M.; Rao, Suresh; Sharma, D.N.

2008-01-01

Full text: Blood transfusion to an immunodeficient or immunosuppressed patient has a high risk involved due to occurrence of Transfusion Graft Versus Host Disease (T-GVHD). In order to eliminate this problem, blood is routinely exposed to ionizing radiation (gamma) prior to transfusion. Doses ranging from 15 Gy to 50 Gy can prevent T-GVHD. Aim of the present work was to perform dosimetry of 60 Co Blood Irradiator-2000 developed by Board of Radiation and isotope Technology (BRIT), India; using FBX dosimetric system. Dose-rate measured by FBX dosimeter was intercompared with Fricke dosimeter, which is a Reference Standard dosimeter. Experiments included measurement of dose-rate at the centre of irradiation volume, dose mapping in the central vertical plane within the irradiation volume and measurement of average dose received by blood sample using blood bags filled with FBX dosimeter by simulating actual irradiation conditions. During irradiation, the sample chamber is retracted into a cylindrical source cage, so that the sample is irradiated from all sides uniformly. Blood irradiator-2000 has sample rotation facility for increasing the dose uniformity during irradiation. The performance of this was investigated by measuring the central vertical plane dose profile in stationary state as well in rotation using the sample rotation facility (60 rpm). FBX being an aqueous dosimetric system fills container of irregular shape being irradiated hence can be used to integrate the dose over the volume. Dose-rate measured by FBX dosimeter was intercompared with Fricke dosimeter, which was in good agreement. Average dose-rate at the centre of irradiation volume and within the blood bag was measured by FBX and Fricke dosimeters. It was observed that dose profiles measured by FBX and Fricke dosimeters agreed within ± 2%. Dose uniformity within the irradiation volume was found to reduce from 21% to 17% when the sample rotation facility was used. Thus, it is suggested by the

2 MeV, 60 kW dual-beam type electron accelerator irradiation facility

International Nuclear Information System (INIS)

Yotsumoto, Keiichi; Kanazawa, Takao; Haruyama, Yasuyuki; Agematsu, Takashi; Mizuhashi, Kiyoshi; Sunaga, Hiromi; Washino, Masamitsu; Tamura, Naoyuki

1984-02-01

The specification of new irradiation facility which has been constructed from 1978 through 1981 as the replacement of 1st Accelerator of JAERI, TRCRE are described. The accelerator is the Cockcroft-Walton type and both vertical and horizontal accelerating tubes are arranged on a single high voltage generator. Transferring of the high voltage to the horizontal accelerating tube is performed with the high voltage changing system in the pressure vessel. The output ratings of the accelerator are 2 MV of acceleration voltage and 30 mA of beam current. By providing the dual beam system, two irradiation rooms, one for vertical and the other for horizontal beam, are independently operationable. Persons can enter the horizontal irradiation room for experimental setting even when the vertical irradiation room is in operation. The specification of the buildings, the exhaust air treatment system, the irradiation conveyor and the safety observation system are also described. (author)

MCNPCX calculations of dose rates and spectra in experimental channels of the CTEx irradiating facility

International Nuclear Information System (INIS)

Gomes, Renato G.; Rebello, Wilson F.; Vellozo, Sergio O.; Junior, Luis M.; Vital, Helio C.; Rusin, Tiago; Silva, Ademir X.

2013-01-01

MCNPX simulations have been performed in order to calculate dose rates as well as spectra along the four experimental channels of the gamma irradiating facility at the Technology Center of the Brazilian Army (CTEx). Safety, operational and research requirements have led to the need to determine both the magnitude and spectra of the leaking gamma fluxes. The CTEx experimental facility is cavity type with a moveable set of 28 horizontally positioned rods, filled with Cesium-137 chloride and doubly encased in stainless steel that yields an approximately plane 42 kCi-source that provides a maximum dose rate of about 1.5 kG/h into two irradiating chambers. The channels are intended for irradiation tests outside facility. They would allow larger samples to be exposed to lower gamma dose rates under controlled conditions. Dose rates have been calculated for several positions inside the channels as well as at their exits. In addition, for purposes related to the safety of operators and personnel, the angles submitted by the exiting beams have also been evaluated as they spread when leaving the channels. All calculations have been performed by using a computational model of the CTEx facility that allows its characteristics and operation to be accurately simulated by using the Monte Carlo Method. Virtual dosimeters filled with Fricke (ferrous sulfate) were modeled and positioned throughout 2 vertical channels (top and bottom) and 2 horizontal ones (front and back) in order to map dose rates and gamma spectrum distributions. The calculations revealed exiting collimated beams in the order of tenths of Grays per minute as compared to the maximum 25 Gy / min dose rate in the irradiator chamber. In addition, the beams leaving the two vertical channels were found to exhibit a widespread cone-shaped distribution with aperture angle ranging around 85 deg. The data calculated in this work are intended for use in the design of optimized experiments (better positioning of samples and

Existing and projected neutron sources and low-temperature irradiation facilities in Germany

International Nuclear Information System (INIS)

Boening, K.

1984-01-01

In this paper, a contribution given at the Kyoto University Research Reactor Institute to the temporal meeting on the design of the facilities for high flux, low temperature irradiation is summarized. The following five subjects were discussed. The project of modernizing the swimming pool type research reactor FRM with 4 MW power at Munich is to achieve relatively high thermal neutron flux, and an extremely compact core is designed. The existing low temperature irradiation facility (LTIF) of the FRM is the most powerful in the world, and has been successfully operated more than 20 years. The fast and thermal neutron fluxes are 2.9 x 10 13 and 3.5 x 10 13 /cm 2 sec, respectively. The experimental techniques in the LTIF of the FRM, such as a measuring cryostat, the mounting of irradiated samples and so on, are described. The installation of new LTIFs in connection with the projects of advanced neutron sources in Germany is likely to be made in the modernized FRM at Garching, in the spallation neutron source SNQ at KFA Juelich and so on. The interesting problems in fundamental and applied researches with LTIFs, and the unusual application of LTIFs are shown. (Kako, I.)

Optimization of the irradiation beam in the BNCT research facility at IEA-R1 reactor

International Nuclear Information System (INIS)

Castro, Vinicius Alexandre de

2014-01-01

Boron Neutron Capture Therapy (BNCT) is a radiotherapeutic technique for the treatment of some types of cancer whose useful energy comes from a nuclear reaction that occurs when thermal neutron impinges upon a Boron-10 atom. In Brazil there is a research facility built along the beam hole number 3 of the IEA-R1 research reactor at IPEN, which was designed to perform BNCT research experiments. For a good performance of the technique, the irradiation beam should be mostly composed of thermal neutrons with a minimum as possible gamma and above thermal neutron components. This work aims to monitor and evaluate the irradiation beam on the sample irradiation position through the use of activation detectors (activation foils) and also to propose, through simulation using the radiation transport code, MCNP, new sets of moderators and filters which shall deliver better irradiation fields at the irradiation sample position In this work, a simulation methodology, based on a MCNP card, known as wwg (weight window generation) was studied, and the neutron energy spectrum has been experimentally discriminated at 5 energy ranges by using a new set o activation foils. It also has been concluded that the BNCT research facility has the required thermal neutron flux to perform studies in the area and it has a great potential for improvement for tailoring the irradiation field. (author)

Bulk-shield design for the Fusion Materials Irradiation Test facility

International Nuclear Information System (INIS)

Carter, L.L.; Mann, F.M.; Morford, R.J.; Johnson, D.L.; Huang, S.T.

1982-07-01

The accelerator-based Fusion Materials Irradiation Test (FMIT) facility will provide a high-fluence, fusion-like radiation environment for the testing of materials. While the neutron spectrum produced in the forward direction by the 35 MeV deuterons incident upon a flowing lithium target is characterized by a broad peak around 14 MeV, a high energy tail extends up to about 50 MeV. Some shield design considerations are reviewed

The radiation field in the New Gamma Irradiation Facility GIF++ at CERN

CERN Document Server

Pfeiffer, Dorothea

2017-09-11

The high-luminosity LHC (HL-LHC) upgrade is setting now a new challenge for particle detector technologies. The increase in luminosity will produce a particle background in the gas-based muon detectors that is ten times higher than under conditions at the LHC. The detailed knowledge of the detector performance in the presence of such a high background is crucial for an optimized design and efficient operation after the HL-LHC upgrade. A precise understanding of possible aging effects of detector materials and gases is of extreme importance. To cope with these challenging requirements, a new Gamma Irradiation Facility (GIF++) was designed and built at the CERN SPS North Area as successor of the Gamma Irradiation Facility (GIF) during the Long Shutdown 1 (LS1) period. It features an intense source of 662 keV photons with adjustable intensity, to simulate continuous background over large areas, and, combined with a high energy muon beam, to measure detector performance in the presence of the background. The new ...

A simple irradiation facility for radiobiological experiments with low energy protons from a cyclotron

International Nuclear Information System (INIS)

Mukherjee, B.

1982-01-01

An experimental facility for irradiation of small biological targets with low-energy protons has been developed. The depth-dose distribution in soft-tissue is calculated from the proton energy spectrum. (orig.)

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

International Nuclear Information System (INIS)

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

1995-01-01

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

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

International Nuclear Information System (INIS)

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

1996-01-01

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

The proposed cold neutron irradiation facility at the Breazeale reactor

International Nuclear Information System (INIS)

Dimeo, R. M.; Sokol, P. E.; Carpenter, J. M.

1997-01-01

We discuss the design considerations of a Cold Neutron Irradiation Facility (CNIF) originally to have been installed at the Penn State Breazeale Reactor (PSBR). The goal of this project was to study the effects of radiation-induced damage to cryogenic moderators and, in particular, solid methane. This work evolved through the design stage undergoing a full safety analysis and received tentative approval from the PSBR Safeguards Committee but was discontinued due to budgetary constraints. (auth)

Assessment of gold flux monitor at irradiation facilities of MINT TRIGA MK II reactor

International Nuclear Information System (INIS)

Wee Boon Siong; Abdul Khalik Wood; Mohd Suhaimi Hamzah; Shamsiah Abdul Rahman; Md Suhaimi Elias; Nazaratul Ashifa Abd Salim

2005-01-01

Neutron source of MINTs TRIGA MK II reactor has been used for activation analysis for many years and neutron flux plays important role in activation of samples at various positions. Currently, two irradiation facilities namely the pneumatic transfer system and rotary rack are available to cater for short and long lived irradiation. Neutron flux variation for both irradiation facilities have been determined using gold wire and gold solution as flux monitor. However, the use of gold wire as flux monitor is costlier if compared to gold solution. The results from analysis of certified reference materials showed that gold solution as flux monitors yield satisfactory results and proved to safe cost on the purchasing of gold wire. Further experiment on self-shielding effects of gold solution at various concentrations has been carried out. This study is crucial in providing vital information on the suitable concentration for gold solution as flux monitor. In the near future, gold solution flux monitor will be applied for routine analysis and hence to improve the capability of the laboratory on neutron activation analysis. (Author)

In situ ion irradiation/implantation studies in the HVEM-Tandem Facility at Argonne National Laboratory

International Nuclear Information System (INIS)

Allen, C.W.; Funk, L.L.; Ryan, E.A.; Taylor, A.

1988-09-01

The HVEM-Tandem User Facility at Argonne National Laboratory interfaces two ion accelerators, a 2 MV tandem accelerator and a 650 kV ion implanter, to a 1.2 MV high voltage electron microscope. This combination allows experiments involving simultaneous ion irradiation/ion implantation, electron irradiation and electron microscopy/electron diffraction to be performed. In addition the availability of a variety of microscope sample holders permits these as well as other types of in situ experiments to be performed at temperatures ranging from 10-1300 K, with the sample in a stressed state or with simultaneous determination of electrical resistivity of the specimen. This paper summarizes the details of the Facility which are relevant to simultaneous ion beam material modification and electron microscopy, presents several current applications and briefly describes the straightforward mechanism for potential users to access this US Department of Energy supported facility. 7 refs., 1 fig., 1 tab

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

International Nuclear Information System (INIS)

Miyashita, Makoto; Sugimoto, Masayoshi; Yutani, Toshiaki

2007-03-01

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

Post-irradiation examination and R and D programs using irradiated fuels at KAERI

International Nuclear Information System (INIS)

Chun, Yong Bum; Min, Duck Kee; Kim, Eun Ka and others

2000-12-01

This report describes the Post-Irradiation Examination(PIE) and R and D programs using irradiated fuels at KAERI. The objectives of post-irradiation examination (PIE) for the PWR irradiated fuels, CANDU fuels, HANARO fuels and test fuel materials are to verify the irradiation performance and their integrity as well as to construct a fuel performance data base. The comprehensive utilization program of the KAERI's post-irradiation examination related nuclear facilities such as Post-Irradiation Examination Facility (PIEF), Irradiated Materials Examination Facility (IMEF) and HANARO is described

Post-irradiation examination and R and D programs using irradiated fuels at KAERI

International Nuclear Information System (INIS)

Chun, Yong Bum; So, Dong Sup; Lee, Byung Doo; Lee, Song Ho; Min, Duck Kee

2001-09-01

This report describes the Post-Irradiation Examination(PIE) and R and D programs using irradiated fuels at KAERI. The objectives of post-irradiation examination (PIE) for the PWR irradiated fuels, CANDU fuels, HANARO fuels and test fuel materials are to verify the irradiation performance and their integrity as well as to construct a fuel performance data base. The comprehensive utilization program of the KAERI's post-irradiation examination related nuclear facilities such as Post-Irradiation Examination Facility (PIEF), Irradiated Materials Examination Facility (IMEF) and HANARO is described

Development of a training programme for radiation protection officers in industrial irradiators

International Nuclear Information System (INIS)

Mumuni, I. I.

2014-01-01

The International Basic Safety Standards (BSS) for Protection against Ionizing Radiation and for the Safety of Radiation Sources establish the basic requirements for protection against the risks associated with exposure to ionizing radiation and for the safety of radiation sources that may deliver such exposure. One important aspect of the Safety Standard is education and training of all personnel involved in the activities of radiation and radioactive sources. According to the BSS a Radiation Protection Officer is an individual technically competent in radiation protection matters relevant for a given type of practice who is designated by the registrant or licensee to oversee the application of the requirements of the standards. By this assigned role, radiation protection officers for industrial irradiators should be adequately trained since these facilities involve very high dose rates during irradiation, such that a person accidentally exposed can receive a lethal dose within minutes or seconds and fatalities can occur. This training among others things will enable the radiation protection officers to understand practical application of the IAEA Safety Standard to industrial irradiator facilities, understand the requirements for safety assessments and emergency plans, be able to develop a radiation protection programme for irradiators, be familiar with the different types of industrial irradiators and their applications and understand the safety philosophy and design requirements for industrial irradiators. (author)

Economic study for the establishment of A food irradiation facility at port said harbour

International Nuclear Information System (INIS)

EL-Gameel, E.A.

2004-01-01

The present study discusses the economic aspects of establishing food irradiation facility at Port Said harbour and the effect of various parameters on the unit processing costs. The study is concerned with carrying out an economic evaluation for the application of food exports from Port Said harbour and the marketing and technical aspects where the suitable commodity mix has been determined for the agricultural crops which were proposed for irradiation. The investment criteria utilized for commercial evaluation were internal rate of return (IRR) and pay back period (PEP). The irradiation cost and the additional income are also discussed. The results of this analysis showed that the establishment of food irradiation unit in Port Said harbour in Egypt would be economically feasible

Characterization of the irradiation facilities SINCA and SIRCA of the TRIGA Mark III reactor using the code MCNPX

International Nuclear Information System (INIS)

Delfin L, A.; Garcia M, T.; Lucatero, M. A.; Cruz G, H. S.; Gonzalez, J. A.; Vargas E, S.

2011-11-01

The commitment of changing fuels of high enrichment for fuels of low enrichment in the TRIGA Mark III reactor of the Nuclear Center of Mexico generates the necessity to know the distribution of the spectrum of the neutrons flux in the irradiation facilities like they are: the Pneumatic System of Capsules Irradiation and the Rotational System of Capsules Irradiation. Is very important for the experiments design as well as for the reactor safety to know the profiles of the neutrons flux and the spectrum that these maintain with the mixed core with which operates, to effect of conserving the same characteristics when the reactor core will be operated with fuel of low enrichment totally. Also, knowing the profiles of the neutrons flux, the reactor operators can optimize the irradiation conditions of the processed samples and likewise the users can select the irradiation positions more adaptable to their necessities. This work present the characterization of the neutron flux in the irradiation facilities SINCA and SIFCA, calculated with the code MCNPX. (Author)

Design and construction of γ-rays irradiation facility for remote-handling parts and components of fusion reactor

International Nuclear Information System (INIS)

Yagi, Toshiaki; Morita, Yousuke; Seguchi, Tadao

1995-03-01

For the evaluation of radiation resistance of remote-handling system for International Thermonuclear Experimental Reactor(ITER), 'high dose-rate and high temperature (upper 350degC) γ-rays irradiation facility' was designed and constructed. In this facility, the parts and components of remote-handling system such as sensing devices, motors, optical glasses, wires and cables, etc., are tested by irradiation with 2x10 6 Roentgen/h Co-60 γ-rays at a temperature up to 350degC under various atmospheres (dry nitrogen gas, argon gas, dry air and vacuum). (author)

Neutron irradiation of seeds 2

Energy Technology Data Exchange (ETDEWEB)

1968-10-01

The irradiation of seeds with the fast neutron of research reactors has been hampered by difficulties in accurately measuring dose and in obtaining repeatable and comparable results. Co-ordinated research under an international program organized by the FAO and IAEA has already resulted in significant improvements in methods of exposing seeds in research reactors and in obtaining accurate dosimetry. This has been accomplished by the development of a standard reactor facility for the neutron irradiation of seeds and standard methods for determining fast-neutron dose and the biological response after irradiation. In this program various divisions of the IAEA and the Joint FAO/IAEA Division co-operate with a number of research institutes and reactor centres throughout the world. Results of the preliminary experiments were reported in Technical Reports Series No. 76, ''Neutron Irradiation of Seeds''. This volume contains the proceedings of a meeting of co-operators in the FAO/IAEA Neutron Seed Irradiation Program and other active scientists in this field. The meeting was held in Vienna from 11 to 15 December 1967. Refs, figs and tabs.

Neutron irradiation of seeds 2

International Nuclear Information System (INIS)

1968-01-01

The irradiation of seeds with the fast neutron of research reactors has been hampered by difficulties in accurately measuring dose and in obtaining repeatable and comparable results. Co-ordinated research under an international program organized by the FAO and IAEA has already resulted in significant improvements in methods of exposing seeds in research reactors and in obtaining accurate dosimetry. This has been accomplished by the development of a standard reactor facility for the neutron irradiation of seeds and standard methods for determining fast-neutron dose and the biological response after irradiation. In this program various divisions of the IAEA and the Joint FAO/IAEA Division co-operate with a number of research institutes and reactor centres throughout the world. Results of the preliminary experiments were reported in Technical Reports Series No. 76, ''Neutron Irradiation of Seeds''. This volume contains the proceedings of a meeting of co-operators in the FAO/IAEA Neutron Seed Irradiation Program and other active scientists in this field. The meeting was held in Vienna from 11 to 15 December 1967. Refs, figs and tabs

Food Irradiation Regulations And Code Of Practice

International Nuclear Information System (INIS)

Jimba, B.W. Centre For Energy Research And Training, Ahmadu Bello University, Zaria,

1996-01-01

Official attitude towards irradiated food is determined by factors such as: level of scientific knowledge, consumer habits, food shortages, agricultural production and technological know-how. To date, 39 countries have accepted the process for one or more food items while 27 nations carry out the process on a commercial basis. Regulations and codes of practice is essential for consumer confidence while uniformity of regulations, at the international level, will enhance international trade in irradiated food items. The internationally accepted Codex Standard on irradiated food and Codes of Practice for the operation of irradiation facilities, adopted in 1983, forms the basis for International regulations and a template for nations in the development of regulations. This paper discusses the basic legal requirements for licensing the process, procedures, facility and the operator and suggests a framework for a national regulation based on experiences of Hungary, Brazil and Israel

Standard Guide for Packaging Materials for Foods to Be Irradiated

CERN Document Server

American Society for Testing and Materials. Philadelphia

2009-01-01

1.1 This guide provides a format to assist producers and users of food packaging materials in selecting materials that have the desirable characteristics for their intended use and comply with applicable standards or government authorizations. It outlines parameters that should be considered when selecting food-contact packaging materials intended for use during irradiation of prepackaged foods and it examines the criteria for fitness for their use. 1.2 This guide identifies known regulations and regulatory frameworks worldwide pertaining to packaging materials for holding foods during irradiation; but it does not address all regulatory issues associated with the selection and use of packaging materials for foods to be irradiated. It is the responsibility of the user of this guide to determine the pertinent regulatory issues in each country where foods are to be irradiated and where irradiated foods are distributed. 1.3 This guide does not address all of the food safety issues associated with the synergisti...

International Fusion Materials Irradiation Facility conceptual design activity. Present status and perspective

International Nuclear Information System (INIS)

Kondo, Tatsuo; Noda, Kenji; Oyama, Yukio

1998-01-01

For developing the materials for nuclear fusion reactors, it is indispensable to study on the neutron irradiation behavior under fusion reactor conditions, but there is not any high energy neutron irradiation facility that can simulate fusion reactor conditions at present. Therefore, the investigation of the IFMIF was begun jointly by Japan, USA, Europe and Russia following the initiative of IEA. The conceptual design activities were completed in 1997. As to the background and the course, the present status of the research on heavy irradiation and the testing means for fusion materials, the requirement and the technical basis of high energy neutron irradiation, and the international joint design activities are reported. The materials for fusion reactors are exposed to the neutron irradiation with the energy spectra up to 14 MeV. The requirements from the users that the IFMIF should satisfy, the demand of the tests for the materials of prototype and demonstration fusion reactors and the evaluation of the neutron field characteristics of the IFMIF are discussed. As to the conceptual design of the IFMIF, the whole constitution, the operational mode, accelerator system and target system are described. (K.I.)

The RaDIATE High-Energy Proton Materials Irradiation Experiment at the Brookhaven Linac Isotope Producer Facility

Energy Technology Data Exchange (ETDEWEB)

Ammigan, Kavin; et al.

2017-05-01

The RaDIATE collaboration (Radiation Damage In Accelerator Target Environments) was founded in 2012 to bring together the high-energy accelerator target and nuclear materials communities to address the challenging issue of radiation damage effects in beam-intercepting materials. Success of current and future high intensity accelerator target facilities requires a fundamental understanding of these effects including measurement of materials property data. Toward this goal, the RaDIATE collaboration organized and carried out a materials irradiation run at the Brookhaven Linac Isotope Producer facility (BLIP). The experiment utilized a 181 MeV proton beam to irradiate several capsules, each containing many candidate material samples for various accelerator components. Materials included various grades/alloys of beryllium, graphite, silicon, iridium, titanium, TZM, CuCrZr, and aluminum. Attainable peak damage from an 8-week irradiation run ranges from 0.03 DPA (Be) to 7 DPA (Ir). Helium production is expected to range from 5 appm/DPA (Ir) to 3,000 appm/DPA (Be). The motivation, experimental parameters, as well as the post-irradiation examination plans of this experiment are described.

Determination of proton and neutron spectra in the LANSCE spallation irradiation facility

International Nuclear Information System (INIS)

James, M.R.; Maloy, S.A.; Sommer, W.F.; Fowler, M.M.; Dry, D.; Ferguson, P.D.; Mueller, G.; Corzine, R.K.

1999-01-01

Materials samples were recently irradiated in the Los Alamos Radiation Effects Facility (LASREF) at the Los Alamos Neutron Science Center (LANSCE) to provide data for the Accelerator Production of Tritium (APT) project on the effect of irradiation on the mechanical and physical properties of materials. The targets were configured to expose samples to a variety of radiation environments including, high-energy protons, mixed protons and high-energy neutrons, and low-energy neutrons. The samples were irradiated for approximately six months during a ten month period using an 800 MeV proton beam with a circular Gaussian shape of approximately 2σ = 3.0 cm. At the end of this period, the samples were extracted and tested. Activation foils were also extracted that had been placed in proximity to the materials samples. These were used to quantify the fluences in various locations

Doserate mapping studies of the Multipurpose Gamma Irradiation Facility after hoist cable replacement

International Nuclear Information System (INIS)

Banini, G.K.; Emi-Reynolds, G.

1998-01-01

Irradiation of ethanol chlorobenzene dosimeters (ECB) in air have been carried out in an attempt to map out and confirm the gamma dose field for the inner and outer chambers of the Gamma Irradiation Facility at the Radiation Technology Centre after the replacement of the 5mm diameter stainless weak hoist cables by a 6mm one. The results obtained were compared with expected dose rate values (regressed from the suppliers readings) for the various positions within the irradiation chamber. Our study reveal that the replacement of the hoist cables have been done correctly within specifications and that the dose rate map has not been affected. The significance of the work to routine radiation processing are discussed. (author). 6 refs.; 8 figs

The radiological accident at the irradiation facility in Nesvizh

International Nuclear Information System (INIS)

1996-01-01

More than 40 years of experience in radiation processing has shown that such technology is generally used safely, and steady improvement in the design of facilities and careful selection and training of operators have contributed to this good safety record. However, some cases of circumvention of safety systems have been registered and it is documented that the consequences of radiological accidents at industrial radiation facilities can be extremely serious. The causes of accidents may have some points in common, but at the same time may be highly specific. A detailed study of these common and specific features seems to be of great importance for further improvements in safety systems. One such event occurred on 26 October 1991 at an industrial sterilization facility in Nesvizh, Belarus, when the operator entered the irradiation chamber and was severely exposed to a lethal dose of radiation. The significant feature of this case was related to the medical management. It should be underlined that some circumstances of the accident only came to light during the post-accident review made by the IAEA. To document the causes and consequences of the accident and to define the lessons learned are of help to those people with responsibility for the safety of such facilities and to those medical authorities who might be involved in the management of a radiation event. 16 refs, figs, tabs, photographs

Large-scale Samples Irradiation Facility at the IBR-2 Reactor in Dubna

CERN Document Server

Cheplakov, A P; Golubyh, S M; Kaskanov, G Ya; Kulagin, E N; Kukhtin, V V; Luschikov, V I; Shabalin, E P; León-Florián, E; Leroy, C

1998-01-01

The irradiation facility at the beam line no.3 of the IBR-2 reactor of the Frank Laboratory for Neutron Physics is described. The facility is aimed at irradiation studies of various objects with area up to 800 cm$^2$ both at cryogenic and ambient temperatures. The energy spectra of neutrons are reconstructed by the method of threshold detector activation. The neutron fluence and $\\gamma$ dose rates are measured by means of alanine and thermoluminescent dosimeters. The boron carbide and lead filters or $(n/\\gamma)$ converter provide beams of different ratio of doses induced by neutrons and photons. For the lead filter, the flux of fast neutrons with energy more than 0.1 MeV is $1.4 \\cdot 10^{10}$ \\fln and the neutron dose is about 96\\% of the total radiation dose. For the $(n/\\gamma)$ converter, the $\\gamma$ dose rate is $\\sim$500 Gy h$^{-1}$ which is about 85\\% of the total dose. The radiation hardness tests of GaAs electronics and materials for the ATLAS detector to be put into operation at the Large Hadron ...

Modification of preheated tungsten surface after irradiation at the GOL-3 facility

Energy Technology Data Exchange (ETDEWEB)

Shoshin, A.A., E-mail: shoshin@mail.ru [Budker Institute of Nuclear Physics SB RAS, Novosibirsk 630090 (Russian Federation); Novosibirsk State University, Novosibirsk 630090 (Russian Federation); Arakcheev, A.S.; Arzhannikov, A.V. [Budker Institute of Nuclear Physics SB RAS, Novosibirsk 630090 (Russian Federation); Novosibirsk State University, Novosibirsk 630090 (Russian Federation); Burdakov, A.V. [Budker Institute of Nuclear Physics SB RAS, Novosibirsk 630090 (Russian Federation); Novosibirsk State Technical University, Novosibirsk 630092 (Russian Federation); Huber, A. [Forschungszentrum Jülich GmbH, Institut für Energie- und Klimaforschung, 52425 Jülich (Germany); Ivanov, I.A. [Budker Institute of Nuclear Physics SB RAS, Novosibirsk 630090 (Russian Federation); Novosibirsk State University, Novosibirsk 630090 (Russian Federation); Kuklin, K.N. [Budker Institute of Nuclear Physics SB RAS, Novosibirsk 630090 (Russian Federation); Polosatkin, S.V.; Postupaev, V.V.; Sinitsky, S.L. [Budker Institute of Nuclear Physics SB RAS, Novosibirsk 630090 (Russian Federation); Novosibirsk State University, Novosibirsk 630090 (Russian Federation); Vasilyev, A.A. [Novosibirsk State University, Novosibirsk 630090 (Russian Federation)

2016-12-15

Highlights: • Preheated tungsten was irradiated at the GOL-3 facility with plasma loads corresponding to the ITER type I ELMs. • The crack pattern and the quantity of bubbles depend on the initial temperatures of the target. • The orientation of major crack networks correlates with the direction of machining of the samples. • Dust impact craters were found. - Abstract: The study is devoted to tungsten surface modification after irradiation at the GOL-3 facility with plasma loads corresponding to the ITER type I ELMs. In order to emulate heating with a steady plasma flux in the ITER divertor, some of the tungsten samples were preheated up to 500 °C. It was found out that the behavior of the surface modification (the crack pattern and the number of bubbles) depends on the initial temperature of the targets. While the orientation of major crack networks correlates with the direction of machining of the samples. Afterwards we have observed the process of craters’ formation caused by dust particle impacts.

Commercial gamma-ray irradiation plant in Japan

Energy Technology Data Exchange (ETDEWEB)

Tomita, K; Sugimoto, S [Radia Industry Co. Ltd., Gunma (Japan)

1977-01-01

In 1973, a commercial gamma-ray irradiation plant was constructed in Takasaki, about 100 km north of Tokyo. The plant has been used for both production of irradiated commercial products and irradiation services. The irradiation services are being made available for sterilization of both medical appliances such as disposable medical syringes, catheters, surgical sutures, and sterilization of feed stuffs for animals. Treatment of plastic materials and colouring of both crystals and glass wares are also undertaken. This facility can accommodate 600 kCi of /sup 60/Co and has a monthly treating capacity of 12,000 packages ( a standard carton of 340 mm x 400 mm x 500 mm) at an irradiation dose of 1 Mrad/hr. A receiving port for packages is on the second floor and the outlet of the irradiated packages on the first floor, with three lines of connecting loop conveyors between them, and the irradiation compartment in the center section. The space arrangement of the facility is well designed and gravity can be utilized for the transportation of the packages. Polymer impregnated coral is put on the market for ornamental building material on an order contract basis.

IFMIF (International Fusion Materials Irradiation Facility) key element technology phase interim report

International Nuclear Information System (INIS)

Nakamura, Hiroo; Ida, Mizuho; Sugimoto, Masayoshi; Takeuchi, Hiroshi; Yutani, Toshiaki

2002-03-01

Activities of International Fusion Materials Irradiation Facility (IFMIF) have been performed under an IEA collaboration since 1995. IFMIF is an accelerator-based deuteron (D + )-lithium (Li) neutron source designed to produce an intense neutron field (2 MW/m 2 , 20 dpa/year for Fe) in a volume of 500 cm 3 for testing candidate fusion materials. In 2000, a 3 year Key Element technology Phase (KEP) of IFMIF was started to reduce the key technology risk factors. This interim report summarizes the KEP activities until mid 2001 in the major project work-breakdown areas of accelerator, target, test facilities and design integration. (author)

Radiation studies on resistive bulk-micromegas chambers at the CERN Gamma Irradiation Facility

CERN Document Server

Alvarez Gonzalez, Barbara; Camerlingo, Maria Teresa; Farina, Edoardo; Iengo, Paolo; Longo, Luigi; Samarati, Jerome; Sidiropoulou, Ourania; Wotschack, Joerg

2018-01-01

With the growing diffusion of resistive Micromegas detectors in HEP experiments the study of long-term aging behaviour is becoming more and more relevant. Two resistive bulk-Micromegas detectors were installed in May 2015 at the CERN Gamma Irradiation Facility and exposed to an intense gamma irradiation with the aim to study the detector behavior under high irradiation and the long-term aging. The detectors have an active area of 10 × 10 cm 2 , readout strip pitch of 400 μ m , amplification gap of 128 μ m and drift gap of 5 mm. The desired accumulated charge of more than 0.2 C/cm 2 has been reached for both chambers, equivalent to 10 years of HL-LHC operation. The efficiency, amplification, and resolution of the Micromegas after this long-term irradiation period is compared with the performance of a non irradiated detector. In addition, the latest results of the measured particle rate as a function of the amplification voltage is presented and compared with those obtained in 2015.

Process control and dosimetry in a multipurpose irradiation facility

International Nuclear Information System (INIS)

Cabalfin, E.G.; Lanuza, L.G.; Solomon, H.M.

1998-01-01

Complete text of publication follows. To introduce and demonstrate radiation processing to the local industries, the Philippine Nuclear Research Institute (PNRI) with the technical assistance of the International Atomic Energy Agency (IAEA) has set up a pilot scale multipurpose gamma irradiation facility. Though on a limited scale, this has led to the commercial radiation sterilization and decontamination of various products, such as empty aluminum tubes, empty gelatin capsules, spices and fresh onions. Process control in this facility involves dose measurement to ensure that the products receive the required dose to get the desired beneficial effect. Prior to routine processing, dose distribution studies to determine the locations of minimum and maximum absorbed dose are undertaken for each product and product-source geometry. The product loading pattern, which meets the required dose uniformity ratio and which gives the optimum amount of product per loading is then chosen. During routine irradiation, dosimeters are placed at the minimum and maximum absorbed dose positions of a process load. If locations of minimum or maximum dose are not readily accessible, dosimeters are placed at reference positions. The relationship of the absorbed dose at these reference positions with the absorbed dose at the minimum or maximum position is established beforehand. Fricke and ethanol chlorobenzene (ECB) dosimeters are used to measure absorbed dose. PNRI participates in the International Dose Assurance Service (IDAS) of IAEA. Results show that absorbed dose as measured by alanine agreed with ECB within 5%, while that from Fricke agreed to within 2%

Process control and dosimetry in a multipurpose irradiation facility

Energy Technology Data Exchange (ETDEWEB)

Cabalfin, E G; Lanuza, L G; Solomon, H M [Philippine Nuclear Research Institute, Diliman, Quezon City (Philippines)

1999-12-31

Complete text of publication follows. To introduce and demonstrate radiation processing to the local industries, the Philippine Nuclear Research Institute (PNRI) with the technical assistance of the International Atomic Energy Agency (IAEA) has set up a pilot scale multipurpose gamma irradiation facility. Though on a limited scale, this has led to the commercial radiation sterilization and decontamination of various products, such as empty aluminum tubes, empty gelatin capsules, spices and fresh onions. Process control in this facility involves dose measurement to ensure that the products receive the required dose to get the desired beneficial effect. Prior to routine processing, dose distribution studies to determine the locations of minimum and maximum absorbed dose are undertaken for each product and product-source geometry. The product loading pattern, which meets the required dose uniformity ratio and which gives the optimum amount of product per loading is then chosen. During routine irradiation, dosimeters are placed at the minimum and maximum absorbed dose positions of a process load. If locations of minimum or maximum dose are not readily accessible, dosimeters are placed at reference positions. The relationship of the absorbed dose at these reference positions with the absorbed dose at the minimum or maximum position is established beforehand. Fricke and ethanol chlorobenzene (ECB) dosimeters are used to measure absorbed dose. PNRI participates in the International Dose Assurance Service (IDAS) of IAEA. Results show that absorbed dose as measured by alanine agreed with ECB within 5%, while that from Fricke agreed to within 2%.

Diagnostic x-ray equipment compliance and facility survey. Recommended procedures for equipment and facility testing

International Nuclear Information System (INIS)

1994-01-01

The Radiation Protection Bureau has set out guidelines for the testing of diagnostic x-ray equipment and facilities. This guide provides information for the x-ray inspector, test engineer, technologist, medical physicist and any other person responsible for verifying the regulatory compliance or safety of diagnostic x-ray equipment and facilities. Diagnostic x-radiation is an essential part of present day medical practice. The largest contributor of irradiation to the general population comes from diagnostic x-radiation. Although individual irradiations are usually small, there is a concern of possible excess cancer risk when large populations are irradiated. Unnecessary irradiations to patients from radiological procedures can be significantly reduced with little or no decrease in the value of medical diagnostic information. This can be achieved by using well designed x-ray equipment which is installed, used and maintained by trained personnel, and by the adoption of standardized procedures. In general, when patient surface dose is reduced, there is a corresponding decrease in dose to x-ray equipment operators and other health care personnel. 2 tabs., 4 figs

Diagnostic x-ray equipment compliance and facility survey. Recommended procedures for equipment and facility testing

Energy Technology Data Exchange (ETDEWEB)

NONE

1994-12-31

The Radiation Protection Bureau has set out guidelines for the testing of diagnostic x-ray equipment and facilities. This guide provides information for the x-ray inspector, test engineer, technologist, medical physicist and any other person responsible for verifying the regulatory compliance or safety of diagnostic x-ray equipment and facilities. Diagnostic x-radiation is an essential part of present day medical practice. The largest contributor of irradiation to the general population comes from diagnostic x-radiation. Although individual irradiations are usually small, there is a concern of possible excess cancer risk when large populations are irradiated. Unnecessary irradiations to patients from radiological procedures can be significantly reduced with little or no decrease in the value of medical diagnostic information. This can be achieved by using well designed x-ray equipment which is installed, used and maintained by trained personnel, and by the adoption of standardized procedures. In general, when patient surface dose is reduced, there is a corresponding decrease in dose to x-ray equipment operators and other health care personnel. 2 tabs., 4 figs.

Shield design for the Fusion Materials Irradiation Test facility

International Nuclear Information System (INIS)

Carter, L.L.; Mann, F.M.; Morford, R.J.; Wilcox, A.D.; Johnson, D.L.; Huang, S.T.

1983-03-01

The shield design for the Fusion Materials Irradiation Test facility is based upon one-, two- and three-dimensional transport calculations with experimental measurements utilized to refine the nuclear data including the neutron cross sections from 20 to 50 MeV and the gamma ray and neutron source terms. The high energy neutrons and deuterons produce activation products from the numerous reactions that are kinematically allowed. The analyses for both beam-on and beam-off (from the activation products) conditions have required extensive nuclear data libraries and the utilization of Monte Carlo, discrete ordinates, point kernel and auxiliary computer codes

FFTF [Fast Flux Test Facility] management

International Nuclear Information System (INIS)

Bennett, C.L.

1986-11-01

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

SNL/CA Facilities Management Design Standards Manual

Energy Technology Data Exchange (ETDEWEB)

Rabb, David [Sandia National Lab. (SNL-CA), Livermore, CA (United States); Clark, Eva [Sandia National Lab. (SNL-CA), Livermore, CA (United States)

2014-12-01

At Sandia National Laboratories in California (SNL/CA), the design, construction, operation, and maintenance of facilities is guided by industry standards, a graded approach, and the systematic analysis of life cycle benefits received for costs incurred. The design of the physical plant must ensure that the facilities are "fit for use," and provide conditions that effectively, efficiently, and safely support current and future mission needs. In addition, SNL/CA applies sustainable design principles, using an integrated whole-building design approach, from site planning to facility design, construction, and operation to ensure building resource efficiency and the health and productivity of occupants. The safety and health of the workforce and the public, any possible effects on the environment, and compliance with building codes take precedence over project issues, such as performance, cost, and schedule.

Control and safety systems for TRIGA irradiation facilities C5 and C9

International Nuclear Information System (INIS)

Talpalariu Cornel Talpalariu Jeni Crucean Mircea Matei Corina

2008-01-01

Full text: The Institute for Nuclear Research conducted research for designing and manufacturing of microprocessor equipment for some irradiation facilities operating by the TRIGA reactor. This equipment has accumulated a wide operating time allowing the conclusions referring to reliability, ergonomics, and design of the operating facilities. Based upon these studies a new program was initiated for the design and manufacturing of a modern equipment with improved reliability and flexibility performances. The system provides the user with a multitude of options, numerical and analog interfaces, keyboard and high reliability local display. The main functional components of the system are: - 8 PID full options regulating loops; - 8 safety analog channels having 4 preset trips; - watch dog restart and fault tolerant facilities; - 8 high precision analog with an input of 0 - 15 mV from thermocouple; - 8 computer controlled power supplies of 220 V, 1 kWA; - alphanumeric display and keyboard; - fault tolerant analog scanner. A real improvement of the system is the future remote control computer, a PC AT Pentium working like a system controller, real time data acquisition, and operator's adviser. This new facility allows the operator to set the trips or to control remotely all the power supply and step-by-step positioner of irradiation device. Software design for acquisition and data processing provides modern techniques for operator interfacing, representation recording and protection of test results. Software implementation keeps a special organization supported by a real time executive that is the best method to achieve the performance required. Following this objective, the software structure consists of: 1. Tasks as follows: - testing parameters setup; - data processing routines; - engineering and electrical conversion; - numerical / graphical data representation; - test results recording routines and data base management. 2. Drivers as follows: - A/I and D

Feasibility for the setting up of a multipurpose food irradiation facility in Senegal

International Nuclear Information System (INIS)

Diop, Y.; Marchioni, E.; Hasswlmann, C.; Ba, D.; Kuntz, F.

2002-01-01

The setting up of a cobalt-60 (activity 500 kCi) irradiation facility in the highest populated region of Senegal (Dakar district) to treat a wide range of foodstuffs for local consumption (millet/sorghum, rice, maize, cowpeas, potatoes, onions, mangoes, citrus fruits and dried fishes) is considered as profitable for a private investor or a Senegalese food producer (or trader), provided the tonnage of foodstuffs treated is adequate, more than 22,000 t·kGy, i.e. a total tonnage above 77,000 t, taking into account the irradiation doses used for the various foodstuffs. (author)

Irradiation test of the HCAL Forward and Endcap upgrade electronics at the CHARM facility at CERN

CERN Document Server

AUTHOR|(CDS)2068434; Costanza, Francesco; Karakaya, Tugba; Sahin, Mehmet Ozgur; Lincoln, Don; Strobbe, Nadja; Kaminskiy, Alexander; Tlisov, Danila; Wang, Yanchu; Hirschauer, James Francis

2016-01-01

In the period October 21 – 28, 2015, the CMS HCAL group did a radiation tolerance study for the Phase I Upgrade HF, HE and HB front end electronics. The test was conducted at the CERN CHARM facility, which is a mixed field radiation facility. No permanent damages were observed. Effects observed during the irradiation are presented.

The JANNUS Saclay facility: A new platform for materials irradiation, implantation and ion beam analysis

Energy Technology Data Exchange (ETDEWEB)

Pellegrino, S., E-mail: stephanie.pellegrino@cea.fr [CEA, INSTN, UEPTN, Laboratoire JANNUS, F-91191 Gif-sur-Yvette (France); Trocellier, P.; Miro, S.; Serruys, Y.; Bordas, E.; Martin, H. [CEA, DEN, Service de Recherches de Metallurgie Physique, Laboratoire JANNUS, F-91191 Gif-sur-Yvette (France); Chaabane, N.; Vaubaillon, S. [CEA, INSTN, UEPTN, Laboratoire JANNUS, F-91191 Gif-sur-Yvette (France); Gallien, J.P.; Beck, L. [CEA, DEN, Service de Recherches de Metallurgie Physique, Laboratoire JANNUS, F-91191 Gif-sur-Yvette (France)

2012-02-15

The third accelerator of the multi-ion irradiation platform JANNUS (Joint Accelerators for Nanosciences and NUclear Simulation), a 6SDH-2 Pelletron from National Electrostatic Corporation, Middleton was installed at Saclay in October 2009. The first triple beam irradiation combining Fe, He and H ion beams has been performed in March 2010. In the first part of this paper, we give a technical description of the triple beam facility, its performances and experimental capabilities. Typically, damage dose up to 100 dpa can be reached in 10 h irradiation with heavy ion beams, with or without simultaneous bombardment by protons, helium-4 ions or any other heavy ion beam. In the second part of this paper, we illustrate some IBA results obtained after irradiation and implantation experiments.

Use of the SPIRAL 2 facility for material irradiations with 14 MeV energy neutrons

International Nuclear Information System (INIS)

Mosnier, A.; Ridikas, D.; Ledoux, X.; Pellemoine, F.; Anne, R.; Huguet, Y.; Lipa, M.; Magaud, P.; Marbach, G.; Saint-Laurent, M.G.; Villari, A.C.C.

2005-01-01

The primary goal of an irradiation facility for fusion applications will be to generate a material irradiation database for the design, construction, licensing and safe operation of a fusion demonstration power station (e.g., DEMO). This will be achieved through testing and qualifying material performance under neutron irradiation that simulates service up to the full lifetime anticipated in the power plant. Preliminary investigations of 14 MeV neutron effects on different kinds of fusion material could be assessed by the SPIRAL 2 Project at GANIL (Caen, France), aiming at rare isotope beams production for nuclear physics research with first beams expected by 2009. In SPIRAL 2, a deuteron beam of 5 mA and 40 MeV interacts with a rotating carbon disk producing high-energy neutrons (in the range between 1 and 40 MeV) via C (d, xn) reactions. Then, the facility could be used for 3-4 months y -1 for material irradiation purposes. This would correspond to damage rates in the order of 1-2 dpa y -1 (in Fe) in a volume of ∼10 cm 3 . Therefore, the use of miniaturized specimens will be essential in order to effectively utilize the available irradiation volume in SPIRAL 2. Sample package irradiation temperature would be in the range of 250-1000 deg. C. The irradiation level of 1-2 dpa y -1 with 14 MeV neutrons (average energy) may be interesting for micro-structural and metallurgical investigations (e.g., mini-traction, small punch tests, etc.) and possibly for the understanding of specimen size/geometric effects of critical material properties. Due to the small test cell volume, sample in situ experiments are not foreseen. However, sample packages would be, if required, available each month after transfer in a special hot cell on-site

36 CFR 1150.2 - Applicability: Buildings and facilities subject to guidelines and standards.

Science.gov (United States)

2010-07-01

... facilities subject to guidelines and standards. 1150.2 Section 1150.2 Parks, Forests, and Public Property... General Information § 1150.2 Applicability: Buildings and facilities subject to guidelines and standards... provided in paragraph (c) of this section, the standards issued under the Architectural Barriers Act of...

Global trends of acceptance and trade in irradiated foods

Energy Technology Data Exchange (ETDEWEB)

Matin, M A [Food and Environmental Protection Section, Joint FAO/IAEA Division of Nuclear Techniques in Food and Agriculture, International Atomic Energy Agency, Vienna (Austria)

2001-05-01

Issues as relevant to wide scale application of food irradiation are presented in this paper to provide current status of the technology. Global development on key issues such as public acceptance, public health improvement, safety and wholesomeness, regulatory aspects, potential application of the technology to ease quarantine problems in the trade of food and agricultural commodities as a viable alternative to fumigation with methyl bromide have been presented. Irradiation ensures the hygienic quality of food and extends shelf-life. Many international organizations and respected regional/national bodies agree on the merits of the technique and valuable contribution that the process can offer to safeguard the food supply worldwide. Codex General Standard for irradiated food and the associated Code of Practice for operation of the irradiation facilities used for the treatment of foods adopted in 1983 forms the regulatory basis for commercial utilization of the processing technology. More than 40 countries of the world have Standards/Regulations to process one or more food products by the irradiation process. Efforts are underway to harmonise national regulations on food irradiation to remove obstacles for international trade of irradiated products. There is a rapid development on commercial application of food irradiation in the USA and elsewhere in the past few months. There are already several existing commercial irradiators available for treating food in the USA and many more are planned to be built. Such commercial food irradiation facilities are also in different stage of development in Brazil, India, Mexico, Thailand, People's Republic of China, Republic of Korea. Roles of irradiation ensuring food safety, contributing food security and facilitating trade are more and more recognized in developed and developing countries alike. (author)

Global trends of acceptance and trade in irradiated foods

International Nuclear Information System (INIS)

Matin, M.A.

2001-01-01

Issues as relevant to wide scale application of food irradiation are presented in this paper to provide current status of the technology. Global development on key issues such as public acceptance, public health improvement, safety and wholesomeness, regulatory aspects, potential application of the technology to ease quarantine problems in the trade of food and agricultural commodities as a viable alternative to fumigation with methyl bromide have been presented. Irradiation ensures the hygienic quality of food and extends shelf-life. Many international organizations and respected regional/national bodies agree on the merits of the technique and valuable contribution that the process can offer to safeguard the food supply worldwide. Codex General Standard for irradiated food and the associated Code of Practice for operation of the irradiation facilities used for the treatment of foods adopted in 1983 forms the regulatory basis for commercial utilization of the processing technology. More than 40 countries of the world have Standards/Regulations to process one or more food products by the irradiation process. Efforts are underway to harmonise national regulations on food irradiation to remove obstacles for international trade of irradiated products. There is a rapid development on commercial application of food irradiation in the USA and elsewhere in the past few months. There are already several existing commercial irradiators available for treating food in the USA and many more are planned to be built. Such commercial food irradiation facilities are also in different stage of development in Brazil, India, Mexico, Thailand, People's Republic of China, Republic of Korea. Roles of irradiation ensuring food safety, contributing food security and facilitating trade are more and more recognized in developed and developing countries alike. (author)

Improvement of plant parameters of the robo gamma irradiation facility due to design modification

International Nuclear Information System (INIS)

Kovacs, A.; Moussa, A.; Othman, I.; Del Valle Odar, C.; Seminario, A.; Linares, M.; Huamanlazo, P.; Aymar, J.; Chu, R.

1998-01-01

Two industrial scale, 'ROBO' type 60 Co gamma irradiation facilities have recently been put into operation in Syria and Peru, and the dosimetry commissioning of both plants have been carried out to determine dose distribution within products and to calculate plant parameters such as efficiency, dose uniformity ratio and throughput. There are some design modifications between the two plants in connection with the location of the carriers with respect to the source plaque and also to each other. The effect of these construction modifications on the plant parameters is discussed in the analysis of the dose distribution data measured in the carriers with depth and height among the four irradiation rows on both sides of the source plaque. The plant parameters were also calculated for different product densities using the technical data of the facilities, and the calculated and measured results were compared to each other

IFMIF (International Fusion Materials Irradiation Facility) key element technology phase interim report

Energy Technology Data Exchange (ETDEWEB)

Nakamura, Hiroo; Ida, Mizuho; Sugimoto, Masayoshi; Takeuchi, Hiroshi; Yutani, Toshiaki (eds.) [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

2002-03-01

Activities of International Fusion Materials Irradiation Facility (IFMIF) have been performed under an IEA collaboration since 1995. IFMIF is an accelerator-based deuteron (D{sup +})-lithium (Li) neutron source designed to produce an intense neutron field (2 MW/m{sup 2}, 20 dpa/year for Fe) in a volume of 500 cm{sup 3} for testing candidate fusion materials. In 2000, a 3 year Key Element technology Phase (KEP) of IFMIF was started to reduce the key technology risk factors. This interim report summarizes the KEP activities until mid 2001 in the major project work-breakdown areas of accelerator, target, test facilities and design integration. (author)

Seismic analysis for shroud facility in-pile tube and saturated temperature capsules

International Nuclear Information System (INIS)

Iimura, Koichi; Yamaura, Takayuki; Ogawa, Mitsuhiro

2009-07-01

At Oarai Research and Development Center, Japan Atomic Energy Agency (JAEA), the plan of repairing and refurbishing Japan Materials Testing Reactor (JMTR) has progressed in order to restart JMTR operation in the fiscal 2011. As a part of effective use of JMTR, the neutron irradiation tests of LWR fuels and materials has been planned in order to study their soundness. By using Oarai Shroud Facility (OSF-1) and Fuel Irradiation Facility with the He-3 gas control system for power lamping test using Boiling Water Capsules (BOCA Irradiation Facility), the irradiation tests with power ramping will be carried out to study the soundness of fuel under LWR Transient condition. OSF-1 is the irradiation facility of shroud type that can insert and eject the capsule under reactor operation, and is composed of 'In-pile Tube', 'Cooling system' and 'Capsule exchange system'. BOCA Irradiation Facility is the facility which simulates irradiation environment of LWR, and is composed of 'Boiling water Capsule', 'Capsule control system' and 'Power control system by He-3'. By using Saturated temperature Capsules and the water environment control system, the material irradiation tests under the water chemistry condition of LWR will be carried out to clarify the mechanism of IASCC. In JMTR, these facilities are in service at the present. However, the detailed design for renewal or remodeling was carried out based on the new design condition in order to be correspondent to the irradiation test plan after restart JMTR operation. In this seismic analysis of the detailed design, each equipment classification and operating state were arranged with 'Japanese technical standards of the structure on nuclear facility for test research' and 'Technical guidelines for seismic design of nuclear power plants on current, and then, stress calculation and evaluation were carried out by FEM piping analysis code 'SAP' and structure analysis code 'ABAQUS'. About the stress of the seismic force, it was proven

Challenges in validating radiation sterilization with low energy electron irradiation

International Nuclear Information System (INIS)

Miller, A.; Helt-Hansen, J.

2011-01-01

Complete text of publication follows. Low energy electron irradiation (80-300 keV) is used increasingly for sterilization or decontamination in connection with isolators for aseptic filling lines in the pharmaceutical industry. It is not defined how validation for this process shall be carried out. A method can be derived from the medical device standard for radiation sterilization, ISO 11137, because the principles described in this standard can be applied to almost any industrial irradiation process. The validations elements are: Process definition, concerning specification of the dose required for the process and the maximum acceptable dose for the product. Installation qualification, concerning acceptance the irradiation facility. Operational qualification, concerning characterization of the facility. Performance qualification, concerning setting up the process. Process control, concerning routine monitoring. The limited penetration of the low energy electrons leads to problems with respect to executing these validation steps. This paper discusses these problems, and shows with examples how they can be solved.

Detection and measurement of neutron-irradiated gemstones

International Nuclear Information System (INIS)

Bunnak, S.; Jerachanchai, S.; Chinudomsub, K.; Saiyut, K.

1990-01-01

Color enhance gemstone, neutron-irradiated topaz, was analyzed by gamma spectrometry for examining characteristic and activity. Topaz was irradiated in the wet-tube facility of the Research Reactor TRR/1 which neutron fluence is 2.52x10 17 neutron per square centimeter. After 100 days of decay, topaz was sampling to the qualitative and quantitative analysis using multichannel analyzer of Nuclear Data Model ND65 and hyper pure germanium detector. Calculation and evaluation were done by microcomputer IBM/PC 640 KB RAM. The qualitative analysis showed that the neutron-irradiated topaz has 2 major isotopes, i.e., Ta-182 and Sc-46. Quantitative activity was compared with reference standard source Eu-152 (NBS) and the results were shown in the table 1. The Health Physics Division, OAEP, inspected on 6240.9 gm of the neutron-irradiated topaz using standard release limit 2 nCi/gm (74 Bq/gm). It was found that only 423.9 gm out of the total amount were over the standard release limit

A commercial gamma-ray irradiation plant in Japan

International Nuclear Information System (INIS)

Tomita, K.; Sugimoto, S.

1977-01-01

In 1973, a commercial gamma-ray irradiation plant was constructed in Takasaki, about 100 km north of Tokyo. The plant has been used for both production of irradiated commercial products and irradiation services. The irradiation services are being made available for sterilization of both medical appliances such as disposable medical syringes, catheters, surgical sutures, and sterilization of feed stuffs for animals. Treatment of plastic materials and colouring of both crystals and glass wares are also undertaken. This facility can accommodate 600 kCi of 60 Co and has a monthly treating capacity of 12,000 packages ( a standard carton of 340 mm x 400 mm x 500 mm) at an irradiation dose of 1 Mrad/hr. A receiving port for packages is on the second floor and the outlet of the irradiated packages on the first floor, with three lines of connecting loop conveyors between them, and the irradiation compartment in the center section. The space arrangement of the facility is well designed and gravity can be utilized for the transportation of the packages. Polymer impregnated coral is put on the market for ornamental building material on an order contract basis. (author)

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

International Nuclear Information System (INIS)

Mizzan, E.; Chenier, R.J.

1979-10-01

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

Status on the construction of the fuel irradiation test facility

International Nuclear Information System (INIS)

Park, Kook Nam; Sim, Bong Shick; Lee, Chung Young; Yoo, Seong Yeon

2005-01-01

As a facility to examine general performance of nuclear fuel under irradiation condition in HANARO, Fuel Test Loop(FTL) has been developed which can accommodate 3 fuel pins at the core irradiation hole(IR1 hole) taking consideration user's test requirement. 3-Pin FTL consists of In-Pile Test Section (IPS) and Out-of- Pile System (OPS). Test condition in IPS such as pressure, temperature and the water quality, can be controlled by OPS. 3-Pin FTL Conceptual design was set up in 2001 and had completed detail design including a design requirement and basic Piping and Instrument Diagram (P and ID) in 2004. The safety analysis report was prepared and submitted in early 2005 to the regulatory body(KINS) for review and approval of FTL. In 2005, the development team is going to purchase and manufacture hardware and make a contract for construction work. In 2006, the development team is going to install an FTL system performance test shall be done as a part of commissioning. After a 3-Pin FTL development which is expected to be finished by the 2007, FTL will be used for the irradiation test of the new PWR-type fuel and the usage of HANARO will be enhanced

Standard Practice for Measurement of Mechanical Properties During Charged-Particle Irradiation

CERN Document Server

American Society for Testing and Materials. Philadelphia

1996-01-01

1.1 This practice covers the performance of mechanical tests on materials being irradiated with charged particles. These tests are designed to simulate or provide understanding of, or both, the mechanical behavior of materials during exposure to neutron irradiation. Practices are described that govern the test material, the particle beam, the experimental technique, and the damage calculations. Reference should be made to other ASTM standards, especially Practice E 521. Procedures are described that are applicable to creep and creep rupture tests made in tension and torsion test modes. 1.2 The word simulation is used here in a broad sense to imply an approximation of the relevant neutron irradiation environment. The degree of conformity can range from poor to nearly exact. The intent is to produce a correspondence between one or more aspects of the neutron and charged particle irradiations such that fundamental relationships are established between irradiation or material parameters and the material respons...

Materials irradiation research in neutron science

Energy Technology Data Exchange (ETDEWEB)

Noda, Kenji; Oyama, Yukio [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

1997-11-01

Materials irradiation researches are planned in Neutron Science Research Program. A materials irradiation facility has been conceived as one of facilities in the concept of Neutron Science Research Center at JAERI. The neutron irradiation field of the facility is characterized by high flux of spallation neutrons with very wide energy range up to several hundred MeV, good accessibility to the irradiation field, good controllability of irradiation conditions, etc. Extensive use of such a materials irradiation facility is expected for fundamental materials irradiation researches and R and D of nuclear energy systems such as accelerator-driven incineration plant for long-lifetime nuclear waste. In this paper, outline concept of the materials irradiation facility, characteristics of the irradiation field, preliminary technical evaluation of target to generate spallation neutrons, and materials researches expected for Neutron Science Research program are described. (author)

The RADEX facility as a tool for studies of radiation damage under proton and spallation neutron irradiation

Energy Technology Data Exchange (ETDEWEB)

Koptelov, E.A.; Lebedev, S.G.; Matveev, V.A.; Sobolevsky, N.M. [Institute for Nuclear Research of Russian Academy of Sciences, Moscow (Russian Federation); Strebkov, Yu.S.; Subbotin, A.V. [Research and Development Institute of Power Engineering, Moscow (Russian Federation)

2001-03-01

We present results of numerical modeling for processes of primary protons and spallation neutrons interactions with structural materials at the RADiation EXperiment facility of the Neutron Complex. The installation has a vertical irradiation channel inside the beam stop for horizontally incident protons with energies up to 600 MeV of the Moscow Meson Factory of the INR (Institute for Nuclear Research) RAS (Russian Academy of Science). The calculations are based on a set of computer codes SHIELD and RADDAM, which were developed in the INR RAS and give data on point defect generation by irradiation, rate of accumulation of H and He atoms produced in nuclear reactions, energetic spectra of primary knocked-off atoms in collision displacements, temperature of samples under irradiation. Different positions of the channel, which are available by rotation of a target relatively the vertical axis for angles 0, 60, 120 and 180 degrees to the proton beam direction, are considered. Changes of irradiation damage parameters due to various inputs of primary protons and spallation neutrons at different target orientations are demonstrated. It is shown also that the spallation neutron facility RADEX may provide with perspective experimental possibilities for modeling of irradiation conditions for fusion reactors ITER and DEMO. (author)

International fusion materials irradiation facility and neutronic calculations for its test modules

International Nuclear Information System (INIS)

Sokcic-Kostic, M.

1997-01-01

The International Fusion Material Irradiation Facility (IFMIF) is a projected high intensity neutron source for material testing. Neutron transport calculations for the IFMIF project are performed for variety of here explained reasons. The results of MCNP neutronic calculations for IFMIF test modules with NaK and He cooled high flux test cells are presented in this paper. (author). 3 refs., 2 figs., 3 tabs

Performance studies under high irradiation and ageing properties of resistive bulk Micromegas chambers at the new CERN Gamma Irradiation Facility

International Nuclear Information System (INIS)

Sidiropoulou, O.; Gonzalez, B. Alvarez; Bianco, M.; Farina, E.M.; Iengo, P.; Longo, L.; Pfeiffer, D.; Wotschack, J.

2017-01-01

Resistive bulk Micromegas chambers, produced at CERN, have been installed at the new CERN Gamma Irradiation Facility (GIF++) in order to study the effects of ageing and to evaluate the detector behaviour under high irradiation. The chambers have an active area of 10×10 cm 2 , strip pitch of 400 μm and an amplification gap of 128 μm. We present the detector performance as a function of the background rate of up to 20 MHz/cm 2 . - Highlights: • Small-size resistive bulk Micromegas detectors have been exposed to the new GIF++. • 9 months irradiation to γ up to 20 Mhz/cm 2 . 0.09 C/cm 2 collected integrated charge. • Νo degradation of the detector performance was observed. • Muon tracks successfully reconstructed up to 68 kHz/cm 2 gamma background. • Higher background rates will be studied in the coming months.

Codes, standards, and requirements for DOE facilities: natural phenomena design

International Nuclear Information System (INIS)

Webb, A.B.

1985-01-01

The basic requirements for codes, standards, and requirements are found in DOE Orders 5480.1A, 5480.4, and 6430.1. The type of DOE facility to be built and the hazards which it presents will determine the criteria to be applied for natural phenomena design. Mandatory criteria are established in the DOE orders for certain designs but more often recommended guidance is given. National codes and standards form a great body of experience from which the project engineer may draw. Examples of three kinds of facilities and the applicable codes and standards are discussed. The safety program planning approach to project management used at Westinghouse Hanford is outlined. 5 figures, 2 tables

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

Science.gov (United States)

2010-04-13

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

Nuclear data for the production of radioisotopes in fusion materials irradiation facility

International Nuclear Information System (INIS)

Cheng, E.T.; Schenter, R.E.; Mann, F.M.; Ikeda, Y.

1991-01-01

The fusion materials irradiation facility (FMIF) is a neutron source generator that will produce a high-intensity 14-MeV neutron field for testing candidate fusion materials under reactor irradiation conditions. The construction of such a facility is one of the very important development stages toward realization of fusion energy as a practical energy source for electricity production. As a result of the high-intensity neutron field, 10 MW/m 2 or more equivalent neutron wall loading, and the relatively high-energy (10- to 20-MeV) neutrons, the FMIF, as future fusion reactors, also bears the potential capability of producing a significant quantity of radioisotopes. A study is being conducted to identify the potential capability of the FMIF to produce radioisotopes for medical and industrial applications. Two types of radioisotopes are involved: one is already available; the second might not be readily available using conventional production methods. For those radioisotopes that are not readily available, the FMIF could develop significant benefits for future generations as a result of the availability of such radioisotopes for medical or industrial applications. The current production of radioisotopes could help finance the operation of the FMIF for irradiating the candidate fusion materials; thus this concept is attractive. In any case, nuclear data are needed for calculating the neutron flux and spectrum in the FMIF and the potential production rates of these isotopes. In this paper, the authors report the result of a preliminary investigation on the production of 99 Mo, the parent radioisotope for 99m Tc

Blood irradiation

International Nuclear Information System (INIS)

Chandy, Mammen

1998-01-01

Viable lymphocytes are present in blood and cellular blood components used for transfusion. If the patient who receives a blood transfusion is immunocompetent these lymphocytes are destroyed immediately. However if the patient is immunodefficient or immunosuppressed the transfused lymphocytes survive, recognize the recipient as foreign and react producing a devastating and most often fatal syndrome of transfusion graft versus host disease [T-GVHD]. Even immunocompetent individuals can develop T-GVHD if the donor is a first degree relative since like the Trojan horse the transfused lymphocytes escape detection by the recipient's immune system, multiply and attack recipient tissues. T-GVHD can be prevented by irradiating the blood and different centers use doses ranging from 1.5 to 4.5 Gy. All transfusions where the donor is a first degree relative and transfusions to neonates, immunosuppressed patients and bone marrow transplant recipients need to be irradiated. Commercial irradiators specifically designed for irradiation of blood and cellular blood components are available: however they are expensive. India needs to have blood irradiation facilities available in all large tertiary institutions where immunosuppressed patients are treated. The Atomic Energy Commission of India needs to develop a blood irradiator which meets international standards for use in tertiary medical institutions in the country. (author)

Planning of gamma-fields: forming and checking dose-rate homogeneity in irradiation facilities

International Nuclear Information System (INIS)

Stenger, V.; Foldiak, G.; Horvath, Zs.; Naszodi, L.

1975-01-01

The optimal geometry of the sources of an 80000-Ci 60 Co irradiation facility was calculated. The array of the sources is suitable for fundamental research and pilot-plant radiosterilization simultaneously. A method was developed to compensate the inhomogeneity of the dose-rate field: it is no worse than that of the continuous large-scale facilities. In five years the activity of the sources decreased by about half; therefore, this recharge became inevitable. Experience proved that with the new source geometry optimalized by calculations a dose-rate of 1.2 +-10% became available with the packages. (author)

Standards for psychological assessment of nuclear facility personnel. Technical report

International Nuclear Information System (INIS)

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

1981-07-01

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

Development of an irradiation system for a small size continuous run multipurpose gamma irradiator

International Nuclear Information System (INIS)

Calvo, W.A.P.; Rela, P.R.; Napolitano, C.M.; Kodama, Y.; Omi, N.M.; Costa, F.E. da; Andradee Silva, L.G. de

2009-01-01

The Radiation Technology Center from IPEN-CNEN/SP, Brazil, developed a revolutionary design and national technology, a small-sized continuous run and multipurpose industrial gamma irradiator, to be used as a demonstration facility for manufacturers and contract service companies, which need economical and logistical in-house irradiation system alternatives. Also, to be useful for supporting the local scientific community on development of products and process using gamma radiation, assisting the traditional and potential users on process validation, training and qualification of operators and radioprotection officers. The developed technology for this facility consists of a continuous tote box transport system, comprising a single concrete vault, where the automated transport system of products inside and outside of the irradiator utilizes a rotating door, integrated with the shielding, avoiding the traditional maze configuration. Covering 76 m 2 of floor area, the irradiator design is a product overlap sources and the maximum capacity of cobalt-60 wet sources is 37 PBq. The performed qualification program of this multipurpose irradiator was based on AAMI/ISO 11137 standard, which recommends the inclusion of the following elements: installation and process qualification. The initial load of the multipurpose irradiator was 3.4 PBq with 13 cobalt-60 sources model C-188, supplied by MDS Nordion - Canada. For irradiator dose optimization, the source distribution was done using the software Cadgamma developed by IPEN-CNEN/SP. The polymethylmetacrylate (PMMA) dosimeter system, certified by the International Dose Assurance Service (IDAS) of the International Atomic Energy Agency (IAEA) was used for irradiator dose mapping. The economic analysis, performance concerning with dose uniformity and cobalt-60 utilization efficiency were calculated and compared with other commercial gamma irradiators available on the market. (authors)

Dose mapping simulation using the MCNP code for the Syrian gamma irradiation facility and benchmarking

International Nuclear Information System (INIS)

Khattab, K.; Boush, M.; Alkassiri, H.

2013-01-01

Highlights: • The MCNP4C was used to calculate the gamma ray dose rate spatial distribution in for the SGIF. • Measurement of the gamma ray dose rate spatial distribution using the Chlorobenzene dosimeter was conducted as well. • Good agreements were noticed between the calculated and measured results. • The maximum relative differences were less than 7%, 4% and 4% in the x, y and z directions respectively. - Abstract: A three dimensional model for the Syrian gamma irradiation facility (SGIF) is developed in this paper to calculate the gamma ray dose rate spatial distribution in the irradiation room at the 60 Co source board using the MCNP-4C code. Measurement of the gamma ray dose rate spatial distribution using the Chlorobenzene dosimeter is conducted as well to compare the calculated and measured results. Good agreements are noticed between the calculated and measured results with maximum relative differences less than 7%, 4% and 4% in the x, y and z directions respectively. This agreement indicates that the established model is an accurate representation of the SGIF and can be used in the future to make the calculation design for a new irradiation facility

IFMIF (International Fusion Materials Irradiation Facility) conceptual design activity reduced cost report

International Nuclear Information System (INIS)

2000-02-01

This report describes the results of a preliminary reevaluation of the design and cost of the International Fusion Materials Irradiation Facility (IFMIF) Project in response to the request from the 28th FPCC meeting in January 1999. Two major ideas have been considered: 1) reduction of the total construction cost through elimination of the previously planned facility upgrade and 2) a facility deployment in 3 stages with capabilities for limited experiments in the first stage. As a result, the size and complexity of the facility could be significantly reduced, leading to substantial cost savings. In addition to these two ideas, this study also included a critical review of the original CDA specification with the objective of elimination of nonessential items. For example, the number of lithium targets was reduced from two to one. As a result of these changes in addition to the elimination of the upgrade, the total cost estimate was very substantially reduced from 797.2 MICF to 487.8 MICF, where 1 MICF = 1 Million of the IFMIF Conversion Units (approximately $1M US January, 1996). (author)

International standardization of instruments for neutron irradiation tests

International Nuclear Information System (INIS)

Tanimoto, Masataka; Shibata, Akira; Nakamura, Jinichi; Tsuchiya, Kunihiko; Cho, M.; Lee, C.; Park, S.; Choo, K.

2012-01-01

The JMTR in JAEA and HANARO in KAERI are the foremost testing/research reactors in the world and these are expected to contribute to many nuclear fields. As a part of instrument development in irradiation field, information exchange of instruments started from 2010 under the cooperation agreements between KAERI and JAEA. The instruments developed in JMTR and HANARO are introduced and cooperation experiments as future plan are discussed for international standardization. (author)

Whole-Pin Furnace system: An experimental facility for studying irradiated fuel pin behavior under potential reactor accident conditions

International Nuclear Information System (INIS)

Liu, Y.Y.; Tsai, H.C.; Donahue, D.A.; Pushis, D.O.; Savoie, F.E.; Holland, J.W.; Wright, A.E.; August, C.; Bailey, J.L.; Patterson, D.R.

1990-05-01

The whole-pin furnace system is a new in-cell experimental facility constructed to investigate how irradiated fuel pins may fail under potential reactor accident conditions. Extensive checkouts have demonstrated excellent performance in remote operation, temperature control, pin breach detection, and fission gas handling. The system is currently being used in testing of EBIR-II-irradiated Integral Fast Reactor (IFR) metal fuel pins; future testing will include EBR-II-irradiated mixed-oxide fuel pins. 7 refs., 4 figs

IFMIF : International Fusion Materials Irradiation Facility Conceptual Design Activity: Final report

International Nuclear Information System (INIS)

Martone, M.

1997-01-01

This report documents the results of the Conceptual Design Activity (CDA) on the International Fusion Materials Irradiation Facility (IFMIF), conducted during 1995 and 1996. The activity is under the auspices of the International Energy Agency (IEA) Implementing Agreement for a Programme of Research and Development on Fusion Materials. An IEA Fusion Materials Executive Subcommittee was charged with overseeing the IFMIF-CDA work. Participants in the CDA are the European Union, Japan, and the United States, with the Russian Federation as an associate member

IFMIF : International Fusion Materials Irradiation Facility Conceptual Design Activity: Final report

Energy Technology Data Exchange (ETDEWEB)

Martone, M [ENEA, Centro Ricerche Frascati, Rome (Italy)

1997-01-01

This report documents the results of the Conceptual Design Activity (CDA) on the International Fusion Materials Irradiation Facility (IFMIF), conducted during 1995 and 1996. The activity is under the auspices of the International Energy Agency (IEA) Implementing Agreement for a Programme of Research and Development on Fusion Materials. An IEA Fusion Materials Executive Subcommittee was charged with overseeing the IFMIF-CDA work. Participants in the CDA are the European Union, Japan, and the United States, with the Russian Federation as an associate member.

Design of a high-flux test assembly for the Fusion Materials Irradiation Test Facility

International Nuclear Information System (INIS)

Opperman, E.K.; Vogel, M.A.

1982-01-01

The Fusion Material Test Facility (FMIT) will provide a high flux fusion-like neutron environment in which a variety of structural and non-structural materials irradiations can be conducted. The FMIT experiments, called test assemblies, that are subjected to the highest neutron flux magnitudes and associated heating rates will require forced convection liquid metal cooling systems to remove the neutron deposited power and maintain test specimens at uniform temperatures. A brief description of the FMIT facility and experimental areas is given with emphasis on the design, capabilities and handling of the high flux test assembly

RF structure design of the China Material Irradiation Facility RFQ

Science.gov (United States)

Li, Chenxing; He, Yuan; Xu, Xianbo; Zhang, Zhouli; Wang, Fengfeng; Dou, Weiping; Wang, Zhijun; Wang, Tieshan

2017-10-01

The radio frequency structure design of the radio frequency quadrupole (RFQ) for the front end of China Material Irradiation Facility (CMIF), which is an accelerator based neutron irradiation facility for fusion reactor material qualification, has been completed. The RFQ is specified to accelerate 10 mA continuous deuteron beams from the energies of 20 keV/u to 1.5 MeV/u within the vane length of 5250 mm. The working frequency of the RFQ is selected to 162.5 MHz and the inter-vane voltage is set to 65 kV. Four-vane cavity type is selected and the cavity structure is designed drawing on the experience of China Initiative Accelerator Driven System (CIADS) Injector II RFQ. In order to reduce the azimuthal asymmetry of the field caused from errors in fabrication and assembly, a frequency separation between the working mode and its nearest dipole mode is reached to 17.66 MHz by utilizing 20 pairs of π-mode stabilizing loops (PISLs) distributed along the longitudinal direction with equal intervals. For the purpose of tuning, 100 slug tuners were introduced to compensate the errors caused by machining and assembly. In order to obtain a homogeneous electrical field distribution along cavity, vane cutbacks are introduced and output endplate is modified. Multi-physics study of the cavity with radio frequency power and water cooling is performed to obtain the water temperature tuning coefficients. Through comparing to the worldwide CW RFQs, it is indicated that the power density of the designed structure is moderate for operation under continuous wave (CW) mode.

Progress in developing the concept for the irradiation research facility

International Nuclear Information System (INIS)

Lee, A.G.; Bishop, W.E.; Gillespie, G.E.; Zeng, Y.

1996-04-01

At the 16th annual Canadian Nuclear Society conference, AECL presented the case for replacing the NRU reactor with an Irradiation Research Facility (IRF) to test CANDU fuels and materials and to perform advanced materials research using neutrons. AECL developed a cost estimate of $500 million for the reference IRF concept, and estimated that it would require 87 months to complete. AECL has initiated a pre-project program to develop the IRF concept and to minimize uncertainties related to feasibility and licensability, and to examine options for reducing the overall project cost before project implementation begins. (author) 10 refs., 2 figs

Food Irradiation Technology in the Philippines

International Nuclear Information System (INIS)

De Guzman, Zenaida M.

2015-01-01

The applications of ionizing radiation for the preservation of food and agricultural products by delaying ripening, destruction of insect pests and pathogenic microorganisms have shown great promise in the country. For more than 30 years, the Philippine Nuclear Research Institute (PNRI) in collaboration with other government and private sectors, has undertaken research and development studies and pilot and semi-commercial scale irradiation of foods. Some of the foods found to be benefit from the use of irradiation technology are mangoes and papayas for disinfestations and delay ripening; onions and garlic for inhibition of sprouting; spices and dehydrated products for reduction of microbial growth and rice and corn for insect and shelf-life extension. Two regulations approved by the Department of Health and the Bureau of Plant Industry are in place creating an enabling environment for food safety and trade of irradiated food. The conduct of awareness program in various parts of the country provided knowledge and information about the food irradiation technology. The Institute has been part of the international projects (IAEA and USDA) on the use of irradiation for sanity and phytosanitary treatment of food. The projects not only established the potential benefits of food irradiation for socio-economic development of the country but also built considerable capacity to properly treat foods. Some of the recent developments in the area of food irradiation include publication of Philippine National Standard (PNS) on Food Irradiation: Code of Good Irradiation Practices which will serve as a guide for stakeholders to irradiate food, a newly-established Electron Beam Facility to demonstrate the potential use of EB and a feasibility study of putting-up a commercial irradiation facility in the country. (author)

Radiation safety training for industrial irradiators: What are we trying to accomplish?

International Nuclear Information System (INIS)

Smith, M.A.

1998-01-01

Radiation safety training at an industrial irradiator facility takes a different approach than the traditional methods and topics used at other facilities. Where the more routine industrial radiation users focus on standard training topics of contamination control, area surveys, and the traditional dogma of time, distance, and shielding, radiation safety in an industrial irradiation facility must be centered on preventing accidents. Because the primary methods for accomplishing that goal are engineering approaches such as safety system interlocks, training provided to facility personnel should address system operation and emergency actions. This presents challenges in delivering radiation safety training to an audience of varied educational and technical background where little to no commercially available training material specific to this type of operation exists

Comparison Between In-Beam and Offline Positron Emission Tomography Imaging of Proton and Carbon Ion Therapeutic Irradiation at Synchrotron- and Cyclotron-Based Facilities

International Nuclear Information System (INIS)

Parodi, Katia; Bortfeld, Thomas; Haberer, Thomas

2008-01-01

Purpose: The benefit of using dedicated in-beam positron emission tomography (PET) detectors in the treatment room instead of commercial tomographs nearby is an open question. This work quantitatively compares the measurable signal for in-beam and offline PET imaging, taking into account realistic acquisition strategies at different ion beam facilities. Both scenarios of pulsed and continuous irradiation from synchrotron and cyclotron accelerators are considered, because of their widespread use in most carbon ion and proton therapy centers. Methods and Materials: A mathematical framework is introduced to compare the time-dependent amount and spatial distribution of decays from irradiation-induced isotope production. The latter is calculated with Monte Carlo techniques for real proton treatments of head-and-neck and paraspinal tumors. Extrapolation to carbon ion irradiation is based on results of previous phantom experiments. Biologic clearance is modeled taking into account available data from previous animal and clinical studies. Results: Ratios between the amount of physical decays available for in-beam and offline detection range from 40% to 60% for cyclotron-based facilities, to 65% to 110% (carbon ions) and 94% to 166% (protons) at synchrotron-based facilities, and increase when including biologic clearance. Spatial distributions of decays during irradiation exhibit better correlation with the dose delivery and reduced influence of biologic processes. Conclusions: In-beam imaging can be advantageous for synchrotron-based facilities, provided that efficient PET systems enabling detection of isotope decays during beam extraction are implemented. For very short (<2 min) irradiation times at cyclotron-based facilities, a few minutes of acquisition time after the end of irradiation are needed for counting statistics, thus affecting patient throughput

Cost-benefit analysis of irradiation of vegetables and fruits at the Shanghai irradiation centre

International Nuclear Information System (INIS)

Xu Zhicheng; Sha Zhenyuan

1993-01-01

Differences between the developing and the developed countries in development and application of food irradiation are discussed, including the objectives of irradiation, scale, and the operation and control of facilities. These represent the chief problems of development of food irradiation in the developing countries. A proposal concerning the economic benefit of a gamma irradiation facility is discussed. In the light of many years' operating experience at the Shanghai Irradiation Centre, the operation cost per hour and coefficient of economic benefit are presented. These data can be used to estimate the economic benefit of gamma irradiated products at any time, and are useful for directing the daily operation of gamma irradiation facilities. From examples of cost-benefit analysis of irradiated garlic and apples it is shown that to improve the benefit of gamma irradiation facilities the annual hours of operation must be increased, so as to reduce the cost of operation. Food irradiated with a low dose provides more economic benefit than other irradiated products; the coefficients of economic benefit will increase as the irradiated processing throughput increases. Practical examples are given relating to garlic and apples, showing the economic benefit to wholesalers and retailers. (author). 4 refs, 3 figs, 7 tabs

Code of practice for the design and safe operation of non-medical irradiation facilities (1988)

International Nuclear Information System (INIS)

1988-01-01

This Code establishes requirements for the design and operation of irradiation facilities which use X-rays, electrons or gamma radiation for non-medical purposes such as the sterilisation of therapeutic goods. These requirements aim to ensure that exposure of workers and members of the public to ionizing and non-ionizing radiation as well as to noxious gases and radioactive contamination of the environment and facilities are controlled through the design of engineering safety features, approved administrative controls and appropriate radiation monitoring [fr

IFMIF : International Fusion Materials Irradiation Facility Conceptual Design Activity: Executive summary

International Nuclear Information System (INIS)

1997-01-01

This report is a summary of the results of the Conceptual Design Activity (CDA) on the International Fusion Materials Irradiation Facility (IFMIF), conducted during 1995 and 1996. The activity is under the auspices of the International Energy Agency (IEA) Implementing Agreement for a Programme of Research and Development on Fusion Materials. An IEA Fusion Materials Executive Subcommittee was charged with overseeing the IFMIF-CDA work. Participants in the CDA are the European Union, Japan, and the United States, with the Russian Federation as an associate member

IFMIF : International Fusion Materials Irradiation Facility Conceptual Design Activity: Executive summary

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-01-01

This report is a summary of the results of the Conceptual Design Activity (CDA) on the International Fusion Materials Irradiation Facility (IFMIF), conducted during 1995 and 1996. The activity is under the auspices of the International Energy Agency (IEA) Implementing Agreement for a Programme of Research and Development on Fusion Materials. An IEA Fusion Materials Executive Subcommittee was charged with overseeing the IFMIF-CDA work. Participants in the CDA are the European Union, Japan, and the United States, with the Russian Federation as an associate member.

Dosimetry control for radiation processing - basic requirements and standards

International Nuclear Information System (INIS)

Ivanova, M.; Tsrunchev, Ts.

2004-01-01

A brief review of the basic international codes and standards for dosimetry control for radiation processing (high doses dosimetry), setting up a dosimetry control for radiation processing and metrology control of the dosimetry system is made. The present state of dosimetry control for food processing and the Bulgarian long experience in food irradiation (three irradiation facilities are operational at these moment) are presented. The absence of neither national standard for high doses nor accredited laboratory for calibration and audit of radiation processing dosimetry systems is also discussed

Shielding Aspects of Accelerators, Targets and Irradiation Facilities - SATIF-11 Workshop Proceedings Report

International Nuclear Information System (INIS)

2013-01-01

Particle accelerators have evolved over the last decades from simple devices to powerful machines. In recent years, new technological and research applications have helped to define requirements while the number of accelerator facilities in operation, being commissioned, designed or planned has grown significantly. Their parameters, which include the beam energy, currents and intensities, and target composition, can vary widely, giving rise to new radiation shielding issues and challenges. Particle accelerators must be operated in safe ways to protect operators, the public and the environment. As the design and use of these facilities evolve, so must the analytical methods used in the safety analyses. These workshop proceedings review the state of the art in radiation shielding of accelerator facilities and irradiation targets. They also evaluate progress in the development of modelling methods used to assess the effectiveness of such shielding as part of safety analyses. The transport of radiation through shielding materials is a major consideration in the safety design studies of nuclear power plants, and the modelling techniques used may be applied to many other types of scientific and technological facilities. Accelerator and irradiation facilities represent a key capability in R and D, medical and industrial infrastructures, and they can be used in a wide range of scientific, medical and industrial applications. High-energy ion accelerators, for example, are now used not only in fundamental research, such as the search for new super-heavy nuclei, but also for therapy as part of cancer treatment. While the energy of the incident particles on the shielding of these facilities may be much higher than those found in nuclear power plants, much of the physics associated with the behaviour of the secondary particles produced is similar, as are the computer modelling techniques used to quantify key safety design parameters, such as radiation dose and activation levels

Development of an irradiation system for a small size continuous run multipurpose gamma irradiator

International Nuclear Information System (INIS)

Calvo, Wilson Aparecido Parejo

2005-01-01

The Radiation Technology Center from Instituto de Pesquisas Energeticas e Nucleares (IPEN-CNEN/SP), Brazil, developed with a revolutionary design and national technology, a small size continuous run and multipurpose industrial gamma irradiator, to be used as a demonstration facility for manufacturers and contract service companies, which need economical and logistical in-house irradiation system alternatives. Also, to be useful for supporting the local scientific community on development of products and process using gamma radiation, assisting the traditional and potential users on process validation, training and qualification of operators and radioprotection officers. The developed technology for this facility consists of continuous tote box transport system, comprising a single concrete vault, where the automated transport system of products inside and outside of the irradiator utilizes a rotate door, integrated with the shielding, avoiding the traditional maze configuration. Covering 76 m 2 of floor area, the irradiator design is product overlap sources and the maximum capacity of cobalt-60 wet sources is 37 P Bq (1 MCi). The performed quantification program of this multipurpose irradiator was based on AAMI/ISO 11137 standard, which recommends the inclusion of the following elements: installation and process quantification. The initial load of the multipurpose irradiator was 3.4 P Bq (92.1 k Ci) with 13 cobalt-60 sources model C-188, supplied by MDS Nordion Ion Technologies - Canada. For irradiator dose optimization, the source distribution was done using the software Cadgamma developed by IPEN-CNEN/SP. The poly-methylmethacrylate (PMMA) dosimeters system, certified by the International Dose Assurance Service (IDAS) of the International Atomic Energy Agency (IAEA) was used for irradiator dose mapping. The economic analysis, performance concerning to dose uniformity and cobalt-60 utilization efficiency were calculated and compared with other commercial gamma

Characterisation of the epithermal neutron irradiation facility at the Portuguese research reactor using MCNP.

Science.gov (United States)

Beasley, D G; Fernandes, A C; Santos, J P; Ramos, A R; Marques, J G; King, A

2015-05-01

The radiation field at the epithermal beamline and irradiation chamber installed at the Portuguese Research Reactor (RPI) at the Campus Tecnológico e Nuclear of Instituto Superior Técnico was characterised in the context of Prompt Gamma Neutron Activation Analysis (PGNAA) applications. Radiographic films, activation foils and thermoluminescence dosimeters were used to measure the neutron fluence and photon dose rates in the irradiation chamber. A fixed-source MCNPX model of the beamline and chamber was developed and compared to measurements in the first step towards planning a new irradiation chamber. The high photon background from the reactor results in the saturation of the detector and the current facility configuration yields an intrinsic insensitivity to various elements of interest for PGNAA. These will be addressed in future developments. Copyright © 2015 Elsevier Ltd. All rights reserved.

A description of the Canadian irradiation-research facility proposed to replace the NRU reactor

Energy Technology Data Exchange (ETDEWEB)

Lee, A G; Lidstone, R F; Bishop, W E; Talbot, E F; McIlwain, H [Atomic Energy of Canada Ltd., Pinawa, MB (Canada). Whiteshell Labs.

1996-12-31

To replace the aging NRU reactor, AECL has developed the concept for a dual-purpose national Irradiation Research Facility (IRF) that tests fuel and materials for CANDU (CANada Deuterium Uranium) reactors and performs materials research using extracted neutron beams. The IRF includes a MAPLE reactor in a containment building, experimental facilities, and support facilities. At a nominal reactor power of 40 MW{sub t}, the IRF will generate powers up to 1 MW in natural-uranium CANDU bundles, fast-neutron fluxes up to 1.4 x 10{sup 18} n{center_dot}m{sup -2}{center_dot}s{sup -1} in Zr-alloy specimens, and thermal-neutron fluxes matching those available to the NRU beam tubes. (author). 9 refs., 5 tabs., 2 figs.

Radiation control standards and procedures

Energy Technology Data Exchange (ETDEWEB)

1956-12-14

This manual contains the Radiation Control Standards'' and Radiation Control Procedures'' at Hanford Operations which have been established to provide the necessary control radiation exposures within Irradiation Processing Department. Provision is also made for including, in the form of Bulletins'', other radiological information of general interest to IPD personnel. The purpose of the standards is to establish firm radiological limits within which the Irradiation Processing Department will operate, and to outline our radiation control program in sufficient detail to insure uniform and consistent application throughout all IPD facilities. Radiation Control Procedures are intended to prescribe the best method of accomplishing an objective within the limitations of the Radiation Control Standards. A procedure may be changed at any time provided the suggested changes is generally agreeable to management involved, and is consistent with department policies and the Radiation Control Standards.

Dose measurements for characterization of a semi-industrial cobalt-60 gamma-irradiation facility

International Nuclear Information System (INIS)

Farah, K.; Jerbi, T.; Kuntz, F.; Kovacs, A.

2006-01-01

Cobalt-60 irradiation facility has been put into operation at the National Centre of Nuclear Sciences and Technology, Sidi-thabet, Tunisia. Its technical specifications were controlled by dosimetry commissioning experiments and compared to the data specified by the plant manufacturer. Installation qualification has been carried out to measure absorbed dose distribution in the irradiation cell and products. Two dosimeter systems were used for measurements: Red and Amber Perspex and Cellulose Triacetate (CTA). The regions of minimum and maximum absorbed dose within a homogeneous dummy product (sawdust) with a bulk density of 114kg/m 3 and the dose uniformity ratio were determined. The isodose curves and the three-dimensional views were built using an automatic geostatistical gridding method, the kriging method

Accelerator conceptual design of the international fusion materials irradiation facility

International Nuclear Information System (INIS)

Sugimoto, M.; Kinsho, M.; Teplyakov, V.; Berwald, D.; Bruhwiler, D.; Peakock, M.; Rathke, J.; Deitinghoff, H.; Klein, H.; Pozimski, Y.; Volk, K.; Miyahara, A.; Olivier, M.; Piechowiak, E.; Tanabe, Y.

1998-01-01

The accelerator system of the international fusion materials irradiation facility (IFMIF) provides the 250-mA, 40-MeV continuous-wave deuteron beam at one of the two lithium target stations. It consists of two identical linear accelerator modules, each of which independently delivers a 125-mA beam to the common footprint of 20 cm x 5 cm at the target surface. The accelerator module consists of an ion injector, a 175 MHz RFQ and eight DTL tanks, and rf power supply system. The requirements for the accelerator system and the design concept are described. The interface issues and operational considerations to attain the proposed availability are also discussed. (orig.)

Economics of gamma irradiation processing

International Nuclear Information System (INIS)

Tani, Toshio

1980-01-01

The gamma-ray irradiation business started at the Takasaki Laboratory of Japan Atomic Energy Research Institute. The irradiation facilities were constructed thereafter at various sites. The facilities must accept various types of irradiation, and must be constructed as multi-purpose facilities. The cost of irradiation consists of the cost of gamma sources, construction expense, personnel expense, management expense, and bank interest. Most of the expenses are considered to be fixed expense, and the amount of irradiation treatment decides the original costs of work. The relation between the irradiation dose and the construction expense shows the larger facility is more economical. The increase of amount of treatment reduces the original cost. The utilization efficiency becomes important when the amount of treatment and the source intensity exceed some values. The principal subjects of gamma-ray irradiation business are the sterilization of medical tools and foods for aseptic animals, the improvement of quality of plastic goods, and the irradiation of foods. Among them, the most important subject is the sterilization of medical tools. The cost of gamma irradiation per m 3 in still more expensive than that by ethylene oxide gas sterilization. However, the demand of gamma-ray irradiation is increasing. For the improvement of quality of plastic goods, electron irradiation is more favourable than the gamma irradiation. In near future, the economical balance of gamma irradiation can be achieved. (Kato, T.)

Facility effluent monitoring plan for the 327 Facility

International Nuclear Information System (INIS)

1994-11-01

The 327 Facility [Post-Irradiation Testing Laboratory] provides office and laboratory space for Pacific Northwest Laboratory (PNL) scientific and engineering staff conducting multidisciplinary research in the areas of post-irradiated fuels and structural materials. The facility is designed to accommodate the use of radioactive and hazardous materials in the conduct of these activities. This report summarizes the airborne emissions and liquid effluents and the results of the Facility Effluent Monitoring Plan (FEMP) determination for the facility. The complete monitoring plan includes characterization of effluent streams, monitoring/sampling design criteria, a description of the monitoring systems and sample analysis, and quality assurance requirements

Integrating industry nuclear codes and standards into United States Department of Energy facilities

Energy Technology Data Exchange (ETDEWEB)

Jacox, J.

1995-02-01

Recently the United States Department of Energy (DOE) has mandated facilities under their jurisdiction use various industry Codes and Standards developed for civilian power reactors that operate under U.S. Nuclear Regulatory Commission License. While this is a major step forward in putting all our nuclear facilities under common technical standards there are always problems associated with implementing such advances. This paper will discuss some of the advantages and problems experienced to date. These include the universal challenge of educating new users of any technical documents, repeating errors made by the NRC licensed facilities over the years and some unique problems specific to DOE facilities.

International status of food irradiation

International Nuclear Information System (INIS)

Diehl, J.F.

1983-01-01

Radiation processing of foods has been studied for over 30 years. To a considerable extent this research was carried out in the framework of various international projects. After optimistic beginnings in the 1950s and long delays, caused by uncertainty about the health safety of foods so treated, food irradiation has now reached the stage of practical application in several countries. In order to prepare the way for world-wide accceptance of the new process, the Codex Alimentarius Commission has accepted an 'International General Standard for Irradiated Foods' and an 'International Code of Practice for the Operation of Irradiation Facilities Used for the Treatment of Foods'. Psychological barriers to a process associated with the word 'radiation' are still formidable; it appears, however, that acceptance by authorities, food industry and consumers continues to grow

Biological shielding design and qualification of concreting process for construction of electron beam irradiation facility

International Nuclear Information System (INIS)

Petwal, V.C.; Kumar, P.; Suresh, N.; Parchani, G.; Dwivedi, J.; Thakurta, A.C.

2011-01-01

A technology demonstration facility for irradiation of food and agricultural products is being set-up by RRCAT at Indore. The facility design is based on linear electron accelerator with maximum beam power of 10 kW and can be operated either in electron mode at 10 MeV or photon modes at 5/7.5 MeV. Biological shielding has been designed in accordance with NCRP 51 to achieve dose rate at all accessible points outside the irradiation vault less than the permissible limit of 0.1 mR/hr. In addition to radiation attenuation property, concrete must have satisfactory mechanical properties to meet the structural requirements. There are number of site specific variables which affect the structural, thermal and radiological properties of concrete, leading to considerable difference in actual values and design values. Hence it is essential to establish a suitable site and environmental specific process to cast the concrete and qualify the process by experimental measurement. For process qualification we have cast concrete test blocks of different thicknesses up to 3.25 m and evaluated the radiological and mechanical properties by radiometry, ultrasonic and mechanical tests. In this paper we describe the biological shielding design of the facility and analyse the results of tests carried out for qualification of the process. (author)

Advancements in internationally accepted standards for radiation processing

International Nuclear Information System (INIS)

Farrar, H. IV; Derr, D.D.; Vehar, D.W.

1993-01-01

Subcommittees of the American Society for Testing and Materials (ASTM) are developing standards on various aspects of radiation processing. Nine standards on how to select and calibrate dosimeters, where to put them, how many to use, and how to use individual types of dosimeter systems have been published. The group is also developing standards on how to use gamma, electron beam, and X-ray facilities for radiation processing, and a standard on how to treat dose uncertainties. Efforts are underway to promote inclusion of these standards into procedures now being developed by government agencies and by international groups such as the United Nations' International Consultative Group on Food Irradiation (ICGFI) in order to harmonize regulations and help avoid trade barriers. Standards on good irradiation practices for meat and poultry and for fresh fruits, and for the irradiation of seafood and spices have been developed. These food-related standards are based on practices previously published by ICGFI. Standards for determining doses for radiation hardness testing of electronics have been developed. Standards on the Fricke and TLD dosimetry systems are equally useful in other radiation processing applications. (Author)

IFMIF-KEP. International fusion materials irradiation facility key element technology phase report

International Nuclear Information System (INIS)

2003-03-01

The International Fusion Materials Irradiation Facility (IFMIF) is an accelerator-based D-Li neutron source designed to produce an intense neutron field that will simulate the neutron environment of a D-T fusion reactor. IFMIF will provide a neutron flux equivalent to 2 MW/m 2 , 20 dpa/y in Fe, in a volume of 500 cm 3 and will be used in the development and qualification of materials for fusion systems. The design activities of IFMIF are performed under an IEA collaboration which began in 1995. In 2000, a three-year Key Element Technology Phase (KEP) of IFMIF was undertaken to reduce the key technology risk factors. This KEP report describes the results of the three-year KEP activities in the major project areas of accelerator, target, test facilities and design integration. (author)

DOE standard: Filter test facility quality program plan

International Nuclear Information System (INIS)

1999-02-01

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

Practice for dosimetry in electron and bremsstrahlung irradiation facilities for food processing. 2. ed.

International Nuclear Information System (INIS)

2002-01-01

This practice describes dosimetric procedures to be followed in facility characterization, process qualification, and routine processing for electron beam and bremsstrahlung irradiation facilities for food processing to ensure that product receives an acceptable range of absorbed doses. Other procedures related to facility characterization, process qualification, and routine product processing that may influence and be used to monitor absorbed dose in the product are also discussed. Information about effective or regulatory dose limits for food products is not within the scope of this practice (see ASTM Guides F 1355 and F 1356). The electron energy range covered in this practice is from 0.3 MeV to 10 MeV. Such electrons can be generated in continuous or pulse modes. The maximum electron energy of bremsstrahlung facilities covered in this practice is 10 MeV. A photon beam can be generated by inserting a bremsstrahlung converter in the electron beam path (See ISO/ASTM Practice 51608

Analyses in support of risk-informed natural gas vehicle maintenance facility codes and standards :

Energy Technology Data Exchange (ETDEWEB)

Ekoto, Isaac W.; Blaylock, Myra L.; LaFleur, Angela Christine; LaChance, Jeffrey L.; Horne, Douglas B.

2014-03-01

Safety standards development for maintenance facilities of liquid and compressed gas fueled large-scale vehicles is required to ensure proper facility design and operation envelopes. Standard development organizations are utilizing risk-informed concepts to develop natural gas vehicle (NGV) codes and standards so that maintenance facilities meet acceptable risk levels. The present report summarizes Phase I work for existing NGV repair facility code requirements and highlights inconsistencies that need quantitative analysis into their effectiveness. A Hazardous and Operability study was performed to identify key scenarios of interest. Finally, scenario analyses were performed using detailed simulations and modeling to estimate the overpressure hazards from HAZOP defined scenarios. The results from Phase I will be used to identify significant risk contributors at NGV maintenance facilities, and are expected to form the basis for follow-on quantitative risk analysis work to address specific code requirements and identify effective accident prevention and mitigation strategies.

Gamma irradiation facilities for radiation tolerance assessment of components and systems at SCK.CEN

International Nuclear Information System (INIS)

Coenen, S.; Decreton, M.

1999-01-01

This paper presents the different gamma irradiation facilities available at SCK-CEN (Mol, Belgium). With gamma dose rates ranging from 1 Gy/h up to 50 kGy/h, extensive environmental control and on-line instrumentation possibilities, they offer ideal test environments for the radiation tolerance assessment of components and systems for many applications where radiation tolerance is a concern. (authors)

A standardization of the physical tests for external irradiation measuring detectors

International Nuclear Information System (INIS)

1977-05-01

This report is the result of a standardization work, realized within the Radioprotection Services of the A.E.C., of the physical tests for dectors measuring external irradiations. Among the various tests mentionned, calibration and the establishment of the relative spectral response are treated in details. As far as calibration is concerned, the standardization refers to: the reference detector, the reference radiation source, the installation and calibration procedure. As for the relative spectral response the standardization refers to: the reference detector, the radiation sources to be used. High flux detectors and those for pulse electromagnetic radiations are also dealt with [fr

Proton irradiated graphite grades for a long baseline neutrino facility experiment

International Nuclear Information System (INIS)

Simos, N.; Nocera, P.; Zwaska, R.; Mokhov, N.

2017-01-01

In search of a low-Z pion production target for the Long Baseline Neutrino Facility (LBNF) of the Deep Underground Neutrino Experiment (DUNE) four graphite grades were irradiated with protons in the energy range of 140–180 MeV, to peak fluence of ~6.1×10"2"0 p/cm"2 and irradiation temperatures between 120–200 °C. The test array included POCO ZXF-5Q, Toyo-Tanso IG 430, Carbone-Lorraine 2020 and SGL R7650 grades of graphite. Irradiation was performed at the Brookhaven Linear Isotope Producer. Postirradiation analyses were performed with the objective of (a) comparing their response under the postulated irradiation conditions to guide a graphite grade selection for use as a pion target and (b) understanding changes in physical and mechanical properties as well as microstructure that occurred as a result of the achieved fluence and in particular at this low-temperature regime where pion graphite targets are expected to operate. A further goal of the postirradiation evaluation was to establish a proton-neutron correlation damage on graphite that will allow for the use of a wealth of available neutron-based damage data in proton-based studies and applications. Macroscopic postirradiation analyses as well as energy dispersive x-ray diffraction of 200 KeV x rays at the NSLS synchrotron of Brookhaven National Laboratory were employed. The macroscopic analyses revealed differences in the physical and strength properties of the four grades with behavior however under proton irradiation that qualitatively agrees with that reported for graphite under neutrons for the same low temperature regime and in particular the increase of thermal expansion, strength and Young’s modulus. The proton fluence level of ~10"2"0 cm"-"2 where strength reaches a maximum before it begins to decrease at higher fluences has been identified and it agrees with neutron-induced changes. X-ray diffraction analyses of the proton irradiated graphite revealed for the first time the similarity in

Proton irradiated graphite grades for a long baseline neutrino facility experiment

Directory of Open Access Journals (Sweden)

N. Simos

2017-07-01

Full Text Available In search of a low-Z pion production target for the Long Baseline Neutrino Facility (LBNF of the Deep Underground Neutrino Experiment (DUNE four graphite grades were irradiated with protons in the energy range of 140–180 MeV, to peak fluence of ∼6.1×10^{20}  p/cm^{2} and irradiation temperatures between 120–200 °C. The test array included POCO ZXF-5Q, Toyo-Tanso IG 430, Carbone-Lorraine 2020 and SGL R7650 grades of graphite. Irradiation was performed at the Brookhaven Linear Isotope Producer. Postirradiation analyses were performed with the objective of (a comparing their response under the postulated irradiation conditions to guide a graphite grade selection for use as a pion target and (b understanding changes in physical and mechanical properties as well as microstructure that occurred as a result of the achieved fluence and in particular at this low-temperature regime where pion graphite targets are expected to operate. A further goal of the postirradiation evaluation was to establish a proton-neutron correlation damage on graphite that will allow for the use of a wealth of available neutron-based damage data in proton-based studies and applications. Macroscopic postirradiation analyses as well as energy dispersive x-ray diffraction of 200 KeV x rays at the NSLS synchrotron of Brookhaven National Laboratory were employed. The macroscopic analyses revealed differences in the physical and strength properties of the four grades with behavior however under proton irradiation that qualitatively agrees with that reported for graphite under neutrons for the same low temperature regime and in particular the increase of thermal expansion, strength and Young’s modulus. The proton fluence level of ∼10^{20}  cm^{−2} where strength reaches a maximum before it begins to decrease at higher fluences has been identified and it agrees with neutron-induced changes. X-ray diffraction analyses of the proton irradiated graphite

Proton irradiated graphite grades for a long baseline neutrino facility experiment

Science.gov (United States)

Simos, N.; Nocera, P.; Zhong, Z.; Zwaska, R.; Mokhov, N.; Misek, J.; Ammigan, K.; Hurh, P.; Kotsina, Z.

2017-07-01

In search of a low-Z pion production target for the Long Baseline Neutrino Facility (LBNF) of the Deep Underground Neutrino Experiment (DUNE) four graphite grades were irradiated with protons in the energy range of 140-180 MeV, to peak fluence of ˜6.1 ×1020 p /cm2 and irradiation temperatures between 120 - 200 °C . The test array included POCO ZXF-5Q, Toyo-Tanso IG 430, Carbone-Lorraine 2020 and SGL R7650 grades of graphite. Irradiation was performed at the Brookhaven Linear Isotope Producer. Postirradiation analyses were performed with the objective of (a) comparing their response under the postulated irradiation conditions to guide a graphite grade selection for use as a pion target and (b) understanding changes in physical and mechanical properties as well as microstructure that occurred as a result of the achieved fluence and in particular at this low-temperature regime where pion graphite targets are expected to operate. A further goal of the postirradiation evaluation was to establish a proton-neutron correlation damage on graphite that will allow for the use of a wealth of available neutron-based damage data in proton-based studies and applications. Macroscopic postirradiation analyses as well as energy dispersive x-ray diffraction of 200 KeV x rays at the NSLS synchrotron of Brookhaven National Laboratory were employed. The macroscopic analyses revealed differences in the physical and strength properties of the four grades with behavior however under proton irradiation that qualitatively agrees with that reported for graphite under neutrons for the same low temperature regime and in particular the increase of thermal expansion, strength and Young's modulus. The proton fluence level of ˜1020 cm-2 where strength reaches a maximum before it begins to decrease at higher fluences has been identified and it agrees with neutron-induced changes. X-ray diffraction analyses of the proton irradiated graphite revealed for the first time the similarity in

Isodose distributions and dose uniformity in the Portuguese gamma irradiation facility calculated using the MCNP code

CERN Document Server

Oliveira, C

2001-01-01

A systematic study of isodose distributions and dose uniformity in sample carriers of the Portuguese Gamma Irradiation Facility was carried out using the MCNP code. The absorbed dose rate, gamma flux per energy interval and average gamma energy were calculated. For comparison purposes, boxes filled with air and 'dummy' boxes loaded with layers of folded and crumpled newspapers to achieve a given value of density were used. The magnitude of various contributions to the total photon spectra, including source-dependent factors, irradiator structures, sample material and other origins were also calculated.

Long-term temporal stability of the National Institute of Standards and Technology spectral irradiance scale determined with absolute filter radiometers

International Nuclear Information System (INIS)

Yoon, Howard W.; Gibson, Charles E.

2002-01-01

The temporal stability of the National Institute of Standards and Technology (NIST) spectral irradiance scale as measured with broadband filter radiometers calibrated for absolute spectral irradiance responsivity is described. The working standard free-electron laser (FEL) lamps and the check standard FEL lamps have been monitored with radiometers in the ultraviolet and the visible wavelength regions. The measurements made with these two radiometers reveal that the NIST spectral irradiance scale as compared with an absolute thermodynamic scale has not changed by more than 1.5% in the visible from 1993 to 1999. Similar measurements in the ultraviolet reveal that the corresponding change is less than 1.5% from 1995 to 1999. Furthermore, a check of the spectral irradiance scale by six different filter radiometers calibrated for absolute spectral irradiance responsivity based on the high-accuracy cryogenic radiometer shows that the agreement between the present scale and the detector-based scale is better than 1.3% throughout the visible to the near-infrared wavelength region. These results validate the assigned spectral irradiance of the widely disseminated NIST or NIST-traceable standard sources

IFMIF-KEP. International fusion materials irradiation facility key element technology phase report

Energy Technology Data Exchange (ETDEWEB)

NONE

2003-03-01

The International Fusion Materials Irradiation Facility (IFMIF) is an accelerator-based D-Li neutron source designed to produce an intense neutron field that will simulate the neutron environment of a D-T fusion reactor. IFMIF will provide a neutron flux equivalent to 2 MW/m{sup 2}, 20 dpa/y in Fe, in a volume of 500 cm{sup 3} and will be used in the development and qualification of materials for fusion systems. The design activities of IFMIF are performed under an IEA collaboration which began in 1995. In 2000, a three-year Key Element Technology Phase (KEP) of IFMIF was undertaken to reduce the key technology risk factors. This KEP report describes the results of the three-year KEP activities in the major project areas of accelerator, target, test facilities and design integration. (author)

An economic benefit analysis on the cobalt-60 irradiation facility of Beijing Radiation Research Center

International Nuclear Information System (INIS)

Wang Binlin

1995-01-01

The peculiarity, the investment and annual operating cost of the 3.7 x 10 16 Bq (MCi) cobalt-60 irradiation facility at Beijing Radiation Application Research Centre are described. Its economic benefits each year are analyzed according to several year operating practice. Some related questions on carrying out radiation processing are raised and discussed. (author)

Accelerator conceptual design of the international fusion materials irradiation facility

Energy Technology Data Exchange (ETDEWEB)

Sugimoto, M.; Kinsho, M. [Japan Atomic Energy Res. Inst., Tokai, Ibaraki (Japan). Intense Neutron Source Lab.; Jameson, R.A.; Blind, B. [Los Alamos National Lab., NM (United States); Teplyakov, V. [Institute for High Energy Physics, Moscow (Russian Federation); Berwald, D.; Bruhwiler, D.; Peakock, M.; Rathke, J. [Northrop Grumman Corp., Bethpage, NY (United States); Deitinghoff, H.; Klein, H.; Pozimski, Y.; Volk, K. [Johann Wolfgang Goethe Univ., Frankfurt (Germany). Inst. fur Angewandte Phys.; Ferdinand, R.; Lagniel, J.-M. [CEA Saclay LNS, Gif-sur-Yvette (France); Miyahara, A. [Teikyo Univ., Tokyo (Japan); Olivier, M. [CEA DSM, Saclay, Gif-sur-Yvette (France); Piechowiak, E. [Northrop Grumman Corp., Baltimore, MD (United States); Tanabe, Y. [Toshiba Corp., Tsurumi-ku, Yokohama (Japan)

1998-10-01

The accelerator system of the international fusion materials irradiation facility (IFMIF) provides the 250-mA, 40-MeV continuous-wave deuteron beam at one of the two lithium target stations. It consists of two identical linear accelerator modules, each of which independently delivers a 125-mA beam to the common footprint of 20 cm x 5 cm at the target surface. The accelerator module consists of an ion injector, a 175 MHz RFQ and eight DTL tanks, and rf power supply system. The requirements for the accelerator system and the design concept are described. The interface issues and operational considerations to attain the proposed availability are also discussed. (orig.) 8 refs.

Development of Pneumatic Transfer Irradiation Facility (PTS no.3) for Neutron Activation Analysis at HANARO Research Reactor

Energy Technology Data Exchange (ETDEWEB)

Chung, Y. S.; Moon, J. H.; Kim, S. H.; Sun, G. M.; Baek, S. Y.; Kim, H. R.; Kim, Y. J

2008-04-15

A pneumatic transfer system (PTS) is one of the most important facilities used during neutron irradiation of a target material for instrumental neutron activation analysis (INAA) in a research reactor. In particular, a fast pneumatic transfer system is essential for the measurement of a short half-life nuclide. The pneumatic transfer irradiation system (PTS no.3) involving a manual system and an semi-automatic system were reconstructed with new designs of a functional improvement at the HANARO research reactor and NAA laboratory of RI building in 2006. In this technical report, the design, operation and control of these system (PTS no.3) was described. Also the experimental results and the characteristic parameters measured from a functional operation test and an irradiation test of these systems, such as the transfer time of irradiation capsule, the different neutron flux, the temperature of the irradiation position with an irradiation time, the radiation dose rate when the rabbit is returned, etc. are reported to provide a user information as well as a reactor's management and safety.

Quality engineering in FFTF irradiation tests

International Nuclear Information System (INIS)

Caplinger, W.H.

1980-01-01

The design and fabrication of an irradiation test for the Fast Flux Test Facility are planned, controlled and documented in accordance with the Department of Energy standards. Tests built by Westinghouse Hanford Company are further controlled and guided by a series of increasingly specific documents, including guidelines for program control, procedures for engineering operations, standard practices and detailed operating procedures. In response to this guidance, a series of five documents is prepared covering each step of the experiment from conception through fabrication and assembly. This paper describes the quality assurance accompanying these five steps

Thermohydraulic study of a MTR fuel element aimed at the construction of an irradiation facility

International Nuclear Information System (INIS)

Coragem, Helio Boemer de Oliveira

1980-01-01

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

Characteristics of neutron irradiation facility and dose estimation method for neutron capture therapy at Kyoto University research reactor institute

International Nuclear Information System (INIS)

Kobayashi, T.; Sakurai, Y.; Kanda, K.

2001-01-01

The neutron irradiation characteristics of the Heavy Water Neutron Irradiation Facility (HWNIF) at the Kyoto University Research Reactor Institute (KIJRRI) for boron neutron capture therapy (BNCT), is described. The present method of dose measurement and its evaluation at the KURRI, is explained. Especially, the special feature and noticeable matters were expounded for the BNCT with craniotomy, which has been applied at present only in Japan. (author)

Development of the irradiation facility SIBO INRA/Tangier, Morocco by upgrading cobalt-60 in a temporary pool and enhancing safety and control features

Directory of Open Access Journals (Sweden)

Mohammed Mouhib

2017-12-01

Full Text Available An automatic control system is one of the most important parts of an irradiation facility. The level of this control is always maintained to comply with safety procedures during routine work in this field. Also sometimes it is limited to the minimum level of regulation required due to economical aspects; some commercial systems are generally made by manufacturers of industrial facilities and considered affordable by irradiators. In some cases specific irradiation facilities tailor their control systems to their needs. For this kind of irradiator the control system can be developed and upgraded according to personal and industrial experiences. These upgrading procedures are also used by others to develop their systems. The objective of this paper is to share a local experience in upgrading security, safety systems and the use of cobalt-60 for the irradiator. It is a composite experiment at SIBO INRA/Tangier, Morocco and concerns the: (i upgrade of cobalt-60 in a temporary pool in the SIBO irradiator in Tangier. This operation was conducted in collaboration with the International Atomic Energy Agency (IAEA and was a success story of 2014 according to the general conference of IAEA; (ii safety and technical upgrade of the system in the SIBO irradiator made in collaboration with IAEA; (iii installation and upgrade of the security system in accordance with the Global Threat Reduction Programme (GTRP to reduce the threat of a Radiological Dispersal Device (RDD in collaboration with The United States Department of Energy’s National Nuclear Security Administration (NNSA.

DUPIC facility engineering

Energy Technology Data Exchange (ETDEWEB)

Park, J. J.; Lee, H. H.; Kim, K. H. and others

2000-03-01

The objectives of this study are (1) the refurbishment for PIEF(Post Irradiation Examination Facility) and M6 hot-cell in IMEF(Irradiated Material Examination Facility), (2) the establishment of the compatible facility for DUPIC fuel fabrication experiments which is licensed by government organization, and (3) the establishment of the transportation system and transportation cask for nuclear material between facilities. The report for this project describes following contents, such as objectives, necessities, scope, contents, results of current step, R and D plan in future and etc.

Development of Pneumatic Transfer Irradiation Facility (PTS no.2) for Neutron Activation Analysis at HANARO Research Reactor

Energy Technology Data Exchange (ETDEWEB)

Chung, Y. S.; Moon, J. H.; Kim, S. H.; Sun, G. M.; Baek, S. Y.; Kim, H. R.; Kim, Y. J

2008-03-15

A pneumatic transfer irradiation system (PTS) is one of the most important facilities used during neutron irradiation of a target material for instrumental neutron activation analysis (INAA) in a research reactor. In particular, a fast pneumatic transfer system is essential for the measurement of a short half-life nuclide and a delayed neutron counting system. The pneumatic transfer irradiation system (PTS no.2) involving a manual system and an automatic system for delayed neutron activation analysis (DNAA) were reconstructed with new designs of a functional improvement at the HANARO research reactor in 2006. In this technical report, the conception, design, operation and control of PTS no.2 was described. Also the experimental results and the characteristic parameters measured by a mock-up test, a functional operation test and an irradiation test of these systems, such as the transfer time of irradiation capsule, automatic operation control by personal computer, delayed neutron counting system, the different neutron flux, the temperature of the irradiation position with an irradiation time, the radiation dose rate when the rabbit is returned, etc. are reported to provide a user information as well as a reactor's management and safety.

Waste encapsulation storage facility (WESF) standards/requirements identification document (S/RIDS)

Energy Technology Data Exchange (ETDEWEB)

Maddox, B.S., Westinghouse Hanford

1996-07-29

This Standards/Requirements Identification Document (S/RID) sets forth the Environmental Safety and Health (ES{ampersand}H) standards/requirements for the Waste Encapsulation Storage Facility (WESF). This S/RID is applicable to the appropriate life cycle phases of design, construction, operation, and preparation for decommissioning. These standards/requirements are adequate to ensure the protection of the health and safety of workers, the public, and the environment.

Accident analysis for aircraft crash into hazardous facilities: DOE standard

International Nuclear Information System (INIS)

1996-10-01

This standard provides the user with sufficient information to evaluate and assess the significance of aircraft crash risk on facility safety without expending excessive effort where it is not required. It establishes an approach for performing a conservative analysis of the risk posed by a release of hazardous radioactive or chemical material resulting from an aircraft crash into a facility containing significant quantities of such material. This can establish whether a facility has a significant potential for an aircraft impact and whether this has the potential for producing significant offsite or onsite consequences. General implementation guidance, screening and evaluation guidelines, and methodologies for the evaluations are included

Practice for dosimetry in an X-ray (bremsstrahlung) facility for radiation processing. 2. ed.

International Nuclear Information System (INIS)

2002-01-01

This practice covers dosimetric procedures to be followed in facility characterization, process qualification, and routine processing using X rays (bremsstrahlung) to ensure that the entire product has been treated within an acceptable range of absorbed doses. Other procedures related to facility characterization, process qualification, and routine processing that may influence absorbed dose in the product are also discussed. The establishment of effective or regulatory dose and X-ray energy limits are not within the scope of this practice. In contrast to monoenergetic gamma rays, the bremsstrahlung energy spectrum extends from low values up to the maximum energy of the electrons incident on the X-ray target (see Section 5 and Annex A1). Dosimetry is only one component of a total quality assurance program for an irradiation facility. Other controls besides dosimetry may be required for specific applications such as medical device sterilization and food preservation. For the irradiation of food and the radiation sterilization of health care products, other specific ISO standards exist. For food irradiation, see ISO/ASTM Practice 51431. For the radiation sterilization of health care products, see ISO 11137:1995. In those areas covered by ISO 11137, that standard takes precedence

Methodology to evaluate the site standard seismic motion to a nuclear facility

International Nuclear Information System (INIS)

Soares, W.A.

1983-01-01

For the seismic design of nuclear facilities, the input motion is normally defined by the predicted maximum ground horizontal acceleration and the free field ground response spectrum. This spectrum is computed on the basis of records of strong motion earthquakes. The pair maximum acceleration-response spectrum is called the site standard seismic motion. An overall view of the subjects involved in the determination of the site standard seismic motion to a nuclear facility is presented. The main topics discussed are: basic principles of seismic instrumentation; dynamic and spectral concepts; design earthquakes definitions; fundamentals of seismology; empirical curves developed from prior seismic data; available methodologies and recommended procedures to evaluate the site standard seismic motion. (Author) [pt

Practice for dosimetry in gamma irradiation facilities for radiation processing. 2. ed.

International Nuclear Information System (INIS)

2004-01-01

This practice outlines the installation qualification program for an irradiator and the dosimetric procedures to be followed during operational qualification, performance quali- fication, and routine processing in facilities that process product with ionizing radiation from radionuclide gamma sources to ensure that product has been treated within a predetermined range of absorbed dose. Other procedures related to installation qualification, operational qualification, performance qualification, and routine processing that may influence absorbed dose in the product are also discussed. Information about effective or regulatory absorbed-dose limits is not within the scope of this practice

Performance testing of beta dosimeters used at Department of Energy facilities

International Nuclear Information System (INIS)

Roberson, P.L.; Holbrook, K.L.; Pappin, J.L.

1983-01-01

A performance test based on the American national draft standard N13.11 was conducted for dosimeter systems in use at Department of Energy facilities. The large differences in dosimeter response found were due to use of different calibration source standards and different dosimeter designs. Differences in 90 Sr/ 90 Y calibrations were approximately 20% or less for all but one participant. The differences observed were attributed to variable thicknesses of dosimeter elements and variable source irradiation geometries. Improved beta calibration standards will result if irradiation specifications include acceptable ranges from the depth-dose characteristics. The low-energy beta responses observed were consistent with the thicknesses of dosimeter sensitive elements and overlying filtration

Gamma irradiation devices

International Nuclear Information System (INIS)

Foeldiak, Gabor; Stenger, Vilmos.

1983-01-01

The main parameters and the preparation procedures of the gamma radiation sources frequently applied for irradiation purposes are discussed. In addition to 60 Co and 137 Cs sources also the nuclear power plants offer further opportunities: spent fuel elements and products of certain (n,γ) reactions can serve as irradiation sources. Laboratory scale equipments, pilot plant facilities for batch or continuous operation, continuous industrial irradiators and special multipurpose, mobile and panorama type facilities are reviewed including those in Canada, USA, India, the Soviet Union, Hungary, UK, Japan and Australia. For irradiator design the source geometry dependence of the spatial distribution of dose rates can be calculated. (V.N.)

Research to connect the ozone monitor into irradiation system at Hanoi Irradiation Centre

International Nuclear Information System (INIS)

Le Van Huy; Pham Duy Duong; Nguyen Dinh Hung; Vu Quoc Dat

2013-01-01

Since 2006, in order to develop radiation technology, Vietnam Atomic Energy Institute has supported Hanoi Irradiation Centre a Project titled: Upgrading the irradiation facility. According to the Project, equipment have been replaced by a new one so that the facility could be suitable for treatment of products. The facility was designed and produced by the former Russia experts. Under normal operating conditions, we are protected by shielding, detection systems, and safety procedures. A system of interlocks prevents unauthorized entry into the radiation chamber when the source is exposed. However, interlocks system have not been warning and preventing ozone gas that can affect human health. So we are having an upgrade as connecting the ozone monitor into irradiation system at Hanoi Irradiation Centre. (author)

PIREX II, a new irradiation facility for testing fusion first wall materials

International Nuclear Information System (INIS)

Marmy, P.; Daum, M.; Gavillet, D.; Green, S.; Green, W.V.; Hegedues, F.; Pronnecke, S.; Rohrer, U.; Stiefel, U.; Victoria, M.

1988-12-01

A new irradiation facility, PIREX II, became operational in March 1987. It is located on a dedicated beam line split from the main beam of the 590 MeV proton accelerator at the Paul Scherrer Institute (PSI). Irradiation with protons of this energy introduces simultaneously displacement damage, helium and other impurities. Because of the penetration range of 590 MeV protons, both damage and impurities are homogeneously distributed in the target. The installation has its own beam line optics that can support a proton current of up to 50 μA. At a typical beam density of 4 μA/mm 2 , the damage rate in steels is 0.7 x 10 -5 dpa/sec (dpa: displacements per atom) and the helium production rate is 170 appm He/dpa. Both flat tensile specimens of up to 0.4 mm thickness and tubular fatigue samples of 3 mm diameter can be irradiated. Cooling of the temperatures can be controlled between 100 o and 800 o C. Installation of an in situ low cycle fatigue device is foreseen. Beams of up to 20 μA have been obtained, the beam having approximately a gaussian distribution of elliptical cross section with 4 σ between 0.8 and 3 mm by 10 mm. Irradiations for a dosimetry program have been completed on samples of Al, Cu, Fe, Ni, Au, W, and the 1.4914 ferritic steel. The evaluation of results allows the correct choice of reactions to be used for determining total dose, from the standpoint of half life and gamma energy. A program of irradiations on candidate materials for the Next European Torus (NET) design (Cu and Cu alloys, the 1.4914 ferritic martensitic steel, W and W-Re alloys and Mo alloys), where the above mentioned characteristics of this type of irradiation can be used advantageously, is now under way. (author) 11 figs., 4 tabs., 20 refs

Regulations in the field of food irradiation

International Nuclear Information System (INIS)

1991-02-01

The material available for this review, as well as the Guidelines for Preparing Regulations for the Control of Food Irradiation Facilities adopted by ICGFI, the international Conference Document on the Acceptance, Control of and Trade in Irradiated Food, the draft European Economic Community Directive and the Codex General Standard and Code of Practice on food irradiation suggest that the following aspects may be subject to regulation: Food irradiation licensing, radiation safety, food hygiene, package labelling, inspection, certification for commercial purposes. The purpose of this review is to provide Member States with the information necessary for and special to the control of food processing by irradiation, so as to enable them to ensure that they have or they can adopt effective regulations governing all aspects of trade in irradiated food. Three countries have introduced in their food laws special provisions to regulate the processing of food by radiation. Twenty-three countries have issued such special regulations under the existing statutory authority of one of the executive branches: Seven countries either by reference or by incorporation in whole or in part in their regulations, gave recognition to the Codex Standard and Code of Practice. The absence of such specific recognition should not be interpreted, however, to mean that those countries have not accepted the Codex recommendations. Many provisions seem to have taken the Codex recommendations as a guide. 16 refs

Characterization of the neutron irradiation system for use in the Low-Dose-Rate Irradiation Facility at Sandia National Laboratories.

Energy Technology Data Exchange (ETDEWEB)

Franco, Manuel [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

2014-08-01

The objective of this work was to characterize the neutron irradiation system consisting of americium-241 beryllium (241AmBe) neutron sources placed in a polyethylene shielding for use at Sandia National Laboratories (SNL) Low Dose Rate Irradiation Facility (LDRIF). With a total activity of 0.3 TBq (9 Ci), the source consisted of three recycled 241AmBe sources of different activities that had been combined into a single source. The source in its polyethylene shielding will be used in neutron irradiation testing of components. The characterization of the source-shielding system was necessary to evaluate the radiation environment for future experiments. Characterization of the source was also necessary because the documentation for the three component sources and their relative alignment within the Special Form Capsule (SFC) was inadequate. The system consisting of the source and shielding was modeled using Monte Carlo N-Particle transport code (MCNP). The model was validated by benchmarking it against measurements using multiple techniques. To characterize the radiation fields over the full spatial geometry of the irradiation system, it was necessary to use a number of instruments of varying sensitivities. First, the computed photon radiography assisted in determining orientation of the component sources. With the capsule properly oriented inside the shielding, the neutron spectra were measured using a variety of techniques. A N-probe Microspec and a neutron Bubble Dosimeter Spectrometer (BDS) set were used to characterize the neutron spectra/field in several locations. In the third technique, neutron foil activation was used to ascertain the neutron spectra. A high purity germanium (HPGe) detector was used to characterize the photon spectrum. The experimentally measured spectra and the MCNP results compared well. Once the MCNP model was validated to an adequate level of confidence, parametric analyses was performed on the model to optimize for potential

IAEA Post Irradiation Examination Facilities Database

International Nuclear Information System (INIS)

Jenssen, Haakon; Blanc, J.Y.; Dobuisson, P.; Manzel, R.; Egorov, A.A.; Golovanov, V.; Souslov, D.

2005-01-01

The number of hot cells in the world in which post irradiation examination (PIE) can be performed has diminished during the last few decades. This creates problems for countries that have nuclear power plants and require PIE for surveillance, safety and fuel development. With this in mind, the IAEA initiated the issue of a catalogue within the framework of a coordinated research program (CRP), started in 1992 and completed in 1995, under the title of ''Examination and Documentation Methodology for Water Reactor Fuel (ED-WARF-II)''. Within this program, a group of technical consultants prepared a questionnaire to be completed by relevant laboratories. From these questionnaires a catalogue was assembled. The catalogue lists the laboratories and PIE possibilities worldwide in order to make it more convenient to arrange and perform contractual PIE within hot cells on water reactor fuels and core components, e.g. structural and absorber materials. This catalogue was published as working material in the Agency in 1996. During 2002 and 2003, the catalogue was converted to a database and updated through questionnaires to the laboratories in the Member States of the Agency. This activity was recommended by the IAEA Technical Working Group on Water Reactor Fuel Performance and Technology (TWGFPT) at its plenary meeting in April 2001. The database consists of five main areas about PIE facilities: acceptance criteria for irradiated components; cell characteristics; PIE techniques; refabrication/instrumentation capabilities; and storage and conditioning capabilities. The content of the database represents the status of the listed laboratories as of 2003. With the database utilizing a uniform format for all laboratories and details of technique, it is hoped that the IAEA Member States will be able to use this catalogue to select laboratories most relevant to their particular needs. The database can also be used to compare the PIE capabilities worldwide with current and future

Fabrication data package for HEDL dosimetry in the ORNL Poolside Facility: LWR Pressure Vessel Mock-up irradiation

International Nuclear Information System (INIS)

Lippincott, E.P.; McElroy, W.N.; Kellogg, L.S.; Gold, R.; Guthrie, G.L.; Ruddy, F.H.; Ulseth, J.A.

1981-09-01

This document provides a complete description of the HEDL dosimetry inserted in the metallurgical specimen irradiation in the LWR Pressure Vessel Mock-up at the Oak Ridge Reactor Poolside Facility (PSF). This experiment is being conducted under the Nuclear Regulatory Commission sponsored program on Surveillance Dosimetry Improvement. The irradiation started April 1980 with recovery of the 2 x 10 19 (nominal fluence with E > 1 MeV) capsule in September 1980, the 4 x 10 19 surveillance capsule in November 1981 and the pressure vessel and void box capaules about August 1982

Proposed rf system for the fusion materials irradiation test facility

International Nuclear Information System (INIS)

Fazio, M.V.; Johnson, H.P.; Hoffert, W.J.; Boyd, T.J.

1979-01-01

Preliminary rf system design for the accelerator portion of the Fusion Materials Irradiation Test (FMIT) Facility is in progress. The 35-MeV, 100-mA, cw deuteron beam will require 6.3 MW rf power at 80 MHz. Initial testing indicates the EIMAC 8973 tetrode is the most suitable final amplifier tube for each of a series of 15 amplifier chains operating at 0.5-MW output. To satisfy the beam dynamics requirements for particle acceleration and to minimize beam spill, each amplifier output must be controlled to +-1 0 in phase and the field amplitude in the tanks must be held within a 1% tolerance. These tolerances put stringent demands on the rf phase and amplitude control system

Commercial Applications at FRM II Based on Neutron Irradiations

Energy Technology Data Exchange (ETDEWEB)

Gerstenberg, H.; Draack, A.; Kastenmuller, A. [Technische Universitaet Muenchen, Munchen (Germany)

2013-07-01

the production of Mo-99 is in progress. It is noteworthy that all of the irradiation facilities at FRM II have been certified according to the ISO 9001:2008 standard.

Technology standards for structure, etc. concerning nuclear power generating facilities

International Nuclear Information System (INIS)

1977-01-01

Based on the Ordinance for the Technology Standards concerning Nuclear Power Generating Facilities, the technology standards are established for the vessels of class 1 to 4 (including reactor pressure vessels, reactor containment vessels, etc.), the pipes of class 1 to 3, safety valves, pressure test and monitoring test specimens. Those specified are materials, nondestructive tests, structures, shapes, shells, flanges, etc. for the vessels and the pipes, and so on. (Mori, K.)

78 FR 16698 - Chemical Facility Anti-Terrorism Standards (CFATS) Chemical-Terrorism Vulnerability Information...

Science.gov (United States)

2013-03-18

... DEPARTMENT OF HOMELAND SECURITY [Docket No. DHS-2012-0057] Chemical Facility Anti-Terrorism Standards (CFATS) Chemical- Terrorism Vulnerability Information (CVI) AGENCY: National Protection and... notice is also soliciting comments concerning the Information Collection Request, Chemical Facility Anti...

Development of Irradiation Procedure for Gamma Irradiation Chamber Bio beam GM 8000

International Nuclear Information System (INIS)

Shuhaimi Shamsudin; Affrida Abu Hassan; Zaiton Ahmad; Abdul Rahim Harun; Ahmad Zainuri Mohd Dzomir

2015-01-01

Bio Beam GM 8000 gamma irradiation chamber obtained a conditional approval to operate on March 27, 2012, and later acquired a full approval on December 13, 2012. The objective for the procurement of this gamma chamber is to develop an acute irradiation facility for biological samples, including plants tissues, insects, pupae, microorganisms, as well as animal and human cells. To ensure a smooth and efficient operation, irradiation procedures were developed and improved over time. This paper discusses the operation and management of the Bio Beam GM 8000 facility, including irradiation procedures and sample preparation, application for services through online e-client system, consultancy, quality assurance and information dissemination to internal as well as external clients. In addition, this paper also discusses the potential, constraints and improvement measures taken to optimize the use of this facility in order to meet its objectives. (author)

A theoretical and experimental dose rate study at a multipurpose gamma irradiation facility in Ghana

International Nuclear Information System (INIS)

Sackey, Tracey A.

2015-01-01

Radiation dose rate monitoring out at the Radiation Technology Centre (RTC) of the Ghana Atomic Energy Commission (GAEC) to establish the safety or otherwise of staff at the occupied areas is presented. The facility operates a rectangular source of Co-60 gamma with an having activity of 27.4kCi as at March 2015 and has 14 workers. The aim of the research was determine by means of practical and theoretical evaluations shielding effectiveness of the irradiation chamber. This was to ensure that occupationally exposed workers are not over exposed or their exposures do not exceed the regulatory limits of 7.5μSv/h or 50mSv per annum. The study included dose rate measurements at controlled areas, evaluation of personnel dose history, comparison of experimental and theoretical values and determination of whether the shielding can support a. 18.5PBq (500kCi) Co-60 source. Practical dose rate measurements when the source was in the irradiation position was carried out using a Thermo Scientific Rad-Eye Gamma Survey Meter in the controlled areas of the facility which included the control room, electric room, deionizer room, on top of the roof of irradiation chamber (specifically above the roof plugs) and the two entrances to the irradiation chamber; the personnel door and the goods door. Background reading was found to be 0.08±0.01μSv/h whilst the average dose rates at the two entrances to the irradiation chamber (i e.,- the personnel door and the goods door) were measured to be 0.090μSv/h and 0.109μSv/h respectively. Practical measurements at the roof plugs produced average values of 0.135μSv/h. A particular point on the roof marked as plug-3 produced a relatively higher dose rate of 8.151μSv/h due probably to leakage along the cable to the drive motor. Measurements in the control room, electrical room and deionizer room had average readings of 0.116μSv/h, 0.089μSv/h and 0.614μSv/h respectively. All these average values were below the regulatory limits of 7.5�

Standardization of 40Ar-39Ar dating facility at KDMIPE, ONGC, Dehradun

International Nuclear Information System (INIS)

Rathore, S.S.; Singh, M.P.; Vijan, A.R.; Bansal, M.; Prabhu, B.N.; Misra, K.N.

2003-01-01

In the pursuit of acquiring state of the art technology, efforts were being made for last more than two years to establish 40 Ar- 39 Ar dating facility at KDMIPE. The 40 Ar- 39 Ar dating technique is an analytical conversion of the conventional K-Ar dating method. In this method, the sample to be dated is first irradiated in a nuclear reactor to transform a portion of 39 K to 39 Ar by the fast neutron reaction i.e. 39 K(n, p) 39 Ar. After irradiation, the sample is placed in an ultra-high vacuum system and the argon extracted from it by fusion is purified and analyzed isotopically in a mass spectrometer. The relative abundances of 40 Ar, 39 Ar, 37 Ar and 36 Ar are measured. The 40 Ar/ 39 Ar K is determined, where 40 Ar is the radiogenic argon, and 39 Ar K is the 39 Ar produced from 39 K during the irradiation. The 40 Ar/ 39 Ar K ratio is proportional to the 40 Ar/ 40 K ratio in the sample and, therefore, is proportional to age

Improvement of plant parameters of the ROBO gamma irradiation facility due to design modification

International Nuclear Information System (INIS)

Moussa, A.; Othman, I.; Chu, R.

1999-01-01

Two industrial scale, ROBO type Co 60 gamma irradiation facilities have recently been put into operation in Syria and Peru, and the dosimetry commissioning of both plants have been carried out to determine dose distribution with products and to calculate plant parameters such as efficiency, dose uniformity ratio and throughput. There are some design modifications between the two plants in connection with the location of the carriers with respect to the source plaque and also to each other. The effect of these construction modifications on the plant parameters is discussed in the analysis of the dose distribution data measured in the carriers with depth and height among the four irradiation rows on both sides of the source plaque. The plant parameters were also calculated and measured results were compared to each other. (author)

Nuclear data needs for neutron spectrum tailoring at International Fusion Materials Irradiation Facility (IFMIF)

International Nuclear Information System (INIS)

Sugimoto, Masayoshi

2001-01-01

International Fusion Materials Irradiation Facility (IFMIF) is a proposal of D-Li intense neutron source to cover all aspects of the fusion materials development in the framework of IEA collaboration. The new activity has been started to qualifying the important technical issues called Key Element technology Phase since 2000. Although the neutron spectrum can be adjusted by changing the incident beam energy, it is favorable to be carried out many irradiation tasks at the same time under the unique beam condition. For designing the tailored neutron spectrum, neutron nuclear data for the moderator-reflector materials up to 50 MeV are required. The data for estimating the induced radioactivity is also required to keep the radiation level low enough at maintenance time. The candidate materials and the required accuracy of nuclear data are summarized. (author)

Nuclear data needs for neutron spectrum tailoring at International Fusion Materials Irradiation Facility (IFMIF)

Energy Technology Data Exchange (ETDEWEB)

Sugimoto, Masayoshi [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

2001-03-01

International Fusion Materials Irradiation Facility (IFMIF) is a proposal of D-Li intense neutron source to cover all aspects of the fusion materials development in the framework of IEA collaboration. The new activity has been started to qualifying the important technical issues called Key Element technology Phase since 2000. Although the neutron spectrum can be adjusted by changing the incident beam energy, it is favorable to be carried out many irradiation tasks at the same time under the unique beam condition. For designing the tailored neutron spectrum, neutron nuclear data for the moderator-reflector materials up to 50 MeV are required. The data for estimating the induced radioactivity is also required to keep the radiation level low enough at maintenance time. The candidate materials and the required accuracy of nuclear data are summarized. (author)

Development of Pneumatic Transfer Irradiation Facility (PTS no.1) for Neutron Activation Analysis at HANARO Research Reactor

Energy Technology Data Exchange (ETDEWEB)

Chung, Y. S.; Moon, J. H.; Kim, S. H.; Sun, G. M.; Baek, S. Y.; Kim, H. R.; Kim, Y. J

2008-03-15

A pneumatic transfer system (PTS) is one of the most important facilities used during neutron irradiation of a target material for instrumental neutron activation analysis (INAA) in a research reactor. In particular, a fast pneumatic transfer system is essential for the measurement of a short half-life nuclide and a delayed neutron counting system. The pneumatic transfer system (PTS no.1) involving a manual system and an semiautomatic system were reconstructed with new designs of a functional improvement at the HANARO research reactor in 2006. In this technical report, the conception, design, operation and control of these system (PTS no.1) was described. Also the experimental results and the characteristic parameters measured by a mock-up test, a functional operation test and an irradiation test of these systems, such as the transfer time of irradiation capsule, the different neutron flux, the temperature of the irradiation position with an irradiation time, the radiation dose rate when the rabbit is returned, etc. are reported to provide a user information as well as a reactor's management and safety.

Irradiated radiation dose measurements of multilayer mirrors and permanent magnets used at FELI facilities

International Nuclear Information System (INIS)

Wakisaka, K.; Tongu, H.; Okuma, S.; Oshita, E.; Wakita, K.; Takii, T.; Tomimasu, Takio

1997-01-01

Recently the operation time of the free electron laser (FEL) user's facilities is close on three thousand hours per year. Cavity mirrors of their optical resonators and permanent magnets of their undulators are used under high intensity radiation field along their high current electron beam lines. Among these mirrors and permanent magnets, multilayer mirrors and Nd-Fe-B permanent magnets are not so strong against radiation damage compared with Au-coated copper mirrors and Sm-Co permanent magnets. A radiation damage on Ta 2 O 5 /SiO 2 mirrors was found for the first time after about fifty hours visible FEL operation at the FELI. The damage is due to irradiated bremsstrahlung and intracavity FEL. However, radiation damages on Nd-Fe-B permanent magnets were already reported compared with Sm-Co ones using high energy neutrons, protons, deuterons and 60 Coγ-rays. Mixed irradiation effects of 85-MeV electrons, bremsstrahlung and 60 Coγ-rays and of 17-MeV electrons and 60 Coγ-rays were also studied. The latest results show that the magnetic flux loss of Nd-Fe-B is 2% at an absorbed dose of 10 MGy. The present work was carried out to study the irradiated dose distributions near the multilayer mirrors and Nd-Fe-B permanent magnets with thermoluminescence dosimeters (TLDs). The irradiated dose to the cavity mirrors used in Linac-based FEL experiment is estimated to be 0.3 MGray for fifty hours irradiation. The irradiated dose to the Nd-Fe-B magnets is estimated to be 16 MGray for 2 thousand hours operation. The decrease of their magnetic flux due to 16 MGray is estimated to be about 3%. These dose monitorings are useful to reduce irradiated dosages to the mirrors and the permanent magnets as low as possible and to estimate their safety lifetimes. (author)

International acceptance of irradiated food. Legal aspects

International Nuclear Information System (INIS)

1979-01-01

The three international organizations competent in the field of irradiation processing for the preservation of food (FAO, WHO, IAEA), convened, at the end of 1977, an Advisory Group to revise and update the recommendations of a similar group which met in early 1972. The Advisory Group considered how national regulations could be harmonized so as to facilitate the international movement of irradiated food. This publication contains the Report of the Advisory Group, which summarizes the considerations of the Group on regulatory control over the irradiation plant and irradiation of foods, and on assurances for comparability of control (international labelling and documentation). Annexes 1 to 6 are included in order to complete the relevant information on the legal aspects of this subject. They include a Draft General Standard for Irradiated Foods, a Draft Code of Practice for the Operation of Radiation Facilities Used for the Treatment of Foods, Recommendations of a Consultation Group on the Legal Aspects of Food Irradiation, a Listing of the Legislation on Food Irradiation Adopted in Member States (1971-1976), and Model Regulations for the Control of and Trade in Irradiated Food

Dosimetry standards for radiation processing

International Nuclear Information System (INIS)

Farrar, H. IV

1999-01-01

For irradiation treatments to be reproducible in the laboratory and then in the commercial environment, and for products to have certified absorbed doses, standardized dosimetry techniques are needed. This need is being satisfied by standards being developed by experts from around the world under the auspices of Subcommittee E10.01 of the American Society for Testing and Materials (ASTM). In the time period since it was formed in 1984, the subcommittee has grown to 150 members from 43 countries, representing a broad cross-section of industry, government and university interests. With cooperation from other international organizations, it has taken the combined part-time effort of all these people more than 13 years to complete 24 dosimetry standards. Four are specifically for food irradiation or agricultural applications, but the majority apply to all forms of gamma, x-ray, Bremsstrahlung and electron beam radiation processing, including dosimetry for sterilization of health care products and the radiation processing of fruits, vegetables, meats, spices, processed foods, plastics, inks, medical wastes and paper. An additional 6 standards are under development. Most of the standards provide exact procedures for using individual dosimetry systems or for characterizing various types of irradiation facilities, but one covers the selection and calibration of dosimetry systems, and another covers the treatment of uncertainties. Together, this set of standards covers essentially all aspects of dosimetry for radiation processing. The first 20 of these standards have been adopted in their present form by the International Organization of Standardization (ISO), and will be published by ISO in 1999. (author)

Characterization of the neutron sources storage pool of the Neutron Standards Laboratory, using Montecarlo Techniques

International Nuclear Information System (INIS)

Campo Blanco, X.

2015-01-01

The development of irradiation damage resistant materials is one of the most important open fields in the design of experimental facilities and conceptual nucleoelectric fusion plants. The Neutron Standards Laboratory aims to contribute to this development by allowing the neutron irradiation of materials in its calibration neutron sources storage pool. For this purposes, it is essential to characterize the pool itself in terms of neutron fluence and spectra due to the calibration neutron sources. In this work, the main features of this facility are presented and the characterization of the storage pool is carried out. Finally, an application is shown of the obtained results to the neutron irradiation of material.

Monte Carlo simulation of neutron irradiation facility developed for accelerator based in vivo neutron activation measurements in human hand bones

International Nuclear Information System (INIS)

Aslam; Prestwich, W.V.; McNeill, F.E.; Waker, A.J.

2006-01-01

The neutron irradiation facility developed at the McMaster University 3 MV Van de Graaff accelerator was employed to assess in vivo elemental content of aluminum and manganese in human hands. These measurements were carried out to monitor the long-term exposure of these potentially toxic trace elements through hand bone levels. The dose equivalent delivered to a patient during irradiation procedure is the limiting factor for IVNAA measurements. This article describes a method to estimate the average radiation dose equivalent delivered to the patient's hand during irradiation. The computational method described in this work augments the dose measurements carried out earlier [Arnold et al., 2002. Med. Phys. 29(11), 2718-2724]. This method employs the Monte Carlo simulation of hand irradiation facility using MCNP4B. Based on the estimated dose equivalents received by the patient hand, the proposed irradiation procedure for the IVNAA measurement of manganese in human hands [Arnold et al., 2002. Med. Phys. 29(11), 2718-2724] with normal (1 ppm) and elevated manganese content can be carried out with a reasonably low dose of 31 mSv to the hand. Sixty-three percent of the total dose equivalent is delivered by non-useful fast group (>10 keV); the filtration of this neutron group from the beam will further decrease the dose equivalent to the patient's hand

Review of Sodium and Plutonium related Technical Standards in Trans-Uranium Fuel Fabrication Facilities

Energy Technology Data Exchange (ETDEWEB)

Jang, Misuk; Jeon, Jong Seon; Kang, Hyun Sik; Kim, Seoung Rae [NESS, Daejeon (Korea, Republic of)

2016-10-15

In this paper, we would introduce and review technical standards related to sodium fire and plutonium criticality safety. This paper may be helpful to identify considerations in the development of equipment, standards, and etc., to meet the safety requirements in the design, construction and operating of TFFF, KAPF and SFR. The feasibility and conceptual designs are being examined on related facilities, for example, TRU Fuel Fabrication Facilities (TFFF), Korea Advanced Pyro-process Facility (KAPF), and Sodium Cooled Fast Reactor (SFR), in Korea. However, the safety concerns of these facilities have been controversial in part because of the Sodium fire accident and Plutonium related radiation safety caused by transport and handling accident. Thus, many researches have been performed to ensure safety and various documents including safety requirements have been developed. In separating and reducing the long-lived radioactive transuranic(TRU) in the spent nuclear fuel, reusing as the potential energy of uranium fuel resources and reducing the high level wastes, TFFF would be receiving the attention of many people. Thus, people would wonder whether compliance with technical standards that ensures safety. For new facility design, one of the important tasks is to review of technical standards, especially for sodium and Plutonium because of water related highly reactive characteristics and criticality hazard respectively. We have introduced and reviewed two important technical standards for TFFF, which are sodium fire and plutonium criticality safety, in this paper. This paper would provide a brief guidance, about how to start and what is important, to people who are responsible for the initial design to operation of TFFF.

Review of Sodium and Plutonium related Technical Standards in Trans-Uranium Fuel Fabrication Facilities

International Nuclear Information System (INIS)

Jang, Misuk; Jeon, Jong Seon; Kang, Hyun Sik; Kim, Seoung Rae

2016-01-01

In this paper, we would introduce and review technical standards related to sodium fire and plutonium criticality safety. This paper may be helpful to identify considerations in the development of equipment, standards, and etc., to meet the safety requirements in the design, construction and operating of TFFF, KAPF and SFR. The feasibility and conceptual designs are being examined on related facilities, for example, TRU Fuel Fabrication Facilities (TFFF), Korea Advanced Pyro-process Facility (KAPF), and Sodium Cooled Fast Reactor (SFR), in Korea. However, the safety concerns of these facilities have been controversial in part because of the Sodium fire accident and Plutonium related radiation safety caused by transport and handling accident. Thus, many researches have been performed to ensure safety and various documents including safety requirements have been developed. In separating and reducing the long-lived radioactive transuranic(TRU) in the spent nuclear fuel, reusing as the potential energy of uranium fuel resources and reducing the high level wastes, TFFF would be receiving the attention of many people. Thus, people would wonder whether compliance with technical standards that ensures safety. For new facility design, one of the important tasks is to review of technical standards, especially for sodium and Plutonium because of water related highly reactive characteristics and criticality hazard respectively. We have introduced and reviewed two important technical standards for TFFF, which are sodium fire and plutonium criticality safety, in this paper. This paper would provide a brief guidance, about how to start and what is important, to people who are responsible for the initial design to operation of TFFF

Use of the National Low-Temperature Neutron Irradiation Facility (NLTNIF) for fusion materials research

International Nuclear Information System (INIS)

Coltman, R.R. Jr.; Kerchner, H.R.; Klabunde, C.E.

1986-01-01

In May 1983 the Division of Materials Sciences, Office of Basic Energy Sciences of the Department of Energy authorized the establishment of a National Low-Temperature Neutron Irradiation Facility (NLTNIF) at ORNL's Bulk Shielding Reactor (BSR). The NLTNIF, which will be available for qualified experiments at no cost to users, will provide a combination of high radiation intensities and special environmental and testing conditions that have not been previously available in the US. Since the DOE authorization, work has proceeded on the design and construction of the new facility without interruption. This report describes the present status of the development of NLTNIF and, for the information of new candidate users, a recounting of the major specifications and capabilities is also given

Alanine-EPR dosimetry in 10 MeV electron beam to optimize process parameters for food irradiation

International Nuclear Information System (INIS)

Sanyal, B.; Kumar, S.; Kumar, M.; Mittal, K.C.; Sharma, A.

2011-01-01

Absorbed dose in a food product is determined and controlled by several components of the LINAC irradiation facility as well as the product. Standardization of the parameters characterizing the facility components, process load and the irradiation conditions collectively termed as 'process parameters' are of paramount importance for successful dose delivery to the food products. In the present study alanine-EPR dosimetry system was employed to optimize the process parameters of 10 MeV electron beam of a LINAC facility for commercial irradiation of food. Three sets of experiments were carried out with different food commodities namely, mango, potato and rawa with the available product conveying system of different irradiation geometry like one sided or both sided mode of irradiation. Three dimensional dose distributions into the process load for low dose requiring food commodities (0.25 to 1 kGy) were measured in each experiment. The actual depth dose profile in food product and useful scan width of the electron beam were found out to be satisfactory for commercial radiation processing of food. Finally a scaled up experiment with commercial food product (packets of Rawa) exhibited adequate dose uniformity ratio of 3 proving the feasibility of the facility for large scale radiation processing of food commodities. (author)

Seismic design standardization of nuclear facilities

International Nuclear Information System (INIS)

Reddy, G.R.; Vaze, K.K.

2011-01-01

Full text: Structures, Systems and Components (SSCs) of Nuclear Facilities have to be designed for normal operating loads such as dead weight, pressure, temperature etc., and accidental loads such as earthquakes, floods, extreme, wind air craft impact, explosions etc. Man made accidents such as aircraft impact, explosions etc., some times may be considered as design basis event and some times taken care by providing administrative controls. This will not be possible in the case of natural events such as earthquakes, flooding, extreme winds etc. Among natural events earthquakes are considered as most devastating and need to be considered as design basis event. It is generally felt design of SSCs for earthquake loads is very time consuming and expensive. Conventional seismic design approaches demands for large number of supports for systems and components. This results in large space occupation and in turn creates difficulties for maintenance and in service inspection of systems and components. In addition, complete exercise of design need to be repeated for plants being located at different sites due to different seismic demands. However, advanced seismic response control methods will help to standardize the seismic design meeting the safety and economy. These methods adopt passive, semi active and active devices, and base isolators to control the seismic response. In nuclear industry, it is advisable to go for passive devices to control the seismic responses. Ideally speaking, these methods will make the designs made for normal loads can also satisfy the seismic demand without calling for change in material, geometry, layout etc. in the SSCs. This paper explain the basic ideas of seismic response control methods, demonstrate the effectiveness of control methods through case studies and eventually give the procedure to be adopted for seismic design standardization of nuclear facilities

Indirect (x-ray) irradiation of encapsulated microtargets in the Iskra-5 facility

International Nuclear Information System (INIS)

Abzaev, F.M.; Bel'kov, S.A.; Bessarab, A.V.; Bondarenko, S.V.; Gaidash, V.A.; Garanin, S.G.; Dolgoleva, G.V.; Zhidkov, N.V.; Izgorodin, V.M.; Kirillov, G.A.; Kochemasov, G.G.; Litvin, D.N.; Martynenko, S.P.; Murugov, V.M.; Mkhitar'yan, L.S.; Pinegin, A.V.; Petrov, S.I.; Senik, A.V.; Suslov, N.A.; Bushuev, V.S.

1998-01-01

Experiments on the indirect (x-ray) irradiation of high-aspect-ratio capsules (with a diameter-to-thickness ratio ≅900) filled with DT gas are performed on the Iskra-5 laser facility. It is shown that all the characteristics measured (neutron yield, ion temperature, shell implosion time, etc.) are faithfully reproduced in calculations based on the one-dimensional SNDA (spectral nonequilibrium diffusion of absorption) program for nonequilibrium radiation gas dynamics. The calculations provide an explanation for the experimentally detected generation of a smaller number of neutrons in an experiment with a higher measured value for the ion temperature of DT gas

A study of the multigap RPC at the gamma irradiation facility at CERN

International Nuclear Information System (INIS)

Akindinov, A.; Alici, A.; Anselmo, F.; Antonioli, P.; Baek, Y.; Basile, M.; Romeo, G.C.G. Cara; Cerron-Zeballos, E.; Cifarelli, L.; Cindolo, F.; Caro, A. De; Pasquale, S. De; Bartolomeo, A. Di; Girard, M.F.M. Fusco; Guida, M.; Hatzifotiadou, D.; Kisselev, S.M.; Laurenti, G.; Luvisetto, M.L.; Margotti, A.; Martemiyanov, A.N.; Morozov, S.; Nania, R.; Pesci, A.; Pierella, F.; Scioli, G.; Sellitto, S.; Smirnitski, A.V.; Valenti, G.; Vicinanza, D.; Williams, M.C.S.; Witoszynskyj, S.; Zagreev, B.V.; Zichichi, A.

2002-01-01

The selected device for the ALICE Time-of-Flight array is the Multigap Resistive Plate Chamber (MRPC). We have tested this device at the Gamma Irradiation Facility at CERN to evaluate the rate dependence. We find that the rate capability of the MRPC easily exceeds the 50 Hz/cm 2 maximum expected rate at the ALICE experiment. In addition, we have measured the power dissipated for an equivalent flux of 1.6 kHz/cm 2 of through-going muons to be 650 mW/m 2

Simulated Irradiation of Samples in HFIR for use as Possible Test Materials in the MPEX (Material Plasma Exposure Experiment) Facility

Energy Technology Data Exchange (ETDEWEB)

Ellis, Ronald James [ORNL; Rapp, Juergen [ORNL

2014-01-01

The importance of Plasma Material Interaction (PMI) is a major concern in fusion reactor design and analysis. The Material-Plasma Exposure eXperiment (MPEX) facility will explore PMI under fusion reactor plasma conditions. Samples with accumulated displacements per atom (DPA) damage produced by irradiations in the High Flux Isotope Reactor (HFIR) at Oak Ridge National Laboratory (ORNL) will be studied in the MPEX facility. The project presented in this paper involved performing assessments of the induced radioactivity and resulting radiation fields of a variety of potential fusion reactor materials. The scientific code packages MCNP and SCALE were used to simulate irradiation of the samples in HFIR; generation and depletion of nuclides in the material and the subsequent composition, activity levels, gamma radiation fields, and resultant dose rates as a function of cooling time. These state-of-the-art simulation methods were used in addressing the challenge of the MPEX project to minimize the radioactive inventory in the preparation of the samples for inclusion in the MPEX facility.

e-Learning Course on Food Irradiation

International Nuclear Information System (INIS)

Hénon, Yves

2016-01-01

Since May 2015, an online, interactive, multi-media and self-study course on Food Irradiation - Technology, Applications and Good Practices has been made available by the Food and Environmental Protection Section. This e-learning Course on Food Irradiation was initiated during a project (RAS/05/057) of the Regional Cooperative Agreement (RCA) Implementing Best Practices of Food Irradiation for Sanitary and Phytosanitary Purposes. Each module contains: • A lesson, largely based on the Manual of Good Practice in Food except for the first part (Food Irradiation) for which expanding the contents and addressing frequently asked questions seemed necessary. The latest chapters will help operators of irradiation facilities to appreciate and improve their practices. • A section called ‘Essentials’ that summarizes the key points. • A quiz to assess the knowledge acquired by the user from the course material. The quiz questions take a variety of forms: answer matching, multiple choice, true or false, picture selection, or simple calculation. Videos, Power Point presentations, pdf files and pictures enrich the contents. The course includes a glossary and approximately 80 downloadable references. These references cover safety of irradiated food, effects of irradiation on the nutritional quality of food, effects of irradiation on food microorganisms, insects and parasites, effects of irradiation on parasites, sanitary and phytosanitary applications of irradiation, packaging of irradiated food, food irradiation standards and regulations, history of food irradiation, and communication aspects.

Status and possible prospects of an international fusion materials irradiation facility

International Nuclear Information System (INIS)

Cozzani, F.

1999-01-01

Structural materials for future DT fusion power reactors will have to operate under intense neutron fields with energies up to 14 MeV and fluences in the order of 2 MW/m 2 per year. As environmental acceptability, safety considerations and economic viability will be ultimately the keys to the widespread introduction of fusion power, the development of radiation-resistant and low activation materials would contribute significantly to fusion development. For this purpose, testing of materials under irradiation conditions close to those expected in a fusion power station would require the availability, in an appropriate time framework, of an intense, high-energy neutron source. Recent advances in linear accelerator technology, in small specimens testing technology, and in the comprehension of damage phenomena, lead to the conclusion that an accelerator-based D-Li neutron source, with beam energy variability, would provide the most realistic option for a fusion materials testing facility. Under the auspices of the IEA, an international effort (EU, Japan, US, RF) to carry out the conceptual design activities (CDA) of an international fusion materials irradiation facility (IFMIF), based on the D-Li concept, have been carried out successfully. A final conceptual design report was produced at the end of 1996. A phase of conceptual design evaluation (CDE), presently underway, is extending and further refining some of the conceptual design details of IFMIF. The results indicate that an IFMIF-class installation would be technically feasible and could meet its mission objectives. However, a suitable phase of Engineering Validation, to carry out some complementary R and D and prototyping, would still be needed to resolve a few key technical uncertainties before the possibility to proceed toward detailed design and construction could be explored. (orig.)

DOE standard: Integration of environment, safety, and health into facility disposition activities. Volume 1 of 2: Technical standard

International Nuclear Information System (INIS)

1998-05-01

This Department of Energy (DOE) technical standard (referred to as the Standard) provides guidance for integrating and enhancing worker, public, and environmental protection during facility disposition activities. It provides environment, safety, and health (ES and H) guidance to supplement the project management requirements and associated guidelines contained within DOE O 430.1A, Life-Cycle Asset Management (LCAM), and amplified within the corresponding implementation guides. In addition, the Standard is designed to support an Integrated Safety Management System (ISMS), consistent with the guiding principles and core functions contained in DOE P 450.4, Safety Management System Policy, and discussed in DOE G 450.4-1, Integrated Safety Management System Guide. The ISMS guiding principles represent the fundamental policies that guide the safe accomplishment of work and include: (1) line management responsibility for safety; (2) clear roles and responsibilities; (3) competence commensurate with responsibilities; (4) balanced priorities; (5) identification of safety standards and requirements; (6) hazard controls tailored to work being performed; and (7) operations authorization. This Standard specifically addresses the implementation of the above ISMS principles four through seven, as applied to facility disposition activities

77 FR 60041 - Heating, Cooling, and Lighting Standards for Bureau-Funded Dormitory Facilities

Science.gov (United States)

2012-10-02

... 1076-AF10 Heating, Cooling, and Lighting Standards for Bureau-Funded Dormitory Facilities AGENCY... confirming the interim final rule published and effective on May 24, 2012, addressing heating, cooling, and... identified in the ``School Facilities Design Handbook'' (handbook) dated March 30, 2007, respecting heating...

Future proton and mixed-field irradiation facilities with slow extraction for LHC operation phase and for LHC upgrades

CERN Document Server

Assmann, Ralph Wolfgang; Brugger, Markus; Efthymiopoulos, Ilias; Feldbaumer, Eduard; Garrido, Mar Capeans; Glaser, Maurice; Kramer, Daniel; Linssen, Lucie; Losito, Roberto; Moll, Michael; Rembser, Christoph; Silari, Marco; Thurel, Yves; Tsesmelis, Emmanuel; Vincke, Helmut; CERN. Geneva. The LHC experiments Committee; LHCC

2010-01-01

In the present proposal we present the need for improved proton and mixed-field irradiation facilities with slow beam extraction at CERN. Strong needs are expressed by both the detector and accelerator communities and concern the LHC operation era as well as the upgrades of machine and experiments. The current facilities and test areas have a number of limitations and drawbacks. Preliminary studies indicate that there are possibilities for a coherent and cost-effective approach towards improved facilities for the future. The aim of this document is to inform the LHCC and seek its recognition for the need of such facilities. In addition we would appreciate the support of the LHCC for pursuing further implementation studies at a PS East Hall location.

Near term, low cost, 14 MeV fusion neutron irradiation facility for testing the viability of fusion structural materials

Energy Technology Data Exchange (ETDEWEB)

Kulcinski, Gerald L., E-mail: glkulcin@wisc.edu [University of Wisconsin-Madison, Madison, WI (United States); Radel, Ross F. [Phoenix Nuclear Labs LLC, Monona, WI (United States); Davis, Andrew [University of Wisconsin-Madison, Madison, WI (United States)

2016-11-01

For over 50 years, engineers have been looking for an irradiation facility that can provide a fusion reactor appropriate neutron spectrum over a significant volume to test fusion reactor materials that is relatively inexpensive and can be built in a minimum of time. The 14 MeV neutron irradiation facility described here can nearly exactly duplicate the neutron spectrum typical of a DT fusion reactor first wall at damage rates of ≈4 displacements per atom and 40 appm He generated over a 2 l volume per full power year of operation. The projected cost of this multi-beam facility is estimated at ≈$20 million and it can be built in <4 years. A single-beam prototype, funded by the U.S. Department of Energy, is already being built to produce medical isotopes. The neutrons are produced by a 300 keV deuterium beam accelerated into 4 kPa (30 Torr) tritium target. The total tritium inventory is <2 g and <0.1 g of T{sub 2} is consumed per year. The core technology proposed has already been fully demonstrated, and no new plasma physics or materials innovations will be required for the test facility to become operational.

External irradiation facilities open for biological studies - progress in july 2005; Les installations d'irradiation externe accessibles aux etudes de biologie etat d'avancement juillet 2005

Energy Technology Data Exchange (ETDEWEB)

Gaillard-Lecanu, E. [CEA Fontenay aux Roses (DSV/Carmin), 92 (France); Authier, N.; Verrey, B. [CEA Valduc, Dept. Recherche sur les Materiaux Nucleaires, 21 - Is-sur-Tille (France); Bailly, I. [CEA Bruyeres le Chatel, 91 (France). Dept. de Physique Theorique et Appliquee; Baldacchino, G.; Pin, S.; Pommeret, S.; Renault, J.Ph. [CEA Saclay, Dept. de Recherche sur Etat Condense, les Atomes et les Molecules, 91 - Gif sur Yvette (France); Bordy, J.M. [CEA Saclay, Dir. de la Recherche Technologique (DRT/DETECS/LNHB/LMD), 91 - Gif sur Yvette (France); Coffigny, H. [CEA Fontenay aux Roses, Dept. de Radiobiologie et de Radiopathologie, 92 (France); Cortela, L. [CEA Grenoble, ARC-Nucleart, 38 (France); Duval, D. [CEA Saclay, Schering - CIS bio International, 91 - Gif sur Yvette (France); Leplat, J.J. [CEA Saclay (DSV/DRR/LREG), 91 - Gif sur Yvette (France); Poncy, J.L. [CEA Fontenay aux Roses (DSV/DRR/SRCA), 92 (France); Testard, I. [CEA Caen (DSV/DRR/LRO-LARIA), 14 - Caen (France); Thuret, J.Y. [CEA Saclay (DSV/DBJC/SBGM), 91 - Gif sur Yvette (France)

2005-07-01

The Life Science Division of the Atomic Energy Commission is making an inventory of the various radiation sources accessible for investigation on the biological effects of ionizing radiation. In this field, a wide range of studies is being carried out at the Life Science Division, attempting to characterize the kind of lesions with their early biological consequences (on the various cell compartments) and their late biological consequences (deterministic or stochastic effects), in relation to the radiation type and dose, especially at low doses. Several experimental models are available: plants, bacteria, eukaryotic cells from yeast up to mammalian cells and in vivo studies, mostly on rodents, in order to characterize the somatic late effects and the hereditary effects. Due to the significant cost of these facilities, also to their specific properties (nature of the radiation, dose and dose rate, possible accuracy of the irradiation at the molecular level), the closeness is no longer the only criteria for biologists to make a choice. The current evolution is to set up irradiation infrastructures combining ionizing radiation sources themselves and specific tools dedicated to biological studies: cell or molecular biology laboratories, animal facilities. The purpose, in this new frame, is to provide biologists with the most suitable facilities, and, if possible, to change these facilities according to requirements in radiobiology. In this report, the basics of interactions of ionizing radiation with biological tissues are briefly introduced, followed by a presentation of some of the facilities available for radiobiological studies especially at CEA. This panorama is not a comprehensive one, new data will be included as they advance, whether reporting existing facilities or if a new one is developed. (authors)

Evaluation of skyshine dose due to gamma-rays from a cobalt-60 irradiation facility

International Nuclear Information System (INIS)

Kanazawa, Tamotsu; Okamoto, Shinichi; Ohnishi, Tokuhiro; Tsujii, Yukio

1991-01-01

We attempted to evaluate skyshine dose due to gamma-rays from a cobalt-60 irradiation facility. As the first step, the results of measurements and calculations were compared of the skyshine dose due to gamma-rays from the cobalt-60 source of 1.45 PBq set in the No.4 irradiation room of our laboratory. Distances of measuring points from the cobalt source were in the range from 17 m to about 100 m in the site of our office. Calculation was carried out with simplified single scattering method. The calculated values of the skyshine dose were higher than the measured values. For more precise evaluation of the skyshine dose, the following factors are to be considered; the dose rate distribution on the roof above the source and the attenuation of gamma-rays by air. (author)

Probabilistic analysis of safety in industrial irradiation plants

International Nuclear Information System (INIS)

Alderete, F.; Elechosa, C.

2006-01-01

The Argentinean Nuclear Regulatory Authority is carrying out the Probabilistic Safety Analysis (PSA) of the two industrial irradiation plants existent in the country. The objective of this presentation is to show from the regulatory point of view, the advantages of applying this tool, as well as the appeared difficulties; for it will be made a brief description of the facilities, of the method and of the normative one. Both plants are multipurpose facilities classified as 'industrial irradiator category IV' (panoramic irradiator with source deposited in pool). Basically, the execution of an APS consists of the following stages: 1. Identification of initiating events. 2. Modeling of Accidental Sequences (Event Trees). 3. Analysis of Systems (Fault trees). 4. Quantification of Accidental Sequences. The argentine normative doesn't demand to these facilities the realization of an APS, however the basic standard of Radiological Safety establishes that in the design of this type of facilities in the cases that is justified, should make sure that the annual probability of occurrence of an accidental sequence and the resulting dose in a person gives as result an radiological risk inferior to the risk limit adopted as acceptance criteria. On the other hand the design standard specifies for these irradiators it demands a maximum fault rate of 10 -2 for the related components with the systems of radiological safety. In our case, the possible initiating events have been identified that carried out to not wanted situations (about people exposure, radioactive contamination). Then, for each one of the significant initiating events, the corresponding accidental sequences were modeled and the safety systems that intervene in this sequences by means of fault trees were analyzed, for then to determine the fault probabilities of the same ones. At the moment they are completing these fault trees, but the difficulty resides in the impossibility of obtaining real data of the reliability

A study of the multigap RPC at the $\\gamma$ irradiation facility at CERN

CERN Document Server

Akindinov, A; Anselmo, F; Antonioli, P; Baek, Y W; Basile, M; Cara Romeo, G; Cerron-Zeballos, E; Cifarelli, Luisa; Cindolo, F; Caro, A D; Pasquale, S D; Bartolomeo, A D; Fusco-Girard, M; Guida, M; Hatzifotiadou, D; Kisselev, S M; Laurenti, G; Luvisetto, M L; Margotti, A; Martemyanov, A N; Morozov, S; Nania, R; Pesci, A; Pierella, F; Scioli, G; Sellitto, S B; Smirnitsky, A V; Valenti, G; Vicinanza, D; Williams, M C S; Witoszynskyj, S; Zagreev, B V; Zichichi, A

2002-01-01

The selected device for the ALICE Time-of-Flight array is the Multigap Resistive Plate Chamber (MRPC). We have tested this device at the Gamma Irradiation Facility at CERN to evaluate the rate dependence. We find that the rate capability of the MRPC easily exceeds the 50 Hz/cm sup 2 maximum expected rate at the ALICE experiment. In addition, we have measured the power dissipated for an equivalent flux of 1.6 kHz/cm sup 2 of through-going muons to be 650 mW/m sup 2.

Operational and safety requirement of radiation facility

International Nuclear Information System (INIS)

Zulkafli Ghazali

2007-01-01

Gamma and electron irradiation facilities are the most common industrial sources of ionizing radiation. They have been used for medical, industrial and research purposes since the 1950s. Currently there are more than 160 gamma irradiation facilities and over 600 electron beam facilities in operation worldwide. These facilities are either used for the sterilization of medical and pharmaceutical products, the preservation of foodstuffs, polymer synthesis and modification, or the eradication of insect infestation. Irradiation with electron beam, gamma ray or ultra violet light can also destroy complex organic contaminants in both liquid and gaseous waste. EB systems are replacing traditional chemical sterilization methods in the medical supply industry. The ultra-violet curing facility, however, has found more industrial application in printing and furniture industries. Gamma and electron beam facilities produce very high dose rates during irradiation, and thus there is a potential of accidental exposure in the irradiation chamber which can be lethal within minutes. Although, the safety record of this industry has been relatively very good, there have been fatalities recorded in Italy (1975), Norway (1982), El Salvador (1989) and Israel (1990). Precautions against uncontrolled entry into irradiation chamber must therefore be taken. This is especially so in the case of gamma irradiation facilities those contain large amounts of radioactivity. If the mechanism for retracting the source is damaged, the source may remain exposed. This paper will, to certain extent, describe safety procedure and system being installed at ALURTRON, Nuclear Malaysia to eliminate accidental exposure of electron beam irradiation. (author)

Results from the CDE phase activity on neutron dosimetry for the international fusion materials irradiation facility test cell

CERN Document Server

Esposito, B; Maruccia, G; Petrizzi, L; Bignon, G; Blandin, C; Chauffriat, S; Lebrun, A; Recroix, H; Trapp, J P; Kaschuck, Y

2000-01-01

The international fusion materials irradiation facility (IFMIF) project deals with the study of an accelerator-based, deuterium-lithium source, producing high energy neutrons at sufficient intensity and irradiation volume to test samples of candidate materials for fusion energy reactors. IFMIF would also provide calibration and validation of data from fission reactor and other accelerator based irradiation tests. This paper describes the activity on neutron/gamma dosimetry (necessary for the characterization of the specimens' irradiation) performed in the frame of the IFMIF conceptual design evaluation (CDE) neutronics tasks. During the previous phase (conceptual design activity (CDA)) the multifoil activation method was proposed for the measurement of the neutron fluence and spectrum and a set of suitable foils was defined. The cross section variances and covariances of this set of foils have now been used for tests on the sensitivity of the IFMIF neutron spectrum determination to cross section uncertainties...

CONTRIBUTION OF HANARO IRRADIATION TECHNOLOGIES TO NATIONAL NUCLEAR R&D

Directory of Open Access Journals (Sweden)

KEE NAM CHOO

2014-08-01

Full Text Available HANARO is a multipurpose research reactor located at the Korea Atomic Energy Research Institute (KAERI. Since the commencement of its operation in 1995, various neutron irradiation facilities, such as rabbit irradiation facilities, fuel test loop (FTL facilities, capsule irradiation facilities, and neutron transmutation doping (NTD facilities, have been developed and actively utilized for various nuclear material irradiation tests requested by users from research institutes, universities, and industries. Most irradiation tests have been related to national R&D relevant to present nuclear power reactors such as the ageing management and safety evaluation of the components. Based on the accumulated experience as well as the sophisticated requirements of users, HANARO has recently supported national R&D projects relevant to new nuclear systems including the System-integrated Modular Advanced Reactor (SMART, research reactors, and future nuclear systems. This paper documents the current state and utilization of irradiation facilities in HANARO, and summarizes ongoing research efforts to deploy advanced irradiation technology.