International status of food irradiation

International Nuclear Information System (INIS)

Roberts, P.B.

1982-09-01

Recent international moves that are likely to result in an increasing acceptance of irradiated foods are reviewed. Particular attention is given to the activities of the FAO, WHO, Codex Alimentarius and to attitudes in the United States and the Asian-Pacific region. In 1979, the Codex Alimentarius Commission adopted a Recommended General Standard for Irradiated Food. A resume is given of a revised version of the standard that is presently under consideration. However, remaining barriers to trade in irradiated food are briefly discussed, such as legal and regulatory problems, labelling, public acceptance and economic viability

Heavy-Section Steel Irradiation Program

International Nuclear Information System (INIS)

Corwin, W.R.

1990-08-01

The primary goal of the Heavy-Section Steel Irradiation Program is to provide a thorough, quantitative assessment of the effects of neutron irradiation on the material behavior (particularly the fracture toughness properties) of typical pressure-vessel steels as they relate to light-water-reactor pressure-vessel integrity. The program includes direct continuation of irradiation studies previously conducted by the Heavy-Section Steel Technology Program augmented by enhanced examinations of the accompanying microstructural changes. Effects of specimen size; material chemistry; product form and microstructure; irradiation fluence, flux, temperature, and spectrum; and postirradiation annealing are examined on a wide range of fracture properties. Detailed statistical analyses of the fracture data on K Ic shift of high-copper welds were performed. Analysis of the first phase of irradiated crack-arrest testing on high-copper welds was completed. Final analysis and publication of the results of the second phase of the irradiation studies on stainless steel weld-overlay cladding were completed. Determinations were made of the variations in chemistry and unirradiated RT NDT of low upper-shelf weld metal from the Midland reactor. Final analyses were performed on the Charpy impact and tensile data from the Second and Third Irradiation series on low upper-shelf welds, and the report on the series was drafted. A detailed survey of existing data on microstructural models and data bases of irradiation damage was performed, and initial development of a reaction-rate-based model was completed. 40 refs., 7 figs., 4 tabs

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

Food irradiation receives international acceptance

Energy Technology Data Exchange (ETDEWEB)

Beddoes, J M [Atomic Energy of Canada Ltd., Ottawa, Ontario. Commercial Products

1982-04-01

Irradiation has advantages as a method of preserving food, especially in the Third World. The author tabulates some examples of actual use of food irradiation with dates and tonnages, and tells the story of the gradual acceptance of food irradiation by the World Health Organization, other international bodies, and the U.S. Food and Drug Administration (USFDA). At present, the joint IAEA/FAO/WHO standard permits an energy level of up to 5 MeV for gamma rays, well above the 1.3 MeV energy level of /sup 60/Co. The USFDA permits irradiation of any food up to 10 krad, and minor constituents of a diet may be irradiated up to 5 Mrad. The final hurdle to be cleared, that of economic acceptance, depends on convincing the food processing industry that the process is technically and economically efficient.

New pallet irradiation for Gammaster International

Science.gov (United States)

Möhlmann, Mr. J. H. F.

1993-07-01

State of the art technology offers many opportunities to improve production process with ionizing radiation. Also the requirements to this process become more and more stringent; who was aware of the ISO-9000 Standards? Now it is a necessary concept? Internal and external audits, in particular by Regulatory Bodies such as the FDA and DHSS/MCA, are necessary and commonplace requirements when operating in the Healthcare and Pharmaceutical sectors. Efficiency is a major requirement for industry and also for our radiation business. With all the above mentioned items in mind, Gammaster International B.V. in close cooperation with Nordion International Inc. has developed and built a new type Pallet Irradiator. In this new concept, our 22 years experience in gamma processing and the expertise gained in 10 years of operation of pallet irradiators was incorporated. For this irradiator Gammaster International designed and built a new process control console, incorporating state of the art technology such as: - A well-balanced safety system - A control panel, with status indication for all essential operating and safety parameters - Advances warning for necessary maintenance work - Automatic timer-setting control in addition to an automatic timer setting modification - Clear indication of the position of the product inside the unit and its status - Fully automatic product information generated when the product leaves the irradiation unit - Visual process control with the help of a color monitor - Incremental dose-control - Fault identification

The PHENIX experimental irradiation program

International Nuclear Information System (INIS)

Michel, P.; Courcon, P.; Coulon, P.

1985-03-01

The PHENIX experimental irradiation program represents a substancial volume of work. For example, more than forty experiments were in the core during the 33rd PHENIX irradiation cycle at the end of 1984. This program ensures the implementation, optimization and qualification of new solutions for the future developpment of French LMFBRs in three significant areas: fissile, fertile and absorber elements

Radioresistance and immunization effectiveness under internal irradiation

International Nuclear Information System (INIS)

Kal'nitskij, S.A.

1978-01-01

The effect of preliminary immunization on the radioresistance of mice to internal irradiation from incorporated 137 Cs or 90 Sr was studied, and it was found that a preliminary single immunization with bacterial vaccines had a favorable effect on the outcome of radiation injury. The present results suggested that vaccination had a very pronounced radioprotective effect and so may be used as a means of biologic protection from internal irradiation

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

ATF Neutron Irradiation Program Technical Plan

Energy Technology Data Exchange (ETDEWEB)

Geringer, J. W. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Materials Science and Technology Division; Katoh, Yutai [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Materials Science and Technology Division

2016-03-01

The Japan Atomic Energy Agency (JAEA) under the Civil Nuclear Energy Working Group (CNWG) is engaged in a cooperative research effort with the U.S. Department of Energy (DOE) to explore issues related to nuclear energy, including research on accident-tolerant fuels and materials for use in light water reactors. This work develops a draft technical plan for a neutron irradiation program on the candidate accident-tolerant fuel cladding materials and elements using the High Flux Isotope Reactor (HFIR). The research program requires the design of a detailed experiment, development of test vehicles, irradiation of test specimens, possible post-irradiation examination and characterization of irradiated materials and the shipment of irradiated materials to JAEA in Japan. This report discusses the technical plan of the experimental study.

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

Food irradiation receives international acceptance

International Nuclear Information System (INIS)

Beddoes, J.M.

1982-01-01

Irradition has advantages as a method of preserving food, especially in the Third World. The author tabulates some examples of actual use of food irradiation with dates and tonnages, and tells the story of the gradual acceptance of food irradiation by the World Health Organization, other international bodies, and the U.S. Food and Drug Administration (USFDA). At present, the joint IAEA/FAO/WHO standard permits an energy level of up to 5 MeV for gamma rays, well above the 1.3 MeV energy level of 60 Co. The USFDA permits irradiation of any food up to 10 krad, and minor constituents of a diet may be irradiated up to 5 Mrad. The final hurdle to be cleared, that of economic acceptance, depends on convincing the food processing industry that the process is technically and economically efficient

Legal aspects and international implications of food irradiation

International Nuclear Information System (INIS)

Gerard, Alain.

1977-11-01

This paper reports on the status of work on food irradiation at international level, namely the IAEA/FAO/WHO Vienna recommendations, the proposed EEC directive, and the Codex alimentarius draft standards. It then deals with the legal aspects of the subject, in particular the problems concerning definitions, controls and instructions, and finally reviews the regulations for international trade in irradiated foodstuffs. (NEA) [fr

Irradiation, annealing, and reirradiation research in the ORNL heavy-section steel irradiation program

International Nuclear Information System (INIS)

Nanstad, R.K.; Iskander, S.K.; McCabe, D.E.; Sokolov, M.A.

1997-01-01

One of the options to mitigate the effects of irradiation on reactor pressure vessels (RPV) is to thermally anneal them to restore the toughness properties that have been degraded by neutron irradiation. This paper summarizes experimental results from work performed as part of the Heavy-Section Steel Irradiation (HSSI) Program managed by Oak Ridge National Laboratory (ORNL) for the U.S. Nuclear Regulatory Commission. The HSSI Program focuses on annealing and re-embrittlement response of materials which are representative of those in commercial RPVs and which are considered to be radiation-sensitive. Experimental studies include (1) the annealing of materials in the existing inventory of previously irradiated materials, (2) reirradiation of previously irradiated/annealed materials in a collaborative program with the University of California, Santa Barbara (UCSB), (3) irradiation/annealing/reirradiation of U.S. and Russian materials in a cooperative program with the Russian Research Center-Kurchatov Institute (RRC-KI), (4) the design and fabrication of an irradiation/anneal/reirradiation capsule and facility for operation at the University of Michigan Ford Reactor, (5) the investigation of potential for irradiation-and/or thermal-induced temper embrittlement in heat-affected zones (HAZs) of RPV steels due to phosphorous segregation at grain boundaries, and (6) investigation of the relationship between Charpy impact toughness and fracture toughness under all conditions of irradiation, annealing, and reirradiation

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

DNA damage induced by radionuclide internal irradiation

International Nuclear Information System (INIS)

Cui Fengmei; Zhao Jingyong; Hong Chengjiao; Lao Qinhua; Wang Liuyi; Yang Shuqin

2004-01-01

Objective: To study the DNA damage of peripheral blood mononuclear cell (PBMC) in rats exposed to radionuclide internal irradiation. Methods: The radionuclides were injected into the rats and single cell get electrophoresis (SCGE) was performed to detect the length of DNA migration in the rat PBMC. Results: DNA migration in the rat PBMC increased with accumulative dose or dose-rate. It showed good relationship of dose vs. response and of dose-rate vs. response, both relationship could be described as linear models. Conclusion: Radionuclide internal irradiation could cause DNA damage in rat PBMC. (authors)

Internal hydriding in irradiated defected Zircaloy fuel rods: A review (LWBR Development Program)

International Nuclear Information System (INIS)

Clayton, J.C.

1987-10-01

Although not a problem in recent commercial power reactors, including the Shippingport Light Water Breeder Reactor, internal hydriding of Zircaloy cladding was a persistent cause of gross cladding failures during the 1960s. It occurred in the fuel rods of water-cooled nuclear power reactors that had a small cladding defect. This report summarizes the experimental findings, causes, mechanisms, and methods of minimizing internal hydriding in defected Zircaloy-clad fuel rods. Irradiation test data on the different types of defected fuel rods, intentionally fabricated defected and in-pile operationally defected rods, are compared. Significant factors affecting internal hydriding in defected Zircaloy-clad fuel rods (defect hole size, internal and external sources of hydrogen, Zircaloy cladding surface properties, nickel alloy contamination of Zircaloy, the effect of heat flux and fluence) are discussed. Pertinent in-pile and out-of-pile test results from Bettis and other laboratories are used as a data base in constructing a qualitative model which explains hydrogen generation and distribution in Zircaloy cladding of defected water-cooled reactor fuel rods. Techniques for minimizing internal hydride failures in Zircaloy-clad fuel rods are evaluated

International Cooperation to Establish Standard Operating Procedure (SOP) for Quarantine Management of Irradiated Foods in International Trade

International Nuclear Information System (INIS)

Lee, J. W.; Byun, M. W.; Kim, J. H.; Choi, J. I.; Song, B. S.; Yoon, Y. H.; Kim, D. H.; Kim, W. G.; Kim, K. P.

2010-02-01

· Development of SOPs through various research activities such as building international cooperation, and analysing current status of food irradiation in domestic and international markets, export and import, international market size, and of R and D - Analysis of examples for quarantine management in agricultural product exporting countries and use of irradiation technology for agricultural product quarantine, and changes in international quarantine management - Analysis of SOPs for food irradiation quarantine in international organization (CODEX, IPPC, WHO). U.S, EU, China, India, and Australia. - Collaborative researches of India/Korea and China/Korea entered into an agreement for market trials · Publishment of irradiation quarantine management SOPs agreed to CODEX standards - Collaborative researches for quarantine management, avoiding Technical Barrier to Trade (TBT), and Sanitary Phytosanitary Measures were conducted, and advanced SOPs agreed with WTO/FTA system were published

Food Irradiation. Proceedings of the International Symposium on Food Irradiation

Energy Technology Data Exchange (ETDEWEB)

NONE

1966-11-15

For some years research has been done in several countries, with the object of contributing to the world's food supplies, on the application of nuclear methods to food preservation and processing. The importance of food preservation is of particular relevance in certain regions of the world where up to thirty per cent of harvested foodstuffs are being lost because of damage by animal pests and microorganisms. A series of international meetings have been held on this subject; the first, held in 1958 at Harwell, was followed by further meetings in 1960 in Paris and in 1961 in Brussels. The International Symposium on Food Irradiation organized by the International Atomic Energy Agency and the Food and Agriculture Organization of the United Nations through their Joint Division of Atomic Energy in Agriculture, and held at the Karlsruhe Nuclear Research Centre, Karlsruhe, from 6 to 10 June 1966, at the generous invitation of the Government of the Federal Republic of Germany, is the most recent of this series of meetings. It was held for the purpose of exchanging the most up-to-date results of research, of contributing towards co-operative efforts between Member States, and of stimulating trade in the international exchange of irradiated products between nations. Papers describing research over the past fourteen years were given by outstanding authorities; the results point to a breakthrough having been achieved in the use of ionizing radiation in food preservation, notwithstanding some problems still to be solved, such as overcoming changes in colour, flavour, odour or texture. The Symposium was attended by over 200 scientists from 25 countries and four international organizations. Sixty-nine papers were presented. It was shown that a wide variety of foodstuffs exist for which radiation could be used for three different purposes: to produce indefinitely stable products, to rid food of organisms that constitute health hazards, and to extend the normal shelf or market life

Food Irradiation. Proceedings of the International Symposium on Food Irradiation

International Nuclear Information System (INIS)

1966-01-01

For some years research has been done in several countries, with the object of contributing to the world's food supplies, on the application of nuclear methods to food preservation and processing. The importance of food preservation is of particular relevance in certain regions of the world where up to thirty per cent of harvested foodstuffs are being lost because of damage by animal pests and microorganisms. A series of international meetings have been held on this subject; the first, held in 1958 at Harwell, was followed by further meetings in 1960 in Paris and in 1961 in Brussels. The International Symposium on Food Irradiation organized by the International Atomic Energy Agency and the Food and Agriculture Organization of the United Nations through their Joint Division of Atomic Energy in Agriculture, and held at the Karlsruhe Nuclear Research Centre, Karlsruhe, from 6 to 10 June 1966, at the generous invitation of the Government of the Federal Republic of Germany, is the most recent of this series of meetings. It was held for the purpose of exchanging the most up-to-date results of research, of contributing towards co-operative efforts between Member States, and of stimulating trade in the international exchange of irradiated products between nations. Papers describing research over the past fourteen years were given by outstanding authorities; the results point to a breakthrough having been achieved in the use of ionizing radiation in food preservation, notwithstanding some problems still to be solved, such as overcoming changes in colour, flavour, odour or texture. The Symposium was attended by over 200 scientists from 25 countries and four international organizations. Sixty-nine papers were presented. It was shown that a wide variety of foodstuffs exist for which radiation could be used for three different purposes: to produce indefinitely stable products, to rid food of organisms that constitute health hazards, and to extend the normal shelf or market life

International training workshop on quality control and management of food irradiation

International Nuclear Information System (INIS)

2004-01-01

The International Training Workshop on Quality Control and Management of Food Indantrione was hold from 28-30, August, 2004 in Beijing, China and organized by Chinese Society of Nuclear Agriculture and China Isotope and Radiation Association. 10 Articles were collected in this symposium including training lectures. The contents included: international developments in food irradiation, Quality control and magement of food irradiation, industrializing development of irradiated food in China, Food irradiator and its quality management, research in setting standard for enterprise about irradiated products and etc.

International Cooperation to Establish Standard Operating Procedure (SOP) for Quarantine Management of Irradiated Foods in International Trade

Energy Technology Data Exchange (ETDEWEB)

Lee, J. W.; Byun, M. W.; Kim, J. H.; Choi, J. I.; Song, B. S.; Yoon, Y. H.; Kim, D. H.; Kim, W. G.; Kim, K. P.

2010-02-15

{center_dot} Development of SOPs through various research activities such as building international cooperation, and analysing current status of food irradiation in domestic and international markets, export and import, international market size, and of R and D - Analysis of examples for quarantine management in agricultural product exporting countries and use of irradiation technology for agricultural product quarantine, and changes in international quarantine management - Analysis of SOPs for food irradiation quarantine in international organization (CODEX, IPPC, WHO). U.S, EU, China, India, and Australia. - Collaborative researches of India/Korea and China/Korea entered into an agreement for market trials {center_dot} Publishment of irradiation quarantine management SOPs agreed to CODEX standards - Collaborative researches for quarantine management, avoiding Technical Barrier to Trade (TBT), and Sanitary Phytosanitary Measures were conducted, and advanced SOPs agreed with WTO/FTA system were published

Preliminary irradiation test results from the Yankee Atomic Electric Company reactor vessel test irradiation program

International Nuclear Information System (INIS)

Biemiller, E.C.; Fyfitch, S.; Campbell, C.A.

1993-01-01

The Yankee Atomic Electric Company test irradiation program was implemented to characterize the irradiation response of representative Yankee Rowe reactor vessel beltline plate materials and to remove uncertainties in the analysis of existing irradiation data on the Yankee Rowe reactor vessel steel. Plate materials each containing 0.24 w/o copper, but different nickel contents at 0.63 w/o and 0.19 w/o, were heat treated to simulate the Yankee vessel heat treatment (austenitized at 1800 deg F) and to simulate Regulatory Guide 1.99 database materials (austenitized at 1600 deg. F). These heat treatments produced different microstructures so the effect of microstructure on irradiation damage sensitivity could be tested. Because the nickel content of the test plates varied and the copper level was constant, the effect of nickel on irradiation embrittlement was also tested. Correlation monitor material, HSST-02, was included in the program to benchmark the Ford Nuclear Reactor (U. of Michigan Test Reactor) which had never been used for this type of irradiation program. Materials taken from plate surface locations (vs. 1/4T) were included to test whether or not the improved toughness properties of the plate surface layer, resulting from the rapid quench, is maintained after irradiation. If the improved properties are maintained, pressurized thermal shock calculations could utilize this margin. Finally, for one experiment, irradiations were conducted at two irradiation temperatures (500 deg. F and 550 deg. F) to determine the effect of irradiation temperature on embrittlement. The preliminary results of the irradiation program show an increase in T 30 shift of 69 deg. F for a decrease in irradiation temperature of 50 deg. F. The results suggest that for nickel bearing steels, the superior toughness of plate surface material is maintained after irradiation and for the copper content tested, nickel had no apparent effect on irradiation response. No apparent microstructure

The irradiation test program for transmutation in the French Phenix fast reactor

International Nuclear Information System (INIS)

Guidez, J.; Chaucheprat, P.; Fontaine, B.; Brunon, E.

2004-01-01

Put on commercial operation in July 1974, the French fast reactor Phenix reached a 100 000 hours operation time in september 2003. When the French law relative to long lived radioactive waste management was promulgated on December 1991, priority was given to Phenix to be run as a research reactor and to carry on a wide irradiation program dedicated to study transmutation of minor actinides and long-lived fission products. After a major renovation program required to extend the reactor lifetime, Phenix power buildup took place in 2003. Experimental irradiations have been loaded in the core, involving components for heterogeneous and homogeneous transmutation modes, americium targets, technetium 99 metal pins and isolated isotopes for integral cross-sections measurements. Associated post- irradiated examination programs are already underway or planned. With new experiments to be loaded in the core in 2006 the Phenix reactor remains to be a powerful tool providing an important experimental data on fast reactors and on transmutation of minor actinides and long-lived fission products, as well as it will contribute to gain further experience in the framework of the GENERATION IV International Forum. (authors)

DOE/EPA sludge irradiation technology transfer program

International Nuclear Information System (INIS)

Ahlstrom, S.B.

1980-01-01

The cesium-137 sludge irradiation program has successfully progressed through the phases of technology development and pilot plant evaluation and has entered the technology transfer phase. Initial technology transfer activities have identified a growing interest among wastewater engineers and public officials to learn more about the application of irradiation in sludge treatment. As a result, a formal technology transfer program has been developed. As a major activity of this program, it is planned that the US Department of Energy, working with the US Environmental Protection Agency, state and local governments, will support the placement of five to 10 sludge irradiators at selected wastewater treatment facilities throughout the United States. Facilities which may best benefit from this process technology are being identified. Technology transfer will be stimulated as engineers and wastewater officials become familiar with the evaluation and implementation of sludge irradiation at these sites

Heavy-Section Steel Irradiation Program

International Nuclear Information System (INIS)

Anon.

1991-01-01

In FY1990 the Heavy-Section Steel Irradiation (HSSI) Program was arranged into 8 tasks: (1) program management, (2) K Ic curve shift in high-copper welds, (3) K Ia curve shift in high-copper welds, (4) irradiation effects on cladding, (5) K Ic and K Ia curve shifts in low upper-shelf (LUS) welds, (6) irradiation effects in a commercial LUS weld, (7) microstructural analysis of irradiation effects, and (8) in-service aged material evaluations. Of particular interest are the efforts in FY1990 concerning the shifts in fracture toughness and crack arrest toughness in high-copper welds, the unirradiated examination of a LUS weld from the Midland reactor, and the continued investigation into the causes of accelerated low-temperature embrittlement recently observed in RPV support steels. In the Fifth and Sixth Irradiation Series, designed to examine the shifts and possible changes in shape in the ASME K Ic and K Ia curves for two irradiated high-copper welds, it was seen that both the lower bound and mean fracture toughness shifts were greater than those of the associated Charpy-impact energies, whereas the shifts in crack arrest toughness were comparable. The irradiation-shifted fracture toughness data fell slightly below the appropriately indexed ASME K Ic curve even when it was shifted according to Revision 2 of Regulatory Guide 1.99 including its margins. The beltline weld, which was removed from the Midland reactor, fabricated by Babcock and Wilcox, Co. using Linde 80 flux, is being examined in the Tenth Irradiation Series to establish the effects of irradiation on a commercial LUS weld. A wide variation in the unirradiated fracture properties of the Midland weld were measured with values of RT NDT ranging from -22 to 54F through its thickness. In addition, a wide range of copper content from 0.21 to 0.45 wt % was found, compared to the 0.42 wt % previously reported

Neutron irradiation experiments for fusion reactor materials through JUPITER program

International Nuclear Information System (INIS)

Abe, K.; Namba, C.; Wiffen, F.W.; Jones, R.H.

1998-01-01

A Japan-USA program of irradiation experiments for fusion research, ''JUPITER'', has been established as a 6 year program from 1995 to 2000. The goal is to study ''the dynamic behavior of fusion reactor materials and their response to variable and complex irradiation environment''. This is phase-three of the collaborative program, which follows RTNS-II program (phase-1: 1982-1986) and FFTF/MOTA program (phase-2: 1987-1994). This program is to provide a scientific basis for application of materials performance data, generated by fission reactor experiments, to anticipated fusion environments. Following the systematic study on cumulative irradiation effects, done through FFTF/MOTA program. JUPITER is emphasizing the importance of dynamic irradiation effects on materials performance in fusion systems. The irradiation experiments in this program include low activation structural materials, functional ceramics and other innovative materials. The experimental data are analyzed by theoretical modeling and computer simulation to integrate the above effects. (orig.)

Heavy-section steel irradiation program summary

International Nuclear Information System (INIS)

Corwin, W.R.; Nanstad, R.K.; Iskander, S.K.; Haggag, F.M.

1992-01-01

Since a failure of the RPV carries the potential of major contamination release and severe accident, it is imperative to safe reactor operation to understand and be able to accurately predict failure models of the vessel material. For this reason, the Heavy-Section Steel Irradiation (HSSI) Program has been established with its primary goal to provide a thorough, quantitative assessment of the effects of neutron irradiation on the material behavior, and in particular the fracture toughness properties, of typical pressure vessel steels as they relate to light-water RPVs. The program includes the direct continuation of irradiation studies previously conducted within the Heavy-Section Steel Technology Program augmented by enhanced examinations of the accompanying microstructural changes. Effects of specimen size, material chemistry, product form and microstructure, irradiation fluence, flux, temperature and spectrum, and postirradiation annealing are being examined on a wide range of fracture properties including fracture toughness (K Ic and J Ic ), crack-arrest toughness (K Ia ), ductile tearing resistance (dJ/da), Charpy V-notch impact energy, dropweight nil-ductility temperature (NDT), and tensile properties. Models based on observations of radiation-induced microstructural changes using field ion and high-resolution transmission electron microscopy provide a firmer basis for extrapolating the measured changes in fracture properties to wider ranges of irradiation conditions. The principal materials examined within the HSSI Program are highcopper welds since their postirradiation properties are most frequently limiting in the continued safe operation of commercial RPVs. In addition, a limited effort will focus on stainless steel weld overlay cladding, typical of that used on the inner surface of RPVs, since its postirradiation fracture properties have the potential for strongly affecting the extension of small surface flaws during overcooling transients. (orig./GL)

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.

Internal friction in irradiated silicon

International Nuclear Information System (INIS)

Kalanov, M.U.; Pajzullakhanov, M.S.; Khajdarov, T.; Ummatov, Kh.

1999-01-01

The submicroscopic heterogeneities in mono- and polycrystal silicon and the influence of X-ray radiation on them were investigated using the ultrasound resonance method. Disk-shaped samples of 27.5 mm in diameter and 4 mm in thickness, with the flat surface parallel to crystallographic plane (111), were irradiated by X-ray beam of 1 Wt/cm 2 (50 KeV, Mo K α ) during 10 hours. Relations of internal frictions (Q -1 ) of samples and their relative attitude (ψ) - Q -1 (ψ) show that there is a presence of double-humped configuration for monocrystal silicon with the peaks at ψ=900 and 270 degrees. The relations Q -1 (ψ) remain the same after the irradiation. However, the peak width becomes larger. This data show that the configuration and attitude of the heterogeneities remain the same after the irradiation. The double-humped configuration was not discovered for the relations Q -1 (ψ) of polycrystal silicon. It is explained by the fact that there is an isotropic distribution in the content of many blocks and granules

Irradiated stainless steel material constitutive model for use in the performance evaluation of PWR pressure vessel internals

Energy Technology Data Exchange (ETDEWEB)

Rashid, J.Y.; Dunham, R.S. [ANATECH (United States); Demma, A. [Electric Power Research Institute - EPRI (United States)

2011-07-01

Demonstration of component functionality requires analytical simulations of reactor internals behavior. Towards that aim, EPRI has undertaken the development of irradiated material constitutive model and damage criteria for use in global and local finite-element based functionality analysis methodology. The constitutive behavioral regimes of irradiated stainless steel types 316 and 304 materials included in the model consist of: elastic-plastic material response considering irradiation hardening of the stress-strain curve, irradiation creep, stress relaxation, and void swelling. IASCC and degradation of ductility with irradiation are the primary damage mechanisms considered in the model. The material behavior model development consists of two parts: the first part is a user-material subroutine that can interface with a general-purpose finite element computer program to adapt it to the special-purpose of functionality analysis of reactor internals. The second part is a user utility in the form of Excel Spread sheets that permit users to extract a given property, e.g. the elastic-plastic stress-strain curve, creep curve, or void-swelling curve, as function of the relevant independent variables. The development of the model takes full advantage of the significant work that has been undertaken within EPRI's Material Reliability Program (MRP) to improve the knowledge of the material properties of irradiated stainless steels. Data from EPRI's MRP database have been utilized to develop equations that characterize the yield strength, ultimate tensile strength, uniform elongation, total elongation, reduction in area, void swelling and irradiation creep of stainless steels in a PWR environment. It is noted that, while the development of the model's equations has been statistically faithful to the material database, approximations were introduced in the model to ensure appropriate conservatism in the model's application consistently with accepted

The characteristics and mechanism of apoptosis induced by internal irradiation

International Nuclear Information System (INIS)

Hong Chengjiao; Zhang Junning; Zhu Shoupeng

2001-01-01

Apoptosis in tumor cells induced by radionuclides is likely the most effective way to cure cancer. In order to explore the possibility in clinic application, the characteristics and mechanism of apoptosis induced by internal irradiation were investigated. The apoptosis and expressions of bcl-2mRNA, bcl-2 and bax of K 562 cells following internal exposure with different accumulated absorbed doses of strontium-89 were studied. 6 h after irradiation, the characteristics of apoptosis and necrosis appeared in K 562 cells. The apoptosis and necrosis enhanced with the prolongation of internally contaminated time at 6 h, 9 h, 12 h, 24 h and 48 h. The expressions of bcl-2mRNA decreased at 12 h, most remarkably at 24 h. The expressions of bcl-2 decreased after irradiation whereas bax had no obvious changes. The results suggest that the apoptosis induced by internal exposure may be regulated by lower expressions of bcl-2mRNA and bcl-2, lower bcl-2/bax value

Food Preservation by Irradiation. Vol. II. Proceedings of an International Symposium on Food Preservation by Irradiation

International Nuclear Information System (INIS)

1978-01-01

In the task of alleviating the distress caused by the world-wide food shortage it is essential to preserve what has been grown and harvested in the fields. Clearly all suitable methods for preserving agricultural produce and food should be made use of. In this context treatment with ionizing radiation has proved its value as an environmentally clean, physical method of food preservation which is low in its energy requirement, but the volume of food being processed in this way is still low. The introduction of food irradiation on a global basis poses certain economic, legal, regulatory and health-related questions, the solution of which requires close international collaboration. Such collaboration between many international, intergovernmental and national organizations began over a decade ago. The need for dissemination and discussion of information gained through research and development work on this subject became apparent, and a number of inter-regional meetings were held. The last international symposium on the topic was held jointly by FAO and the IAEA in 1972 in Bombay. To review progress made since then, FAO and the IAEA, together with WHO, convened the present Symposium on 21-25 November 1977. It appeared timely to hold this Symposium for the following reasons: (1) Apart from significant scientific work reported in the literature, progress in other directions between 1972 and 1977 had also been made. For example, the number of food items authorized by governments, with or without restriction, had grown from 19 to 26, and the number of countries accepting one or more irradiated foods for human consumption had increased from 11 to 19. (2) Largely on the basis of the work of the International Project in the Field of Food Irradiation (Karlsruhe), already described at the Bombay Symposium, an international expert committee, jointly convened by FAO, the IAEA and WHO in August-September 1976, had made important statements on the philosophy of wholesomeness studies

Food Preservation by Irradiation. Vol. I. Proceedings of an International Symposium on Food Preservation by Irradiation

International Nuclear Information System (INIS)

1978-01-01

In the task of alleviating the distress caused by the world-wide food shortage it is essential to preserve what has been grown and harvested in the fields. Clearly all suitable methods for preserving agricultural produce and food should be made use of. In this context treatment with ionizing radiation has proved its value as an environmentally clean, physical method o f food preservation which is low in its energy requirement, but the volume of food being processed in this way is still low. The introduction o f food irradiation on a global basis poses certain economic, legal, regulatory and health-related questions, the solution o f which requires close international collaboration. Such collaboration between many international, intergovernmental and national organizations began over a decade ago. The need for dissemination and discussion o f information gained through research and development work on this subject became apparent, and a number of inter-regional meetings were held. The last international symposium on the topic was held jointly by FAO and the IAEA in 1972 in Bombay. To review progress made since then, FAO and the IAEA, together with WHO, convened the present Symposium on 21-25 November 1977. It appeared timely to hold this Symposium for the following reasons: (1) Apart from significant scientific work reported in the literature, progress in other directions between 1972 and 1977 had also been made. For example, the number of food items authorized by governments, with or without restriction, had grown from 19 to 26, and the number of countries accepting one or more irradiated foods for human consumption had increased from 11 to 19. (2) Largely on the basis of the work of the International Project in the Field of Food Irradiation (Karlsruhe), already described at the Bombay Symposium, an international expert committee, jointly convened by FAO, the IAEA and WHO in August-September 1976, had made important statements on the philosophy of wholesomeness

The dynamics of immunologic reactions in rats affected by repeated external γ-irradiation and internal irradiation with radionuclides

International Nuclear Information System (INIS)

Shubik, V.M.; Livshits, R.E.

1975-01-01

Nonspecific factors of immunity and formation of autoantibodies in rats exposed to comparable doses of repeated external γ-irradiation and of internal irradiation with Cs 137 , Sr 90 and I 131 chronically administered to animals have been studied comparatively. No essential variations have been found in changes induced in the immunologic reactions by chronic external and even internal γ-irradiation. Certain peculiarities have been revealed in the character of changes in the immunologic reactions depending on biophysical properties of the radionuclides used in the experiments

Preliminary irradiation test results from the Yankee Atomic Electric Company reactor vessel test irradiation program

International Nuclear Information System (INIS)

Biemiller, E.C.; Fyfitch, Stephen; Campbell, C.A.

1994-01-01

The Yankee Atomic Electric Company test irradiation program was implemented to characterize the irradiation response of representative Yankee Rowe reactor vessel beltline plate materials and to remove uncertainties in the analysis of existing irradiation data on the Yankee Rowe reactor vessel steel. Plate materials each containing 0.24 w/o copper, but different nickel contents at 0.63 w/o and 0.19 w/o, were heat treated to simulate the Yankee vessel heat treatment (austenitized at 982 o C (1800 o F)) and to simulate Regulatory Guide 1.99 database materials (austenitized at 871 o C (1600 o F)). These heat treatments produced different microstructures so the effect of microstructure on irradiation damage sensitivity could be tested. Because the nickel content of the test plates varied and the copper level was constant, the effect of nickel on irradiation embrittlement was also tested. Correlation monitor material, HSST-02, was included in the program to benchmark the Ford Nuclear Reactor (University of Michigan Test Reactor) which had never been used before for this type of irradiation program. Materials taken from plate surface locations (versus 1/4 T) were included to test whether or not the improved toughness properties of the plate surface layer, resulting from the rapid quench, are maintained after irradiation. If the improved properties are maintained, pressurized thermal shock calculations could utilize this margin. Finally, for one experiment, irradiations were conducted at two irradiation temperatures (260 o C and 288 o C) to determine the effect of irradiation temperature on embrittlement. (Author)

IAEA and food irradiation

International Nuclear Information System (INIS)

Machi, Sueo

1995-01-01

IAEA was founded in 1957. 122 countries take part in it. It is operated with the yearly ordinary budget of about 20 billion yen and the technical cooperation budget of about 6 billion yen and by 2200 personnel. Its two important roles are the promotion of the peaceful utilization of atomic energy and the prevention of nuclear proliferation. The activities of IAEA are shown. The cooperation with developing countries and the international research cooperation program are the important activities. The securing of foods is an urgent subject, and the utilization of radiation and isotopes has been promoted, aiming at sustaining agriculture. The necessity of food irradiation is explained, and at present, commercial food irradiation is carried out in 28 countries including Japan. The irradiation less than 10 kGy does not cause poisonous effect in any food, according to JECFI. The new international agreement is expected to be useful for promoting the international trade of irradiated foods. The international cooperation for the spread of food irradiation and the public acceptance of food irradiation are reported. (K.I.)

Heavy-Section Steel Irradiation Program

Energy Technology Data Exchange (ETDEWEB)

Rosseel, T.M.

2000-04-01

Maintaining the integrity of the reactor pressure vessel (RPV) in a light-water-cooled nuclear power plant is crucial in preventing and controlling severe accidents that have the potential for major contamination release. Because the RPV is the only key safety-related component of the plant for which a redundant backup system does not exist, it is imperative to fully understand the degree of irradiation-induced degradation of the RPV's fracture resistance that occurs during service. For this reason, the Heavy-Section Steel Irradiation (HSSI) Program has been established.

Heavy-Section Steel Irradiation Program

International Nuclear Information System (INIS)

Rosseel, T.M.

2000-01-01

Maintaining the integrity of the reactor pressure vessel (RPV) in a light-water-cooled nuclear power plant is crucial in preventing and controlling severe accidents that have the potential for major contamination release. Because the RPV is the only key safety-related component of the plant for which a redundant backup system does not exist, it is imperative to fully understand the degree of irradiation-induced degradation of the RPV's fracture resistance that occurs during service. For this reason, the Heavy-Section Steel Irradiation (HSSI) Program has been established

Segmented fuel irradiation program: investigation on advanced materials

International Nuclear Information System (INIS)

Uchida, H.; Goto, K.; Sabate, R.; Abeta, S.; Baba, T.; Matias, E. de; Alonso, J.

1999-01-01

The Segmented Fuel Irradiation Program, started in 1991, is a collaboration between the Japanese organisations Nuclear Power Engineering Corporation (NUPEC), the Kansai Electric Power Co., Inc. (KEPCO) representing other Japanese utilities, and Mitsubishi Heavy Industries, Ltd. (MHI); and the Spanish Organisations Empresa Nacional de Electricidad, S.A. (ENDESA) representing A.N. Vandellos 2, and Empresa Nacional Uranio, S.A. (ENUSA); with the collaboration of Westinghouse. The objective of the Program is to make substantial contribution to the development of advanced cladding and fuel materials for better performance at high burn-up and under operational power transients. For this Program, segmented fuel rods were selected as the most appropriate vehicle to accomplish the aforementioned objective. Thus, a large number of fuel and cladding combinations are provided while minimising the total amount of new material, at the same time, facilitating an eventual irradiation extension in a test reactor. The Program consists of three major phases: phase I: design, licensing, fabrication and characterisation of the assemblies carrying the segmented rods (1991 - 1994); phase II: base irradiation of the assemblies at Vandellos 2 NPP, and on-site examination at the end of four cycles (1994-1999). Phase III: ramp testing at the Studsvik facilities and hot cell PIE (1996-2001). The main fuel design features whose effects on fuel behaviour are being analysed are: alloy composition (MDA and ZIRLO vs. Zircaloy-4); tubing texture; pellet grain size. The Program is progressing satisfactorily as planned. The base irradiation is completed in the first quarter of 1999, and so far, tests and inspections already carried out are providing useful information on the behaviour of the new materials. Also, the Program is delivering a well characterized fuel material, irradiated in a commercial reactor, which can be further used in other fuel behaviour experiments. The paper presents the main

Combined effect of external and internal irradiation

International Nuclear Information System (INIS)

Kiradzhiev, G.

1987-01-01

Some of the general regularities of the combined effect of external irradiation and iodine 131 are discussed. Data are adduced showing that modification of the effects of these two radiation factors, when jointly applied, is also determined by the quantitative relations of the applied doses of external and internal irradiation, referred to a particular moment of the effects. It was shown that the effects of the radionuclides in these combined radiation injuries are basically realized by two mechanisms: 1. changes are found in the radionuclide kinetic parameters (nonspecific effects); 2. changes in their kinetic parameters are absent (specific effect). These two mechanisms underlie different approaches to therapy

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)

Beneficial uses program. Progress report ending December 31, 1978. [Irradiated sewage sludge

Energy Technology Data Exchange (ETDEWEB)

1979-03-01

The Beneficial Uses Program is a comprehensive program to develop the necessary technologies for cost-beneficial uses of existing and future surplus radioactive materials. The major portion of the work at Sandia is concentrated in two sub-programs: The Waste Resources Utilization Program and the Separation Technology and Source Development Program. Progress is reported on: (1) the Sandia Irradiator for Dried Sewage Sludge; (2) bacteriology; (3) mycology; (4) virology; (5) animal feeds containing irradiated sewage solids; (6) use of irradiated sewage sludge as fertilizer; and (7) development of /sup 90/Sr and /sup 137/Cs radiation sources obtained from radioactive wastes. (TFD)

Heavy-section steel irradiation program. Progress report, October 1994--March 1995

International Nuclear Information System (INIS)

Corwin, W.R.

1995-10-01

This document is the October 1994-March 1995 Progress Report for the Heavy Section Steel Irradiation Program. The report contains a summary of activities in each of the 14 tasks of the HSSI Program, including: (1) Program management, (2) Fracture toughness shifts in high-copper weldments, (3) Fracture toughness shifts in low upper-shelf welds, (4) Irradiation effects in a commercial low upper-shelf weld, (5) Irradiation effects on weld heat-affected zone and plate materials, (6) Annealing effects in low upper-shelf welds, (7) Microstructural analysis of radiation effects, (8) In-service irradiated and aged material evaluations, (9) Japanese power development reactor vessel steel examination, (10) fracture toughness curve shift method, (11) Special technical assistance, (12) Technical assistance for JCCCNRS, (13) Correlation monitor materials, and (14) Test reactor irradiation coordination. Selected papers have been indexed separately for inclusion in the Energy Science and Technology Database

Influence of electron irradiation on internal friction and structure evolution of polymer composites

International Nuclear Information System (INIS)

Ismailova, G.A.

2007-01-01

Full text: Important qualitative information on structural evolution and radiation alterations in polymer materials under the action of ionizing radiation can be obtained from the analysis of the temperature dependences of internal friction. Changing of internal friction parameters of relax maxima during irradiation is qualitative degree parameter of radiation scission-cross linking of the polymer molecules. In this work, the general phenomenological approach is realized by introduction of the effective 'observed' parameters into the simple kinetic equations. The applicability of such approach is justified by the fact that kinetics of both internal friction and scission-cross linking processes can be characterized by the same effective parameters. Temperature dependences of internal friction are experimentally studied in epoxy irradiated by 2.5 MeV pulse electron beam to different doses (D=3 MGy, 6 MGy and 9 MGy). Time dependences of internal friction characteristics associated with radiation-induced processes of polymer scission and cross-linking are analyzed and discussed. Experimental data on kinetics of structural transformations in epoxy are interpreted on the base of analytical solutions of differential equations for free radical accumulation during and after irradiation subject to the arbitrary effective order of radical recombination. It is shown that in the range of doses and dose rates under study radiation-induced scission predominates during polymer irradiation but in a certain period of time after irradiation scission changes to cross-linking. Characteristics of the kinetic curves obtained essentially depend on the dose

Worldwide status of food irradiation and the role of IAEA and other international organizations

International Nuclear Information System (INIS)

Loaharanu, P.

1988-01-01

While there has been an increasing interest in introducing irradiation for preservation and decontamination of food by national authorities and food industry, this technology has generated wide public debate in view of its perceived association with nuclear technology. The purpose of this paper is twofold: (1) to provide objectivity to the application of irradiation for food processing and (2) to project future trends of this technology. Irradiation appears to offer the most viable alternative to the existing technologies in quarantine treatment, hygienic quality of foods, reduction of food losses, and increase in market demand for fresh foods. Current limitations of food irradiation are discussed in terms of technical aspects, infrastructure and economics, consumer concerns, and harmonization of national regulations. Commercial applications have been reported in 19 countries. It is estimated that the total production of irradiated foods world-wide amounted to approximately 500,000 tons per annum. To ensure an effective implementation of the technology on a global basis, FAO and WHO have collaborated closely with the IAEA. An International Consultative Group on Food Irradiation was established under the aegis of FAO, IAEA, and WHO in May 1984. These organizations play an important role in training, technology transfer, developing guidelines on specific applications of food irradiation, international register of food irradiation facilities, acceptance and international trade in irradiated foods, and public information. (Namekawa, K.)

Worldwide status of food irradiation and the role of IAEA and other international organizations

Energy Technology Data Exchange (ETDEWEB)

Loaharanu, P.

1988-04-01

While there has been an increasing interest in introducing irradiation for preservation and decontamination of food by national authorities and food industry, this technology has generated wide public debate in view of its perceived association with nuclear technology. The purpose of this paper is twofold: (1) to provide objectivity to the application of irradiation for food processing and (2) to project future trends of this technology. Irradiation appears to offer the most viable alternative to the existing technologies in quarantine treatment, hygienic quality of foods, reduction of food losses, and increase in market demand for fresh foods. Current limitations of food irradiation are discussed in terms of technical aspects, infrastructure and economics, consumer concerns, and harmonization of national regulations. Commercial applications have been reported in 19 countries. It is estimated that the total production of irradiated foods world-wide amounted to approximately 500,000 tons per annum. To ensure an effective implementation of the technology on a global basis, FAO and WHO have collaborated closely with the IAEA. An International Consultative Group on Food Irradiation was established under the aegis of FAO, IAEA, and WHO in May 1984. These organizations play an important role in training, technology transfer, developing guidelines on specific applications of food irradiation, international register of food irradiation facilities, acceptance and international trade in irradiated foods, and public information. (Namekawa, K.).

Influence of chronic internal and acute external irradiations on the critical tissues of plants

International Nuclear Information System (INIS)

Kostyuk, O.P.; Ryasnenko, N.A.; Grodzins'kij, D.M.

1998-01-01

Peculiarities of chronic internal and acute external irradiations of the critical (as for irradiation influence) plants part, meristem, are studied. In particular, the investigation has aimed to evaluate the level of doses, accumulated by plant tissues, of the chronic internal irradiation from radiocaesium incorporated by them, and to compare its possible effect to one caused by the acute external irradiation. It is shown that the effects of both chronic and acute irradiations have similar features, and it is assumed that they have the very same mechanisms. We think that such a parameter of the plant ability to accumulate radiocaesium as the ratio of its content in a root tip and in the whole root system is a very sensible and useful criterion to estimate the irradiation influence on plants

Study by internal friction of curing low temperature irradiation defects in graphite

International Nuclear Information System (INIS)

Rouby, Dominique.

1974-01-01

Micromechanical properties and anelastic effects of neutrons irradiated graphites at 300 and 77 0 K are investigated by internal friction analysis and elasticity modulus variations. Defects created by irradiation are studied and evolution versus dose and annealing is followed [fr

Heavy-Section Steel Irradiation Program: Embrittlement issues

International Nuclear Information System (INIS)

Corwin, W.R.

1991-01-01

Maintaining the integrity of the reactor pressure vessel (RPV) in a light-water-cooled nuclear power plant is crucial in preventing and controlling severe accidents and the potential for major contamination releases. It is imperative to understand and predict the capabilities and limitations of its integrity. It is particularly vital to fully understand the degree of irradiation-induced degradation of the RPV's fracture resistance which occurs during service, since without that radiation damage it is virtually impossible to postulate a realistic scenario which would result in RPV failure. The Heavy-Section Steel Irradiation (HSSI) Program has been established by the US Nuclear Regulatory Commission (USNRC) to provide a thorough, quantitative assessment of the effects of neutron irradiation on the material behavior, and in particular the fracture toughness properties, of typical pressure vessel steels as they relate to light-water reactor pressure-vessel integrity. Results from HSSI studies provide information needed to aid in resolving major regulatory issues facing the USNRC which involve RPV irradiation embrittlement such as pressurized-thermal shock, operating pressure-temperature limits, low-temperature overpressurization, and the specialized problems associated with low upper-shelf (LUS) welds. Taken together the results of these studies also provide guidance and bases for evaluating both the aging behavior and the potential for plant life extension of light-water RPVs. The principal materials examined within the HSSI program are high-copper welds since their postirradiation properties are most frequently limiting in the continued safe operation of commercial RPVs. Embrittlement modeling studies have shown that the time or dose required for the point defect concentrations, which ultimately contribute to irradiation embrittlement, to reach their steady state values can be comparable to the component lifetime or to the duration of an irradiation experiment

Mitigating IASCC of Reactor Core Internals by Post-Irradiation Annealing

International Nuclear Information System (INIS)

Was, Gary

2017-01-01

This final report summarizes research performed during the period between September 2012 and December 2016, with the objective of establishing the effectiveness of post-irradiation annealing (PIA) as an advanced mitigation strategy for irradiation-assisted stress corrosion cracking (IASCC). This was completed by using irradiated 304SS control blade material to conduct crack initiation and crack growth rate (CGR) experiments in simulated BWR environment. The mechanism by which PIA affects IASCC susceptibility will also be verified. The success of this project will provide a foundation for the use of PIA as a mitigation strategy for core internal components in commercial reactors.

Mitigating IASCC of Reactor Core Internals by Post-Irradiation Annealing

Energy Technology Data Exchange (ETDEWEB)

Was, Gary [Univ. of Michigan, Ann Arbor, MI (United States)

2017-06-02

This final report summarizes research performed during the period between September 2012 and December 2016, with the objective of establishing the effectiveness of post-irradiation annealing (PIA) as an advanced mitigation strategy for irradiation-assisted stress corrosion cracking (IASCC). This was completed by using irradiated 304SS control blade material to conduct crack initiation and crack growth rate (CGR) experiments in simulated BWR environment. The mechanism by which PIA affects IASCC susceptibility will also be verified. The success of this project will provide a foundation for the use of PIA as a mitigation strategy for core internal components in commercial reactors.

Irradiation growth of Zircaloy (LWBR) development program

International Nuclear Information System (INIS)

Williard, H.J.

1984-01-01

Irradiation growth of recrystallized annealed (RXA) Zircaloy is divided into four stages and a model is presented to account for each stage. Stage I is a short time, low-strain transient caused by the accumulation of point defects, small interstitial loops, and vacancy clusters. Stage II is a quasi-steady-state region of relatively low strain rate during which the loops grow and intrinsic dislocations climb. Stage III is a transient during which the strain rate increases due to the production and motion of irradiation-induced dislocation lines. Stage IV is a high-strain-rate, steady-state region during which nonrecoverable strain is caused predominantly by glide of the irradiationinduced dislocations. The proposed model is based on two new mechanisms: (1) direct production of an interstitial dislocation loop accompanied by a vacancy cluster in the primary damage event, and (2) production of dislocations due to the activation of Frank-Read sources by internal stresses caused by interaction of the loops with themselves and with intrinsic (cold work) dislocations. Nonconservative, recoverable strain is due to climb of all dislocations, whereas conservative, nonrecoverable strain is caused by glide of irradiation-induced and intrinsic dislocations under the action of the internal stress. The conservative strain follows a (1-3f) texture dependence

Hanford internal dosimetry program manual

International Nuclear Information System (INIS)

Carbaugh, E.H.; Sula, M.J.; Bihl, D.E.; Aldridge, T.L.

1989-10-01

This document describes the Hanford Internal Dosimetry program. Program Services include administrating the bioassay monitoring program, evaluating and documenting assessments of internal exposure and dose, ensuring that analytical laboratories conform to requirements, selecting and applying appropriate models and procedures for evaluating internal radionuclide deposition and the resulting dose, and technically guiding and supporting Hanford contractors in matters regarding internal dosimetry. 13 refs., 16 figs., 42 tabs

Beneficial Uses Program. Progress report, period ending December 31, 1977. [Irradiated sewage sludge

Energy Technology Data Exchange (ETDEWEB)

1978-11-01

The Beneficial Uses Program is a comprehensive program to develop the necessary technologies for cost-beneficial uses of existing and future surplus radioactive materials. The major portion of the work at Sandia is concentrated in two sub-programs: the Waste Resources Utilization Program and the Separation Technology and Source Development Program. Progress is reported on: (1) the Sandia Irradiator for Dried Sewage Solids; (2) bacteriology; (3) mycology; (4) virology; (5) animal feeds containing irradiated sewage solids; (6) use of irradiated sewage sludge as fertilizer; and (7) development of /sup 90/Sr and /sup 137/Cs radiation sources obtained from radioactive wastes. (TFD)

Beneficial Uses Program. Progress report, period ending March 31, 1979. [Irradiated sewage sludge

Energy Technology Data Exchange (ETDEWEB)

1979-08-01

The Beneficial Uses Program is a comprehensive program to develop the necessary technologies for cost-beneficial uses of existing and future surplus radioactive materials. The major portion of the work at Sandia is concentrated in two sub-programs: the Waste Resources Utilization Program and the Separation Technology and Source Development Program. Progress is reported on: (1) the Sandia Irradiator for Dried Sewage Solids; (2) bacteriology; (3) mycology; (4) virology; (5) animal feeds containing irradiated sewage solids; (6) use of irradiated sewage sludge as fertilizer; and (7) development of /sup 137/Cs radiation sources obtained from radioactive wastes. (TFD)

Mathematical models in Slowpoke reactor internal irradiation site

International Nuclear Information System (INIS)

Raza, J.

2007-01-01

The main objective is to build representative mathematical models of neutron activation analysis in a Slowpoke internal irradiation site. Another significant objective is to correct various elements neutron activation analysis measured mass using these models. The neutron flux perturbation is responsible for the measured under-estimation of real masses. We supposed that neutron flux perturbation measurements taken during the Ecole Polytechnique de Montreal Slowpoke reactor first fuel loading were still valid after the second fuelling. .We also supposed that the thermal neutrons spatial and kinetic energies distributions as well as the absorption microscopic cross section dependence on the neutrons kinetic energies were important factors to satisfactorily represent neutron activation analysis results. In addition, we assumed that the neutron flux is isotropic in the laboratory system. We used experimental results from the Slowpoke reactor internal irradiation sites, in order to validate our mathematical models. Our models results are in close agreement with these experimental results..We established an accurate global mathematical correlation of the neutron flux perturbation in function of samples volumes and macroscopic neutron absorption cross sections. It is applicable to sample volumes ranging from 0,1 to 1,3 ml and macroscopic neutron absorption cross section up to 5 moles-b for seven (7) elements with atomic numbers (Z) ranging from 5 to 79. We first came up with a heuristic neutron transport mathematical semi-analytical model, in order to better understand neutrons behaviour in presence of one of several different nuclei samples volumes and mass. In order to well represent the neutron flux perturbation, we combined a neutron transport solution obtained from the spherical harmonics method of a finite cylinder and a mathematical expression combining two cylindrical harmonic functions..With the help of this model and the least squares method, we made extensive

Heavy-section steel irradiation program: Embrittlement issues

International Nuclear Information System (INIS)

Corwin, W.R.

1991-01-01

Maintaining the integrity of the reactor pressure vessel (RPV) in a light-water-cooled nuclear power plant is crucial in preventing and controlling severe accidents and the potential for major contamination releases. The RPV is one of only two major safety- related components of the plant for which a duplicate or redundant backup system does not exist. In particular, it is vital to fully understand the degree of irradiation-induced degradation of the RPV's fracture resistance which occurs during service, since without that radiation damage it is virtually impossible to postulate a realistic scenario which would result in RPV failure. For this reason, the Heavy-Section Steel Irradiation (HSSI) Program has been established by the US Nuclear Regulatory Commission (USNRC) to provide a thorough, quantitative assessment of the effects of neutron irradiation on the material behavior, and in particular the fracture toughness properties, of typical pressure vessel steels as they relate to light-water reactor pressure-vessel integrity. Effects of specimen size, material chemistry, product form and microstructure, irradiation fluence, flux, temperature and spectrum, and postirradiation annealing are being examined on a wide range of fracture properties including fracture toughness crack arrest toughness ductile tearing resistance Charpy V-notch impact energy, dropweight nil-ductility temperature and tensile properties. Models based on observations of radiation-induced microstructural changes using the field on microprobe and the high resolution transmission electron microscopy provide improved bases for extrapolating the measured changes in fracture properties to wider ranges of irradiation conditions. The principal materials examined within the HSSI program are high-copper welds since their postirradiation properties are most frequently limiting in the continued safe operation of commercial RPVs

Heavy-section steel irradiation program. Progress report, October 1992--March 1993

International Nuclear Information System (INIS)

Corwin, W.R.

1998-04-01

Maintaining the integrity of the reactor pressure vessel (RPV) in a light-water-cooled nuclear power plant is crucial in preventing and controlling severe accidents that have the potential for major contamination release. The RPV is one of only two more safety-related components of the plant for which a duplicate or redundant backup system does not exist. It is therefore imperative to understand and be able to predict the capabilities and limitations of the integrity inherent in the RPV. In particular, it is vital to fully understand the degree of irradiation-induced degradation of the RPV's fracture resistance that occurs during service. For this reason, the Heavy-Section Steel Irradiation (HSSI) Program has been established at Oak Ridge National Laboratory (ORNL) under sponsorship of the Nuclear Regulatory Commission (NRC). The primary goal of this major safety program is to provide a thorough, quantitative assessment of the effects of neutron irradiation on the material behavior (in particular, the fracture toughness properties) of typical pressure-vessel steels as they relate to light-water-reactor pressure-vessel integrity. The program centers on experimental assessments of irradiation-induced embrittlement (including the completion of certain irradiation studies previously conducted by the Heavy-Section Steel Technology Program) augmented by detailed examinations and modeling of the accompanying microstructural changes. Effects of specimen size; material chemistry; product form and microstructure; irradiation fluence, flux, temperature, and spectrum; and postirradiation annealing are being examined on a wide range of fracture properties

N-Acetyl-L-cysteine protects thyroid cells against DNA damage induced by external and internal irradiation.

Science.gov (United States)

Kurashige, Tomomi; Shimamura, Mika; Nagayama, Yuji

2017-11-01

We evaluated the effect of the antioxidant N-acetyl-L-cysteine (NAC) on the levels of reactive oxygen species (ROS), DNA double strand breaks (DSB) and micronuclei (MN) induced by internal and external irradiation using a rat thyroid cell line PCCL3. In internal irradiation experiments, ROS and DSB levels increased immediately after 131 I addition and then gradually declined, resulting in very high levels of MN at 24 and 48 h. NAC administration both pre- and also post- 131 I addition suppressed ROS, DSB and MN. In external irradiation experiments with a low dose (0.5 Gy), ROS and DSB increased shortly and could be prevented by NAC administration pre-, but not post-irradiation. In contrast, external irradiation with a high dose (5 Gy) increased ROS and DSB in a bimodal way: ROS and DSB levels increased immediately after irradiation, quickly returned to the basal levels and gradually rose again after >24 h. The second phase was in parallel with an increase in 4-hydroxy-2-nonenal. The number of MN induced by the second wave of ROS/DSB elevations was much higher than that by the first peak. In this situation, NAC administered pre- and post-irradiation comparably suppressed MN induced by a delayed ROS elevation. In conclusion, a prolonged ROS increase during internal irradiation and a delayed ROS increase after external irradiation with a high dose caused serious DNA damage, which were efficiently prevented by NAC. Thus, NAC administration even both after internal or external irradiation prevents ROS increase and eventual DNA damage.

Guidelines for dynamic international programs

International Nuclear Information System (INIS)

Gold, M.A.

1993-01-01

Matters of global concern-deforestation, global warming, biodiversity loss, sustainable development, fuelwood crises, watershed destruction, and large-scale flooding-frequently involve forests and natural resources. In the future, university students will enter a global setting that more than ever depends on a strong knowledge of international issues. USA land-grant universities are attempting to prepare students for this challenge by improving their international programs including forestry. To improve university programs, several factors will need to be addressed and are discussed, with examples, in this article: commitment of the faculty; program specialization; geographic specialization; reward systems for international contributions; international collaboration; recycled dollars within the university; active teaching programs; research; extention and outreach; language training; international faculty; travel grants; twinning relationships with sister institutions; selective in pursuit of international development assistance; and study centers. 6 refs

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

Heavy-Section Steel Irradiation Program on irradiation effects in light-water reactor pressure vessel materials

International Nuclear Information System (INIS)

Nanstad, R.K.; Corwin, W.R.; Alexander, D.J.; Haggag, F.M.; Iskander, S.K.; McCabe, D.E.; Sokolov, M.A.; Stoller, R.E.

1995-01-01

The safety of commercial light-water nuclear plants is highly dependent on the structural integrity of the reactor pressure vessel (RPV). In the absence of radiation damage to the RPV, fracture of the vessel is difficult to postulate. Exposure to high energy neutrons can result in embrittlement of radiation-sensitive RPV materials. The Heavy-Section Steel Irradiation (HSSI) Program at Oak Ridge National Laboratory, sponsored by the US Nuclear Regulatory Commission (USNRC), is assessing the effects of neutron irradiation on RPV material behavior, especially fracture toughness. The results of these and other studies are used by the USNRC in the evaluation of RPV integrity and regulation of overall nuclear plant safety. In assessing the effects of irradiation, prototypic RPV materials are characterized in the unirradiated condition and exposed to radiation under varying conditions. Mechanical property tests are conducted to provide data which can be used in the development of guidelines for structural integrity evaluations, while metallurgical examinations and mechanistic modeling are performed to improve understanding of the mechanisms responsible for embrittlement. The results of these investigations, in conjunction with results from commercial reactor surveillance programs, are used to develop a methodology for the prediction of radiation effects on RPV materials. This irradiation-induced degradation of the materials can be mitigated by thermal annealing, i.e., heating the RPV to a temperature above that of normal operation. Thus, thermal annealing and evaluation of reirradiation behavior are major tasks of the HSSI Program. This paper describes the HSSI Program activities by summarizing some past and recent results, as well as current and planned studies. 30 refs., 8 figs., 1 tab

The German carbide program: Performance, experimental findings, and evaluation of irradiation results

International Nuclear Information System (INIS)

Steiner, H.; Freund, D.; Geithoff, D.

1982-09-01

In this report a synopsis of the German carbide program is presented. The program comprises the irradiation of about 100 carbide pins equipped with pelletted fuel. Most of these fuel pins were He-bonded, the sodium bonding concept taken as a back-up solution. The main design parameters such as smear and pellet density, gap size, pin diameter and wall thickness as well as the irradiation conditions were varied mostly within wide ranges. Based on a compilation of relevant pin parameters, irradiation conditions, and the results of various irradiation experiments conclusions on the optimum ranges of the main design parameters are drawn. Furthermore, some important aspects of fuel pin behaviour are discussed based on quantitative results from post irradiation examinations. (orig.) [de

Facts about food irradiation. A series of fact sheets from the International Consultative Group on Food Irradiation

Energy Technology Data Exchange (ETDEWEB)

NONE

1991-12-01

The safety and benefits of foods processed by ionizing radiation are well documented. In an effort to provide governments, especially those of developing countries, with scientifically accurate information on issues of general interest to the public, the International Consultative Group on Food Irradiation (ICGFI), which was established under the aegis of the Food and Agriculture Organization of the United Nations (FAO), the World Health Organization (WHO), and the IAEA, decided at its 7th Annual Meeting in Rome, Italy, on October 1990, to issue a series of ''Fact Sheets'' on the subject. ICGFI, an inter-governmental body with a membership of 37 governments, has as one of its mandates the function to provide information to Member States of the FAO, WHO, and IAEA and to the three organizations themselves on the safe and proper use of food irradiation technology. The Fact Sheets included here cover issues relating to: status and trends; scientific and technical terms; food irradiation and radioactivity; chemical changes in irradiated food; nutritional quality of irradiated foods; genetic studies; microbiological safety of irradiated food; irradiation and food safety; irradiation and food additives and residues; packaging of irradiated foods; safety of irradiation facilities; controlling the process; food irradiation costs; and irradiated foods and the consumer. The Fact Sheets have been separately indexed and included in the INIS Database under Reference Numbers 23011206-23011217, 23011319 and 23012743. The Fact Sheets were first issued by the ICGFI Secretariat (Joint FAO/IAEA Division of Nuclear Techniques in Food and Agriculture, Vienna, Austria) in May 1991.

Facts about food irradiation. A series of fact sheets from the International Consultative Group on Food Irradiation

International Nuclear Information System (INIS)

1991-12-01

The safety and benefits of foods processed by ionizing radiation are well documented. In an effort to provide governments, especially those of developing countries, with scientifically accurate information on issues of general interest to the public, the International Consultative Group on Food Irradiation (ICGFI), which was established under the aegis of the Food and Agriculture Organization of the United Nations (FAO), the World Health Organization (WHO), and the IAEA, decided at its 7th Annual Meeting in Rome, Italy, on October 1990, to issue a series of ''Fact Sheets'' on the subject. ICGFI, an inter-governmental body with a membership of 37 governments, has as one of its mandates the function to provide information to Member States of the FAO, WHO, and IAEA and to the three organizations themselves on the safe and proper use of food irradiation technology. The Fact Sheets included here cover issues relating to: status and trends; scientific and technical terms; food irradiation and radioactivity; chemical changes in irradiated food; nutritional quality of irradiated foods; genetic studies; microbiological safety of irradiated food; irradiation and food safety; irradiation and food additives and residues; packaging of irradiated foods; safety of irradiation facilities; controlling the process; food irradiation costs; and irradiated foods and the consumer. The Fact Sheets have been separately indexed and included in the INIS Database under Reference Numbers 23011206-23011217, 23011319 and 23012743. The Fact Sheets were first issued by the ICGFI Secretariat (Joint FAO/IAEA Division of Nuclear Techniques in Food and Agriculture, Vienna, Austria) in May 1991

Beneficial Uses Program. Progress report for period ending June 30, 1978. [Irradiated sewage sludge

Energy Technology Data Exchange (ETDEWEB)

1979-01-01

The Beneficial Uses Program is a comprehensive program to develop the necessary technologies for cost-beneficial uses of existing and future surplus radioactive materials. The major portion of the work at Sandia is concentrated in two sub-programs: the Waste Resources Utilization Program and the Separation Technology and Source Development Program. Progress is reported on: (1) the Sandia Irradiator for Dried Sewage Solids; (2) bacteriology; (3) mycology; (4) virology; (5) animal feeds containing irradiated sewage solids; (6) use of irradiated sewage sludge as fertilizer; and (7) development of /sup 137/Cs radiation sources obtained from radioactive wastes. (TFD)

International Photovoltaic Program Plan

Energy Technology Data Exchange (ETDEWEB)

Costello, D.; Koontz, R.; Posner, D.; Heiferling, P.; Carpenter, P.; Forman, S.; Perelman, L.

1979-12-01

The International Photovoltaics Program Plan is in direct response to the Solar Photovoltaic Energy Research, Development, and Demonstration Act of 1978 (PL 95-590). As stated in the Act, the primary objective of the plan is to accelerate the widespread use of photovoltaic systems in international markets. Benefits which could result from increased international sales by US companies include: stabilization and expansion of the US photovoltaic industry, preparing the industry for supplying future domestic needs; contribution to the economic and social advancement of developing countries; reduced world demand for oil; and improvements in the US balance of trade. The plan outlines programs for photovoltaic demonstrations, systems developments, supplier assistance, information dissemination/purchaser assistance, and an informaion clearinghouse. Each program element includes tactical objectives and summaries of approaches. A program management office will be established to coordinate and manage the program plan. Although the US Department of Energy (DOE) had the lead responsibility for preparing and implementing the plan, numerous federal organizations and agencies (US Departments of Commerce, Justice, State, Treasury; Agency for International Development; ACTION; Export/Import Bank; Federal Trade Commission; Small Business Administration) were involved in the plan's preparation and implementation.

Heavy-Section Steel Irradiation Program: Volume 3, Progress report, October 1991--September 1992

International Nuclear Information System (INIS)

Corwin, W.R.

1995-02-01

The primary goal of the Heavy-Section Steel Irradiation Program is to provide a thorough, quantitative assessment of the effects of neutron irradiation on the material behavior, and in particular the fracture toughness properties, of typical pressure vessel steels as they relate to light-water reactor pressure-vessel integrity. Effects of specimen size, material chemistry, product form and microstructure, irradiation fluence, flux, temperature and spectrum, and postirradiation annealing are being examined on a wide range of fracture properties. The HSSI Program is arranged into 10 tasks: (1) program management, (2) K Ic curve shift in high-copper welds, (3) K Ia curve shift in high-copper welds, (4) irradiation effects on cladding, (5) K Ic and K Ia curve shifts in low upper-shelf welds, (6) irradiation effects in a commercial low upper-shelf weld, (7) microstructural analysis of irradiation effects, (8) in-service aged material evaluations, (9) correlation monitor materials, and (10) special technical assistance. This report provides an overview of the activities within each of these tasks from October 1991 to September 1992

Alloy development for irradiation performance: program strategy

International Nuclear Information System (INIS)

Bloom, E.E.; Stiegler, J.O.; Wiffen, F.W.; Dalder, E.N.C.; Reuther, T.C.; Gold, R.E.; Holmes, J.J.; Kummer, D.L.; Nolfi, F.V.

1978-01-01

The objective of the Alloy Development for Irradiation Performance Program is the development of structural materials for use in the first wall and blanket region of fusion reactors. The goal of the program is a material that will survive an exposure of 40 MWyr/m 2 at a temperature which will allow use of a liquid-H 2 O heat transport system. Although the ultimate aim of the program is development of materials for commercial reactors by the end of this century, activities are organized to provide materials data for the relatively low performance interim machines that will precede commercial reactors

Intense neutron irradiation facility for fusion reactor materials

Energy Technology Data Exchange (ETDEWEB)

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

1997-03-01

Technical R and D of d-Li stripping type neutron irradiation facilities for development of fusion reactor materials was carried out in Fusion Materials Irradiation Test Facility (FMIT) project and Energy Selective Neutron Irradiation Test Facility (ESNIT) program. Conceptual design activity (CDA) of International Fusion Materials Irradiation Facility (IFMIF), of which concept is an advanced version of FMIT and ESNIT concepts, are being performed. Progress of users` requirements and characteristics of irradiation fields in such neutron irradiation facilities, and outline of baseline conceptual design of IFMIF were described. (author)

Business and International Education Program

Science.gov (United States)

Office of Postsecondary Education, US Department of Education, 2012

2012-01-01

This paper presents an overview of the Business and International Education Program of the International Education Programs Service (IEPS). This program provides funds to institutions of higher education that enter into an agreement with a trade association, a business, or both for the purpose of improving business curriculum and as a means of…

The program of international intercomparison of accident dosimetry

International Nuclear Information System (INIS)

2002-06-01

The French institute of radioprotection and nuclear safety (IRSN) has carried out in June 2002 an international intercomparison program for the testing of the physical and biological accident dosimetry techniques. The intercomparison is jointly organized by the IRSN and the OECD-NEA with the sustain of the European commission and the collaboration of the CEA centre of Valduc (France). About 30 countries have participated to this program. Each country has supplied its own dosimeters and biological samples which have been irradiated using the Silene reactor of CEA-Valduc or a 60 Co source. These experiments allow to test the new dosimetric techniques that have been developed since the previous intercomparison program (1993) and to confirm or improve the performances of older techniques. Aside from the intercomparison exercise, this report makes a status of the known radiological accidents and of the effects of high doses of ionizing radiations on human health (symptoms, therapeutics). It explains the phenomenology of criticality accidents, the prevention means, and the history of such accidents up to the Tokai-Mura one in 1999. Finally, the dosimetry of criticality is presented with its physical and biological techniques. (J.S.)

Experiences of an international trade action with irradiated onions between GDR and Hungary

International Nuclear Information System (INIS)

Zachariev, G.; Kiss, I.; Luther, T.; Huebner, G.; Doellstaedt, R.

1988-01-01

Extensive work has been carried out in the field of food irradiation in the GDR and Hungary in recent years. The irradiation of onions for sprout inhibition has reached a commercial stage in the GDR of more than 5,000 tons in 1986. The export of onions is the first example of international trade in irradiated food between socialist countries. Experiences of this trade is presented in the paper. Results of quality control of the bulbs (losses in weight an quality) after an intermediate storage period are discussed. Hungarian consumer reactions to irradiated onions is also evaluated. (author)

Heavy-section steel irradiation program. Semiannual progress report, October 1996--March 1997

International Nuclear Information System (INIS)

Rosseel, T.M.

1998-02-01

Maintaining the integrity of the reactor pressure vessel (RPV) in a light-water-cooled nuclear power plant is crucial in preventing and controlling severe accidents that have the potential for major contamination release. Because the RPV is the only key safety-related component of the plant for which a redundant backup system does not exist, it is imperative to fully understand the degree of irradiation-induced degradation of the RPV's fracture resistance that occurs during service. For this reason, the Heavy-Section Steel Irradiation (HSSI) Program has been established. Its primary goal is to provide a thorough, quantitative assessment of the effects of neutron irradiation on the material behavior and, in particular, the fracture toughness properties of typical pressure-vessel steels as they relate to light-water RPV integrity. Effects of specimen size; material chemistry; product form and microstructure; irradiation fluence, flux, temperature, and spectrum; and postirradiation annealing are being examined on a wide range of fracture properties. The HSSI Program is arranged into eight tasks: (1) program management, (2) irradiation effects in engineering materials, (3) annealing, (4) microstructural analysis of radiation effects, (5) in-service irradiated and aged material evaluations, (6) fracture toughness curve shift method, (7) special technical assistance, and (8) foreign research interactions. The work is performed by the Oak Ridge National Laboratory

Internal friction measurements of Mo after low-temperature proton irradiation

International Nuclear Information System (INIS)

Tanimoto, H.; Mizubayashi, H.; Masuda, R.; Okuda, S.; Tagishi, Y.

1992-01-01

Internal friction measurements are performed in Mo after 20 MeV proton irradiation in order to clarify the behavior of self-interstitial atoms (SIA's) in Mo. In the low dose range, strong dislocation pinning suggesting the free migration of defects is observed at about 40 K and weak pinning at about 25 K. The features are very similar to those reported after neutron irradiation except that the 25 K pinning is much smaller after proton irradiation. The result suggests that the migration of free SIA's is responsible for the 40 K pinning and that of SIA-defect clusters, probably di-SIA's, formed during irradiation for the 25 K pinning. In the high dose range, the relaxation peaks are observed at about 13 and 41 K, where the close similarities are found between the present peaks and the corresponding peaks reported after neutron irradiation except that the peak height of the 41 K peak per unit concentration of Frenkel pairs (FP) tends to increase strongly with decreasing dose here. The latter fact suggests the strong interaction between SIA's. Then the smallness of the 41 K peak reported after electron irradiation with very high dose could be explained by an increased interaction between SIA's, but not by the two-dimensional migration of SIA's as proposed by Jacques and Robrock. Deformation given prior to irradiation causes a drastic decrease in the modulus defects associated with FP's (so-called bulk effect) and in the 13 K peak height. After neutron irradiation, no such effect of deformation was reported. A possible origin for this difference is discussed. (orig.)

Program of assessment of mechanical and corrosion mechanical properties of reactor internals materials due to operation conditions in WWERs

International Nuclear Information System (INIS)

Ruscak, M.; Zamboch, M.

1998-01-01

Reactor internals are subject to three principle operation influences: neutron and gamma irradiation, mechanical stresses, both static and dynamic, and coolant chemistry. Several cases of damage have been reported in previous years in both boiling and pressure water reactors. They are linked with the term of irradiation assisted stress corrosion cracking as a possible damage mechanism. In WWERs, the principal material used for reactor internals is austenitic titanium stabilized stainless steel 08Kh18N10T, however high strength steels are used as well. To assess the changes of mechanical properties and to determine whether sensitivity to intergranular cracking can be increased by high neutron fluences, the experimental program has been started. The goal is to assure safe operation of the internals as well as life management for all planned operation period. The program consists of tests of material properties, both mechanical and corrosion-mechanical. Detailed neutron fluxes calculation as well as stress and deformation calculations are part of the assessment. Model of change will be proposed in order to plan inspections of the facility. In situ measurements of internals will be used to monitor exact status of structure during operation. Tensile specimens manufactured from both base metal and model weld joint have been irradiated to the total fluences of 3-20 dpa. Changes of mechanical properties are tested by the tensile test, stress corrosion cracking tests are performed in the autoclave with water loop and active loading. Operation temperature, pressure and water chemistry are chosen for the tests. (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)

Utilization of a system of automated radiotherapy of malignant tumors using optimum programs of irradiation

International Nuclear Information System (INIS)

Pavlov, A.S.; Kostromina, K.N.; Fadeeva, M.A.

1983-01-01

The clinical experience in the implementation of optimized irradiation programs is summed up for tumors of different sites with the help of the first serial specimen of the system of automated control over irradiation - Altai-MT. The utilization of the system makes it possible to save time and avoid an error in the implementation of complex irradiation programs as well as to lower the exposure of medical personnel to radiation. Automated programs of irradiation meet the requirements of the conformity and homogeneity of a dose field within a focus of lesion, gradient conditions on the border with normal tissues, the minimization of radiation exposure in critical organs

Effects of Si3+ and H+ Irradiation on Tungsten Evaluated by Internal Friction Method

International Nuclear Information System (INIS)

Hu Jing; Wang Xianping; Fang Qianfeng; Liu Changsong; Zhang Yanwen; Zhao Ziqiang

2013-01-01

Effects of Si 3+ and H + irradiation on tungsten were investigated by internal friction (IF) technique. Scanning electron microscope (SEM) analysis revealed that sequential dual Si+H irradiation resulted in more serious damage than single Si irradiation. After irradiation, the IF background was significantly enhanced. Besides, two obvious IF peaks were initially found in temperature range of 70∼330 K in the sequential Si+H irradiated tungsten sample. The mechanism of increased IF background for the irradiated samples was suggested to originate from the high density dislocations induced by ion irradiation. On the other hand, the relaxation peak P L and non-relaxation peak P H in the Si+H irradiated sample were ascribed to the interaction process of hydrogen atoms with mobile dislocations and transient processes of hydrogen redistribution, respectively. The obtained experimental results verified the high sensitivity of IF method on the irradiation damage behaviors in nuclear materials

International Research and Studies Program

Science.gov (United States)

Office of Postsecondary Education, US Department of Education, 2012

2012-01-01

The International Research and Studies Program supports surveys, studies, and instructional materials development to improve and strengthen instruction in modern foreign languages, area studies, and other international fields. The purpose of the program is to improve and strengthen instruction in modern foreign languages, area studies and other…

Thoria-fuel irradiation. Program to irradiate 80% ThO2/20% UO2 ceramic pellets at the Savannah River Plant

International Nuclear Information System (INIS)

Pickett, J.B.

1982-02-01

This report describes the fabrication of proliferation-resistant thorium oxide/uranium oxide ceramic fuel pellets and preparations at the Savannah River Laboratory (SRL) to irradiate those materials. The materials were fabricated in order to study head end process steps (decladding, tritium removal, and dissolution) which would be required for an irradiated proliferation-resistant thorium based fuel. The thorium based materials were also to be studied to determine their ability to withstand average commercial light water reactor (LWR) irradiation conditions. This program was a portion of the Thorium Fuel Cycle Technology (TFCT) Program, and was coordinated by the Oak Ridge National Laboratory (ORNL) under the Consolidated Fuel Reprocessing Program (CFRP). The fuel materials were to be irradiated in a Savannah River Plant (SRP) reactor at conditions simulating the heat ratings and burnup of a commercial LWR. The program was terminated due to a de-emphasis of the TFCT Program, following completion of the fabrication of the fuel and the modified assemblies which were to be used in the SRP reactor. The reactor grade ceramic pellets were fabricated for SRL by Battelle, Pacific Northwest Laboratories. Five fuel types were prepared: 100% UO 2 pellets (control); 80% ThO 2 /20% UO 2 pellets; approximately 80% ThO 2 /20% UO 2 + 0.25 CaO (dissolution aid) pellets; 100% UO 2 hybrid pellets (prepared from sol-gel microspheres); and 100% ThO 2 pellets (control). All of the fuel materials were transferred to SRL from PNL and were stored pending a subsequent reactivation of the TFCT Programs

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

The future Jules Horowitz material testing reactor: An opportunity for developing international collaborations on a major European irradiation infrastructure

International Nuclear Information System (INIS)

Parrat, D.; Bignan, G.; Maugard, B.; Gonnier, C.; Blandin, C.

2015-01-01

Development process of a fuel product or a nuclear material before using at an industrial scale in a power reactor ranges from characterization of the material itself under neutronic flux up to its qualification in accidental conditions. Irradiations in Material Testing Reactors (MTRs) are in practice the basis of the whole process, in complement of prediction capabilities gained by modelling. Dedicated experimental reactors play also an important complementary role for some specific integral tests (e.g. RIA tests). Irradiations of precursors in power reactors are often limited to products which present a slight design evolution compare to the standard product or are implemented for further tests when a statistical approach is useful for defining a safety criterion. However European MTR park status is characterized by ageing infrastructures, which could cause operational issues in coming years, either on technological or on safety point of views. Moreover some specific supplies related to the public demand could be strongly affected (e.g. radiopharmaceutical targets). To avoid a lack in irradiation capacity offer at European level, CEA launched the Jules Horowitz Material Testing Reactor (JHR) international program, in the frame of a Consortium gathering also EDF (FR), AREVA (FR), European Commission (EU), SCK.CEN (BE), VTT (FI), CIEMAT (SP), STUDSVIK (SE), UJV (CZ), NNL (UK), IAEC (IL), DAE (IN) and as associated partnership: JAEA (JP). Some institutions in this list are themselves the flagship of a national Consortium. Discussions for enlarging participation are on-going with other countries, as JHR Consortium is open to new member entrance until JHR completion. The Jules Horowitz Material Testing Reactor (JHR MTR) is under construction at CEA Cadarache in southern France and will be an important international User Facility for R&D in support to the nuclear industry, research centres, regulatory bodies and TSO, and academic institutions. It represents a unique

15 years of existence of the International Consultative Group on Food Irradiation (ICGFI)

International Nuclear Information System (INIS)

Ehlermann, D.A.E.

1999-01-01

The ICGFI essentially contributed to international dissemination of unbiased information about the advantages and risks of food irradiation. The body has issued ICGFI publications containing codes of good practice for a variety of purposes, as eg. for operation of irradiation facilities for the treatment of food (GIP), or guidelines for due handling of irradiated food (GMP). Training courses have been offered to scientists, especially from developing countries, as well as for inspectors of national supervisory authorities. The activities of the advisory group as well as the conditions governing future activities are discussed. (orig./CB) [de

Irradiation Embrittlement Monitoring Programs of RPV's in the Slovak Republic NPP's

International Nuclear Information System (INIS)

Kupca, Ludovik

2006-01-01

Four types of surveillance programs were (are) realized in Slovak NPP's: 'Standard Surveillance Specimen Program' (SSSP) was finished in Jaslovske Bohunice V-2 Nuclear Power Plant (NPP) Units 3 and 4, 'Extended Surveillance Specimen Program' (ESSP), was prepared for Jaslovske Bohunice NPP V-2 with aim to validate the SSSP results, For the Mochovce NPP Unit 1 and 2 was prepared completely new surveillance program 'Modern Surveillance Specimen Program' (MSSP), based on the philosophy that the results of MSSP must be available during all NPP service life, For the Bohunice V-1 NPP was finished 'New Surveillance Specimen Program' (NSSP) coordinated by IAEA, which gave arguments for prolongation of service life these units for minimum 20 years, New Advanced Surveillance Specimen Program (ASSP) for Bohunice V-2 NPP (units 3 and 4) and Mochovce NPP (units 1, 2) is approved now. ASSP is dealing with the irradiation embrittlement of heat affected zone (HAZ) and RPV's austenitic cladding, which were not evaluated till this time in surveillance programs. SSSP started in 1979 and was finished in 1990. ESSP program started in 1995 and will be finished in 2007, was prepared with aim of: increasing of neutron fluence measurement accuracy, substantial improvement the irradiation temperature measurement, fixed orientation of samples to the centre of the reactor core, minimum differences of neutron dose for all the Charpy-V notch and COD specimens, the dose rate effect evaluation. In the year 1996 was started the new surveillance specimen program for the Mochovce RPV's unit-1 and 2, based on the fundamental postulate - to provide the irradiation embrittlement monitoring till the end of units operation. The 'New Surveillance Specimen Program' (NSSP) prepared in the year 1999 for the Bohunice V-1 NPP was finished in the year 2004. Main goal of this program was to evaluate the weld material properties degradation due to the irradiation and recovery efficiency by annealing too. The

Heavy-section steel irradiation program. Semiannual progress report, September 1993--March 1994

International Nuclear Information System (INIS)

Corwin, W.R.

1995-04-01

Maintaining the integrity of the reactor pressure vessel (RPV) in a light-water-cooled nuclear power plant is crucial in preventing and controlling severe accidents that have the potential for major contamination release. The RPV is the only component in the primary pressure boundary for which, if it should rupture, the engineering safety systems cannot assure protection from core damage. It is therefore imperative to understand and be able to predict the capabilities and limitations of the integrity inherent in the RPV. In particular, ft is vital to fully understand the degree of irradiation-induced degradation of the RPV's fracture resistance that occurs during service. The Heavy-Section Steel (HSS) Irradiation Program has been established; its primary goal is to provide a thorough, quantitative assessment of the effects of neutron irradiation on the material behavior, and in particular the fracture toughness properties of typical pressure-vessel steels, as they relate to light-water RPV integrity. The program includes the direct continuation of irradiation studies previously conducted within the HSS Technology Program augmented by enhanced examinations of the accompanying microstructural changes. During this period, the report on the duplex-type crack-arrest specimen tests from Phase 11 of the K la program was issued, and final preparations for testing the large, irradiated crack-arrest specimens from the Italian Committee for Research and Development of Nuclear Energy and Alternative Energies were completed. Tests on undersize Charpy V-notch (CVN) energy specimens in the irradiated and annealed weld 73W were completed. The results are described in detail in a draft NUREG report. In addition, the ORNL investigation of the embrittlement of the High Flux Isotope RPV indicated that an unusually large ratio of the high-energy gamma-ray flux to fast-neutron flux is most likely responsible for the apparently accelerated embrittlement

The US DOE EM international program

Energy Technology Data Exchange (ETDEWEB)

Elmetti, Rosa R.; Han, Ana M. [U.S. Department of Energy, Washington, D.C. (United States); Roach, Jay A. [Nexergy Technical, LLC., Falls Church, Virginia (United States)

2013-07-01

The U.S. Department of Energy (DOE) Office of Environmental Management (EM) conducts international collaboration activities in support of U.S. policies and objectives regarding the accelerated risk reduction and remediation of environmental legacy of the nations' nuclear weapons program and government sponsored nuclear energy research. The EM International Program supported out of the EM Office of the Associate Principal Deputy Assistant Secretary pursues collaborations with foreign government organizations, educational institutions and private industry to assist in identifying technologies and promote international collaborations that leverage resources and link international experience and expertise. In fiscal year (FY) 2012, the International Program awarded eight international collaborative projects for work scope spanning waste processing, groundwater and soil remediation, deactivation and decommissioning (D and D) and nuclear materials disposition initiatives to seven foreign organizations. Additionally, the International Program's scope and collaboration opportunities were expanded to include technical as well as non-technical areas. This paper will present an overview of the on-going tasks awarded in FY 2012 and an update of upcoming international activities and opportunities for expansion into the remainder of FY 2013 and beyond. (authors)

Coordinated irradiation plan for the Fuel Refabrication and Development Program

International Nuclear Information System (INIS)

Barner, J.O.

1979-04-01

The Department of Energy's Fuel Refabrication and Development (FRAD) Program is developing a number of proliferation-resistant fuel systems and forms for alternative use in nuclear reactors. A major portion of the program is the development of irradiation behavioral information for the fuel system/forms with the ultimate objective of qualifying the design for licensing and commercial utilization. The nuclear fuel systems under development include denatured thoria--urania fuels and spiked urania--plutonia or thoria--plutonia fuels. The fuel forms being considered include pellet fuel produced from mechanically mixed or coprecipitated feed materials, pellet fuel fabricated from partially calcined gel-derived or freeze-dried spheres (hybrid fuel) and packed-particle fuel produced from sintered gel-derived spheres (sphere-pac). This document describes the coordinated development program that will be used to test and demonstrate the irradiation performance of alternative fuels

Canadian Nuclear Safety Commission's intern program

International Nuclear Information System (INIS)

Gilmour, P.E.

2002-01-01

The Intern Program was introduced at the Canadian Nuclear Safety Commission, Canada's Nuclear Regulator in response to the current competitive market for engineers and scientists and the CNSC's aging workforce. It is an entry level staff development program designed to recruit and train new engineering and science graduates to eventually regulate Canada's nuclear industry. The program provides meaningful work experience and exposes the interns to the general work activities of the Commission. It also provides them with a broad awareness of the regulatory issues in which the CNSC is involved. The intern program is a two-year program focusing on the operational areas and, more specifically, on the generalist functions of project officers. (author)

Early radiation changes of normal dog brain following internal and external brain irradiation: A preliminary report

International Nuclear Information System (INIS)

Chin, H.; Maruyama, Y.; Markesbery, W.; Goldstein, S.; Wang, P.; Tibbs, P.; Young, B.; Feola, J.; Beach, L.

1984-01-01

To examine radiation-induced changes in the normal brain, internal or external radiation was given to normal dog brain. Seven medium-sized dogs were used in this study. Two dogs were controls and an ice-pick (plastic implant applicator) was placed in the right frontal lobe for about 5 hours but no irradiation. Two dogs underwent Cs-137 brain implantation for 4 and 5 hours, respectively using an ice-pick technique. Two dogs were given internal neutron irradiation using the same technique of intracerebral ice-pick brachytherapy. One dog received an external photon irradiation using 6-Mev Linear Accelerator. Postmortem microscopic examination was made to study the early cerebral changes to irradiation in three dogs: one control with no irradiation; one received intracerebral Cesium implantation; and one external photon irradiation. Vascular change was the most prominent microscopic finding. There were hemorrhage, endothelial proliferation and fibrinoid changes of small vessel wall. Most of the changes were localized in the white matter and the cortex remained intact. Details (CT, NMR and histological studies) are discussed

15 CFR 752.11 - Internal Control Programs.

Science.gov (United States)

2010-01-01

... 15 Commerce and Foreign Trade 2 2010-01-01 2010-01-01 false Internal Control Programs. 752.11... COMPREHENSIVE LICENSE § 752.11 Internal Control Programs. (a) Scope—(1) Introduction. It is through Internal Control Programs (ICPs) that the SCL holder and the consignee assure that exports and reexports are not...

Microstructural characterization and model of hardening for the irradiated austenitic stainless steels of the internals of pressurized water reactors; Caracterisation microstructurale et modelisation du durcissement des aciers austenitiques irradies des structures internes des reacteurs a eau pressurisee

Energy Technology Data Exchange (ETDEWEB)

Pokor, C

2003-07-01

The core internals of Pressurized Water Reactors (PWR) are composed of SA 304 stainless steel plates and CW 316 stainless steel bolts. These internals undergo a neutron flux at a temperature between 280 deg C and 380 deg C which modifies their mechanical properties. These modifications are due to the changes in the microstructure of these materials under irradiation which depend on flux, dose and irradiation temperature. We have studied, by Transmission Electron Microscopy, the microstructure of stainless steels SA 304, CW 316 and CW 316Ti irradiated in a mixed flux reactor (OSIRIS at 330 deg C between 0,8 dpa et 3,4 dpa) and in a fast breeder reactor at 330 deg C (BOR-60) up to doses of 40 dpa. Moreover, samples have been irradiated at 375 deg C in a fast breeder reactor (EBR-II) up to doses of 10 dpa. The microstructure of the irradiated stainless steels consists in faulted Frank dislocation loops in the [111] planes of austenitic, with a Burgers vector of [111]. It is possible to find some voids in the solution annealed samples irradiated at 375 deg C. The evolution of the dislocations loops and voids has been simulated with a 'cluster dynamic' model. The fit of the model parameters has allowed us to have a quantitative description of our experimental results. This description of the microstructure after irradiation was coupled together with a hardening model by Frank loops that has permitted us to make a quantitative description of the hardening of SA 304, CW 316 and CW 316Ti stainless steels after irradiation at a certain dose, flux and temperature. The irradiation doses studied grow up to 90 dpa, dose of the end of life of PWR internals. (author)

Design of an internal dosimetry program

International Nuclear Information System (INIS)

Wu, C.F.; Goff, T.E.

2004-01-01

Measurement of radiation dose is an essential element of radiation protection programs at nuclear facilities. To protect workers and demonstrate compliance with regulatory requirements, dosimetry programs must be established based on sound technical basis. Historically, external exposure was controlled by occupational dose limits. Internal exposure to radionuclides was limited by maximum permissible body burden and maximum permissible concentration. With the issuance of ICRP 26, ICRP 30, DOE Order 5480.11, DOE/EH-0256T, and the new 10 CFR 20, it has become a requirement that internal dose be assessed and the sum of internal and external doses be maintained below regulatory limits. Nuclear facilities are required to have internal dose evaluation programs adequate to demonstrate compliance with radiation protection standards (RPSs). The Waste Isolation Pilot Plant is a DOE facility designed to demonstrate safe disposal of transuranic (TRU) wastes in an ancient salt bed 2,150 feet underground. Internal dose measurement is required to support waste handling activities. This paper describes the technical basis for the WIPP Internal Dosimetry Program. (author)

Low temperature internal friction on γ-irradiated polyvinylidene fluoride (PVDF)

International Nuclear Information System (INIS)

Callens, A.; Eersels, L.; De Batist, R.

1978-01-01

A least-squares fitting of the below room temperature part of the internal friction spectra, obtained by the torsion pendulum technique on as-received and γ-irradiated (up to 1 Grad) strips and fibres of polyvinylidene fluoride by a superposition of single Debye functions, reveals that the spectral component features are determined not only by purely amorphous chain characteristics but also by the dose-dependence of crystallinity. A careful analysis of the relaxation spectra confirms that at least one relaxation effect (approximately 236 K) is created upon irradiation. The analysis of the dose dependence of the characteristics of the β (glass transition; approximately 220 K) and βsub(u) (apparent upper glass transition; approximately 270 K) relaxations, suggests the probable influence of crystallinity on the molecular motion in the amorphous phase. The increase of the intensity of the γ relaxation (approximately 190 K) is related to the irradiation-induced crystallite degradation. (author)

Internal friction study of neutron-irradiation effects on an amorphous Cu40Ti60 alloy

International Nuclear Information System (INIS)

Dong, Y.; Wu, G.; Xiao, K.; Li, X.; He, Y.

1988-01-01

Effects of neutron irradiation on the structure of an amorphous Cu 40 Ti 60 alloy have been studied by internal friction measurements. After irradiation, the position of the first internal friction peak remains almost unchanged and the shoulder position shifts towards a higher temperature by about 5 K, which indicates that the Cu 40 Ti 60 glass becomes more stable. These results are finally discussed based on the concept of changes of chemical short-range ordering and geometrical short-range ordering due to radiation damage

Super Phenix. Monitoring of structures subject to irradiation. Neutron dosimetry measurement and calculation program

International Nuclear Information System (INIS)

Cabrillat, J.C.; Arnaud, G.; Calamand, D.; Manent, G.; Tavassoli, A.A.

1984-09-01

For the Super Phenix reactor, the evolution, versus the irradiation of the mechanical properties of the core diagrid steel is the object of studies and is particularly monitored. The specimens irradiated, now in PHENIX and will be later irradiated in SUPER PHENIX as soon as the first operating cycles. An important dosimetry program coupling calculation and measurement, is parallely carried out. This paper presents the reasons, the definition of the structure, of the development and of materials used in this program of dosimetry, as also the first results of a calculation-measurement comparison [fr

A computer program (FUGI) for design and operation of a conveyor type irradiator with multi-tier and multi-layer

International Nuclear Information System (INIS)

Hoshi, Tatsuo; Aggarwal, K.S.

1976-10-01

A computer program (FUGI) was established to facilitate the determination of factors related to design and operation of a conveyor type irradiator with multi-tier and multi-layer. The factors determined by this program are as follows: (1) maximum dose, minimum dose and dose uniformity in irradiated material; (2) dose rate distribution on the path of irradiated material; (3) mass flow rate of irradiated material; (4) requisite activity of source; (5) requisite speed of conveyor; (6) utilization efficiency. This program partly uses the program FUDGE 4A for determination of dose rate in irradiated material in static state by Galanter and Krishnamurthy. (auth.)

Finite element method programs to analyze irradiation behavior of fuel pellets

International Nuclear Information System (INIS)

Yamada, Rayji; Harayama, Yasuo; Ishibashi, Akihiro; Ono, Masao.

1979-09-01

For the safety assessment of reactor fuel, it is important to grasp local changes of fuel pins due to irradiation in a reactor. Such changes of fuel result mostly from irradiation of fuel pellets. Elasto-plastic analysis programs based on the finite element method were developed to analyze these local changes. In the programs, emphasis is placed on the analysis of cracks in pellets; the interaction between cracked-pellets and cladding is not taken into consideration. The two programs developed are FEMF3 based on a two-dimensional axially symmetric model (r-z system) and FREB4 on a two-dimensional plane model (r-theta system). It is discussed in this report how the occurrence and distribution of cracks depend on heat rate of the fuel pin. (author)

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.

Heavy-Section Steel Irradiation Program. Volume 5, No. 2, Progress report, April 1994--September 1994

International Nuclear Information System (INIS)

Corwin, W.R.

1995-07-01

The Heavy-Section Steel Irradiation (HSSI) Program has been established with its primary goal to provide a thorough, quantitative assessment of the effects of neutron irradiation on the material behavior and the fracture toughness properties of typical pressure-vessel steels as they relate to light-water RPV integrity. Effects of specimen size; material chemistry; product form and microstructure; irradiation fluence, flux, temperature, and spectrum; and postirradiation annealing are being examined on a wide range of fracture properties. The HSSI Program is arranged into 14 tasks: (1) program management, (2) fracture toughness curve shift in high-copper weldments (Series 5 and 6), (3) K lc and K la curve shifts in low upper-shelf (LUS) welds (Series 8), (4) irradiation effects in a commercial LUS weld (Series 10), (5) irradiation effects on weld heat-affected zone and plate materials (Series 11), (6) annealing effects in LUS welds (Series 9), (7) microstructural and microfracture analysis of irradiation effects, (8) in-service irradiated and aged material evaluations, (9) Japan Power Development Reactor (JPDR) steel examination, (10) fracture toughness curve shift method, (11) special technical assistance, (12) technical assistance for Joint Coordinating Committee on Civilian Nuclear Reactor Safety (JCCCNRS) Working Groups 3 and 12, (13) correlation monitor materials, and (14) test reactor coordination. Progress on each task is reported

Heavy-Section Steel Irradiation Program: Progress report for April--September 1995. Volume 6, Number 2

International Nuclear Information System (INIS)

Corwin, W.R.

1996-08-01

The goal of the Heavy-Section Steel Irradiation Program is to provide a thorough, quantitative assessment of effects of neutron irradiation on material behavior, and in particular the fracture toughness properties, of typical pressure vessel steels as they relate to light-water reactor pressure-vessel integrity. Effects of specimen size, material chemistry, product form and microstructure, irradiation fluence, flux, temperature and spectrum, and post-irradiation annealing are being examined on a wide range of fracture properties. The HSSI Program is arranged into 14 tasks: (1) program management, (2) fracture toughness (K Ic ) curve shift in high-copper welds, (3) crack-arrest toughness (K Ia ) curve shift in high-copper welds, (4) irradiation effects on cladding, (5) K Ic and K Ia curve shifts in low upper-shelf welds, (6) annealing effects in low upper-shelf welds, (7) irradiation effects in a commercial low upper-shelf weld, (8) microstructural analysis of irradiation effects, (9) in-service aged material evaluations, (10) correlation monitor materials, (11) special technical assistance, (12) JPDR steel examination, (13) technical assistance for JCCCNRS Working Groups 3 and 12, and (14) additional requirements for materials. This report provides an overview of the activities within each of these task from April through September 1995

Irradiation experiments on materials for core internals, pressure vessel and fuel cladding

Energy Technology Data Exchange (ETDEWEB)

Tsukada, Takashi [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

1998-03-01

Materials degradation due to the aging phenomena is one of the key issues for the life assessment and extension of the light water reactors (LWRs). This presentation introduces JAERI`s activities in the field of LWR material researches which utilize the research and testing reactors for irradiation experiments. The activities are including the material studies for the core internals, pressure vessel and fuel cladding. These materials are exposed to the neutron/gamma radiation and high temperature water environments so that it is worth reviewing their degradation phenomena as the continuum. Three topics are presented; For the core internal materials, the irradiation assisted stress corrosion cracking (IASCC) of austenitic stainless steels is the present major concern. At JAERI the effects of alloying elements on IASCC have been investigated through the post-irradiation stress corrosion cracking tests in high-temperature water. The radiation embrittlement of pressure vessel steels is still a significant issue for LWR safety, and at JAERI some factors affecting the embrittlement behavior such as a dose rate have been investigated. Waterside corrosion of Zircaloy fuel cladding is one of the limiting factors in fuel rod performance and an in-situ measurement of the corrosion rate in high-temperature water was performed in JMTR. To improve the reliability of experiments and to extent the applicability of experimental techniques, a mutual utilization of the technical achievements in those irradiation experiments is desired. (author)

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.

Recent developments in Sandia Laboratories' sewage sludge irradiation program

International Nuclear Information System (INIS)

Sivinski, H.D.; Brandon, J.R.; Morris, M.E.; Neuhauser, K.S.; Ward, R.L.; McCaslin, B.; Smith, G.S.

1977-01-01

Pathogen reduction studies show that gamma irradiation is effective in inactivating pathogenic bacteria, parasite ova, and viruses in liquid sludges. Ammonia is shown to be virucidal to poliovirus and several other enteric viruses. Sludge processing costs are relatively economical for composted or dried sludges, but only marginally competitive with costs of heat treatment for liquid sludges. Physical and chemical studies show that effects of irradiation of sludges on dewatering properties are insignificant when compared to the effects of polymer addition. Dried, irradiated undigested sludge has significant nutritional value as a feed supplement for sheep and cattle and in agronomic uses such as greenhouses and field plots. No significant harmful effects have been demonstrated in the feeding program. Product enhancement studies are under way, including schemes for removing nitrogen from wastewaters and adding it to sludges in the form of ammonium salts

A proposal for an international program to develop dry recycle of spent nuclear fuel

International Nuclear Information System (INIS)

Feinroth, H.

1999-01-01

The dry oxidation-reduction process (called OREOX for Oxidation Reduction of Oxide Fuel) being developed by Korea and Canada, in cooperation with IAEA and the US State Department, is limited to recycle of spent LWR fuel into CANDU reactors (DUPIC). When first conceived and demonstrated via irradiation of test elements by Atomics International in 1965, (the process was called AIROX at that time) a wider range of applications was intended, including recycle of spent LWR fuel into LWRs. Studies sponsored by DOE's Idaho Office in 1992 confirmed the applicability of this technology to regions containing LWR's only, and described the potential advantages of such recycle from an environmental, waste management and economic point of view, as compared to the direct disposal option. Recent analyses conducted by the author indicates that such dry recycle may be one of the few acceptable paths remaining for resolution of the US spent fuel storage dilemma that remains consistent with US non-proliferation policy. It is proposed that a new US program be established to develop AIROX dry recycle for use in the US, and this become part of an international cooperative program, including the current Canadian - Korean program, and possibly including participation of other countries wishing to pursue alternatives to the once through cycle, and wet reprocessing. With shared funding of major project elements, such international cooperation would accelerate the demonstration and commercial deployment of dry recycle technology, as compared to separate and independent programs in each country. (author)

Estimation of irradiation temperature within the irradiation program Rheinsberg

CERN Document Server

Stephan, I; Prokert, F; Scholz, A

2003-01-01

The temperature monitoring within the irradiation programme Rheinsberg II was performed by diamond powder monitors. The method bases on the effect of temperature on the irradiation-induced increase of the diamond lattice constant. The method is described by a Russian code. In order to determine the irradiation temperature, the lattice constant is measured by means of a X-ray diffractometer after irradiation and subsequent isochronic annealing. The kink of the linearized temperature-lattice constant curves provides a value for the irradiation temperature. It has to be corrected according to the local neutron flux. The results of the lattice constant measurements show strong scatter. Furthermore there is a systematic error. The results of temperature monitoring by diamond powder are not satisfying. The most probable value lays within 255 C and 265 C and is near the value estimated from the thermal condition of the irradiation experiments.

WHO wants more use of irradiated food, calls for education programs

International Nuclear Information System (INIS)

Anon.

1989-01-01

Short note. The World Health Organization (WHO) has taken aim at critics of irradiated food, claiming that the process has the potential to reduce the incidence of foodborne diseases such as salmonellosis, to cut postharvest food losses and to provide a wider variety of foods for consumers. 'The unwarranted rejection of this process, often based on lack of understanding of what food irradiation entails, may hamper its use in those countries which may benefit most', Dr. Jean-Paul Jardel, WHO's assistant director-general, argued following a recent international conference on the subject. Critics, including Canadians, has opposed food irradiation for years, claiming that more needs to be known about its effects. WHO said the 'vast majority' of the 54 national delegations at the conference supported use of the technology on foods ranging from grain and potatoes to poultry, tropical fruit and strawberries. WHO wants governments to educate the public on the benefits and safety of irradiation because 'strange as it may seem, at least to the scientific community, this misconception (that irradiated food is radioactive) proves to be a stumbling block in general public acceptance of irradiated food'

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.

HEINBE; the calculation program for helium production in beryllium under neutron irradiation

International Nuclear Information System (INIS)

Shimakawa, Satoshi; Ishitsuka, Etsuo; Sato, Minoru

1992-11-01

HEINBE is a program on personal computer for calculating helium production in beryllium under neutron irradiation. The program can also calculate the tritium production in beryllium. Considering many nuclear reactions and their multi-step reactions, helium and tritium productions in beryllium materials irradiated at fusion reactor or fission reactor may be calculated with high accuracy. The calculation method, user's manual, calculated examples and comparison with experimental data were described. This report also describes a neutronics simulation method to generate additional data on swelling of beryllium, 3,000-15,000 appm helium range, for end-of-life of the proposed design for fusion blanket of the ITER. The calculation results indicate that helium production for beryllium sample doped lithium by 50 days irradiation in the fission reactor, such as the JMTR, could be achieved to 2,000-8,000 appm. (author)

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)

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)

Relationship between internal medicine program board examination pass rates, accreditation standards, and program size.

Science.gov (United States)

Falcone, John L; Gonzalo, Jed D

2014-01-19

To determine Internal Medicine residency program compliance with the Accreditation Council for Graduate Medical Education 80% pass-rate standard and the correlation between residency program size and performance on the American Board of Internal Medicine Certifying Examination. Using a cross-sectional study design from 2010-2012 American Board of Internal Medicine Certifying Examination data of all Internal Medicine residency pro-grams, comparisons were made between program pass rates to the Accreditation Council for Graduate Medical Education pass-rate standard. To assess the correlation between program size and performance, a Spearman's rho was calculated. To evaluate program size and its relationship to the pass-rate standard, receiver operative characteristic curves were calculated. Of 372 Internal Medicine residency programs, 276 programs (74%) achieved a pass rate of =80%, surpassing the Accreditation Council for Graduate Medical Education minimum standard. A weak correlation was found between residency program size and pass rate for the three-year period (p=0.19, pInternal Medicine residency programs complied with Accreditation Council for Graduate Medical Education pass-rate standards, a quarter of the programs failed to meet this requirement. Program size is positively but weakly associated with American Board of Internal Medicine Certifying Examination performance, suggesting other unidentified variables significantly contribute to program performance.

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.)

An international overview on the development of radurization

International Nuclear Information System (INIS)

Farkas, Jozsef

1983-01-01

A brief summary on the characteristics, applicability and limiting factors of food preservation by irradiation is given. Economic, energy and hygienic aspects of the process are outlined and the legal procedures for food irradiation process and plant licensing are treated including international aspects. Finally, the international cooperation programs and projects in the hygienic investigations, technical execution and education issues and the main trends of future development are outlined. (author)

Heavy-Section Steel Irradiation Program. Volume 2, No. 2: Semiannual progress report, April--September 1991

International Nuclear Information System (INIS)

Corwin, W.R.

1994-10-01

Goal is to provide a thorough, quantitative assessment of the effects of neutron irradiation on the material behavior, and in particular the fracture toughness properties, of typical pressure vessel stools as they relate to light-water reactor pressure-vessel integrity. Effects of specimen size, material chemistry, product form and microstructure, irradiation fluence, flux, temperature and spectrum, and post-irradiation annealing are being examined on a wide range of fracture properties. The HSSI Program is into 10 tasks: (1) program management, (2) K Ic curve shift in high-copper welds, (3) K Ia curve shift in high-copper welds, (4) irradiation effects on cladding, (5) K Ic and K Ia curve shifts in low upper-shelf welds, (6) irradiation effects in a commercial low upper-sheer weld, (7) microstructural analysis of irradiation effects, (8) in-service aged material evaluations, (9) correlation monitor materials, and (10) special technical assistance. This report provides an overview of the activities within each of these tasks from April to September 1991

Internal friction in Al alloys after neutron irradiation at low temperature

International Nuclear Information System (INIS)

Takamura, S.; Kobiyama, M.

1985-01-01

Internal friction and elastic modulus of dilute Al alloys have been measured after fast neutron irradiation at about 5 K. The internal friction spectra in Al-Pb, Al-Si, Al-Zn, Al-Ag, Al-Sn and Al-In are very similar. This result suggests that the configuration of the interstitial-solute atom complex in these alloys is very similar. In Al-Mg, the main complexes have the configuration with nearly symmetry, but its internal friction spectrum is different from that of the above-mentioned alloys. The internal friction spectra and their annealing behavior in Al-Be, Al-Mn, Al-Fe and Al-Cu demonstrate that the configuration of their interstitial-solute atom complex seems to be different from each other and the main complex in these alloys is immobile until stage III. (author)

International collaboration on CESR-TA program

International Nuclear Information System (INIS)

Flanagan, John; Suetsugu, Yusuke

2009-01-01

An international collaboration on the CESR-TA (Cornell Electron Storage Ring-Test Accelerator) program, which is a program to investigate electron cloud instability (ECI) issues in the positron damping ring of the ILC (International Linear-Collider), is currently underway a Cornell University, KEK is supporting the program through the development of an X-ray beam profile monitor system to measure the extremely small beam size, and through the development of clearing electrodes to mitigate the ECI. (author)

BWRVIP-140NP: BWR Vessel and Internals Project Fracture Toughness and Crack Growth Program on Irradiated Austenitic Stainless Steel

International Nuclear Information System (INIS)

Gilman, J.

2005-01-01

To prepare for this project, EPRI and BWRVIP conducted a workshop at Ponte Vedra Beach, Florida during February 19-21, 2003 (EPRI report 1007822). Attendees were invited to exchange relevant information on the effects of irradiation on austenitic materials in light water reactors and to produce recommendations for further work. EPRI reviewed the data, recommendations, and conclusions derived from the workshop and developed prioritized test matrices defining new data needs. Proposals were solicited, and selected proposals are the basis for the program described in this report. Results The planned test matrix for fracture toughness testing includes 21 tests on 5 materials

LWR pressure vessel irradiation surveillance dosimetry. Quarterly progress report, July--September 1978

Energy Technology Data Exchange (ETDEWEB)

Guthrie, G L; McElroy, W N; Lippincott, E P; Gold, R

1978-12-01

Program objectives and progress to date by the national laboratories in LWR pressure vessel irradiation surveillance dosimetry are summarized. Participants in the program include: Rockwell International, Hanford Engineering Development Laboratory, National Bureau of Standards, and Oak Ridge National Laboratory.

Technology development on analysis program for measuring fracture toughness of irradiated specimens

International Nuclear Information System (INIS)

Shibata, Akira; Takada, Fumiki

2007-03-01

The fracture toughness which represents resistance for brittle or ductile fracture is one of the most important material property concerning linear and non-linear fracture mechanics analyses. In order to respond to needs of collecting data relating to fracture toughness of pressure vessel and austenitic stainless steels, fracture toughness test for irradiated materials has been performed in JMTR hot laboratory. On the other hand, there has been no computer program for analysis of fracture toughness using the test data obtained from the test apparatus installed in the hot cell. Therefore, only load-displacement data have been provided to users to calculate fracture toughness of irradiated materials. Recently, request of analysis of fracture toughness have been increased. Thus a computer program, which calculates the amount of the crack extension, the compliance and the fracture toughness from the data acquired from the test apparatus installed in the hot cell, has been developed. In the program unloading elastic compliance method is applied based on ASTM E1820-01. Through the above development, the request for the fracture toughness analysis can be satisfied and the fracture toughness of irradiated test specimens can be provided to users. (author)

10 CFR 1.29 - Office of International Programs.

Science.gov (United States)

2010-01-01

... maintains working relationships with individual countries and international nuclear organizations, as well... 10 Energy 1 2010-01-01 2010-01-01 false Office of International Programs. 1.29 Section 1.29 Energy... Staff § 1.29 Office of International Programs. The Office of International Programs— (a) Advises the...

Literature study of the radiobiological parameters of Caesium-137 required for evaluating internal irradiation doses as a function of age; Etude bibliographique des parametres radiobiologiques du cesium-137 necessaires a l'evaluation des doses d'irradiation interne en fonction de l'age

Energy Technology Data Exchange (ETDEWEB)

Garnier, A [Commissariat a l' Energie Atomique, 92 - Fontenay-aux-Roses (France). Centre d' Etudes Nucleaires

1968-07-01

This document reassembles information published in scientific literature on radiobiological parameters of Cs-137, necessary for the estimate of the internal irradiation dose of man according to his age (during growth). The data are completed by a commented review of the mathematical models, proposed in order to value the irradiation doses from ingested cesium and the biological parameters. (author) [French] Ce document rassemble les informations publiees dans la litterature scientifique, concernant les parametres radiobiologiqueo du cesium-137, necessaires a l'evaluation des doses d'irradiation interne de l'homme en fonction de l'age. Ces donnees sont completees par une revue commentee des modeles mathematiques proposes en vue de l'evaluation des doses d'irradiation a partir des quantites de cesium ingerees et des parametres biologiques. (auteur)

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

Nondestructive post-irradiation examination of Loop-1, S1 and B1 rods

International Nuclear Information System (INIS)

Bratton, R.L.

1997-05-01

As a part of the Pacific Northwest National Laboratory's Tritium Target Development Program, eleven tritium target rods were irradiated in the Advanced Test Reactor located at the Idaho National Engineering and Environmental Laboratory during 1991. Both nondestructive and destructive post-irradiation examination on all eleven rods was planned under the Tritium Target Development Program. Funding for the program was reduced in 1991 resulting in the early removal of the program experiments before reaching their irradiation goals. Post-irradiation examination was only performed on one of the irradiated rods at the Pacific Northwest National Laboratory before the program was terminated in 1992. On December 6, 1995, the Secretary of Energy announced the pursuit of the Commercial Light-Water Reactor option for producing tritium establishing the Tritium Target Qualification Program at the Pacific Northwest National Laboratory. This program decided to pursue nondestructive and destructive post-irradiation examination of the ten remaining rods from the previous program. The ten rods comprise three experiments. The Loop-1 experiment irradiated eight target rods in a loop configuration for 217 irradiation days. The other two rods were irradiated in two separate irradiation experiments, designated as S1 and B1 for 143 effective full-power days, but at different power levels. After the ten rods were transferred from the ATR Canal to the Hot Fuels Examination Facility, the following examinations were performed: (1) visual examination and photography; (2) neutron radiography; (3) axial gamma scanning; (4) contact profilometry measurement; (5) bow and length measurements; (6) rod puncture and plenum gas analysis/measurement of plenum gas quantity; (7) void volume determination; and (8) internal pressure determination. This report presents the data collected during these examinations

The application of an internal state variable model to the viscoplastic behavior of irradiated ASTM 304L stainless steel

Energy Technology Data Exchange (ETDEWEB)

McAnulty, Michael J., E-mail: mcanulmj@id.doe.gov [Department of Energy, 1955 Fremont Avenue, Idaho Falls, ID 83402 (United States); Potirniche, Gabriel P. [Mechanical Engineering Department, University of Idaho, Moscow, ID 83844 (United States); Tokuhiro, Akira [Mechanical Engineering Department, University of Idaho, Idaho Falls, ID 83402 (United States)

2012-09-15

Highlights: Black-Right-Pointing-Pointer An internal state variable approach is used to predict the plastic behavior of irradiated metals. Black-Right-Pointing-Pointer The model predicts uniaxial tensile test data for irradiated 304L stainless steel. Black-Right-Pointing-Pointer The model is implemented as a user-defined material subroutine in the finite element code ABAQUS. Black-Right-Pointing-Pointer Results are compared for the unirradiated and irradiated specimens loaded in uniaxial tension. - Abstract: Neutron irradiation of metals results in decreased fracture toughness, decreased ductility, increased yield strength and increased ductile-to-brittle transition temperature. Designers use the most limiting material properties throughout the reactor vessel lifetime to determine acceptable safety margins. To reduce analysis conservatism, a new model is proposed based on an internal state variable approach for the plastic behavior of unirradiated ductile materials to support its use for analyzing irradiated materials. The proposed modeling addresses low temperature irradiation of 304L stainless steel, and predicts uniaxial tensile test data of irradiated experimental specimens. The model was implemented as a user-defined material subroutine (UMAT) in the finite element software ABAQUS. Results are compared between the unirradiated and irradiated specimens subjected to tension tests.

Degradation of austenitic stainless steel (SS) light water ractor (LWR) core internals due to neutron irradiation

Energy Technology Data Exchange (ETDEWEB)

Rao, Appajosula S., E-mail: Appajosula.Rao@nrc.gov

2014-04-01

Austenitic stainless steels (SSs) are extensively being used in the fabrication of light water reactor (LWR) core internal components. It is because these steels have relatively high ductility, fracture toughness and moderate strength. However, the LWR internal components exposure to neutron irradiation over an extended period of plant operation degrades the materials mechanical properties such as the fracture toughness. This paper summarizes some of the results of the existing open literature data on irradiation assisted stress corrosion cracking (IASCC) of 316 CW steels that have been published by the United States Nuclear Regulatory Commission (USNRC), industry, academia, and other research agencies.

Irradiation's potential for preserving food

International Nuclear Information System (INIS)

Morrison, R.M.

1986-01-01

The first experimental studies on the use of ionizing radiation for the preservation of foods were published over thirty years ago (1, 2) . After a period of high expectations and perhaps exaggerated optimism a series of disappointments occurred in the late '60s .The first company specifically created to operate a food irradiation plant, Newfield Products Inc, ran into financial difficulties and had to close its potato irradiation facility in 1966. The irradiator, designed to process 15,000t of potatoes per month for inhibition of sprouting, was in operation during one season only. In 1968 the US Food an Drug Administration refused approval for radiation-sterilisation of ham and withdrew the approval it had granted in 1963 for irradiated bacon. An International Project on the Irradiation of Fruit and Fruit juices, created in 1965 at Seibersdorf, Austria, with the collaboration or 9 countries, ended with general disappointment after three years. The first commercial grain irradiator, built in the Turkish harbour town of Iskenderun by the International Atomic Energy Agency with funds from the United Nations Development Program, never received the necessary operating licence from the Turkish Government and had to be dismantled in 1968. The US Atomic Energy Commission terminated its financial support to all research programmes on food irradiation in 1970. For a number of years, little chance seemed to remain that the new process would ever be practically used. However, research and development work was continued in a number of laboratories all over the world, and it appears that the temporary setbacks now have been overcome. Growing quantities of irradiated foods are being marketed in several countries and indications are that irradiated foods will eventually be as generally accepted as are frozen, dried or heatsterilised foods

International service learning programs: ethical issues and recommendations.

Science.gov (United States)

Reisch, Rebecca A

2011-08-01

Inequities in global health are increasingly of interest to health care providers in developed countries. In response, many academic healthcare programs have begun to offer international service learning programs. Participants in these programs are motivated by ethical principles, but this type of work presents significant ethical challenges, and no formalized ethical guidelines for these activities exist. In this paper the ethical issues presented by international service learning programs are described and recommendations are made for how academic healthcare programs can carry out international service learning programs in a way that minimizes ethical conflicts and maximizes benefits for all stakeholders. Issues related to project sustainability and community involvement are emphasized. © 2011 Blackwell Publishing Ltd.

Extension of the RPV irradiation surveillance program of NPP GKN II by T0 approach

International Nuclear Information System (INIS)

Barthelmes, J.; Keim, E.; Hein, H.; Koenig, G.

2015-01-01

The nuclear power plant (NPP) Neckarwestheim II (GKN II) started operation in 1989 and was designed for 40 years of operation. During the plant life time the reactor pressure vessel (RPV) integrity is a main aspect for nuclear safety since the RPV is exposed to neutron irradiation affecting the mechanical material properties, in particular toughness. In this context the ductile to brittle transition reference temperature of the RPV materials can be determined either indirectly according to the RT(NDT) concept by means of comparative examinations of irradiated and unirradiated notched-bar impact specimens or directly according to the Master Curve concept by means of examination of irradiated fracture mechanic specimens and determination of an alternative reference temperature RT(T0). With the implementation and evaluation of the first irradiation surveillance program consisting of three sets, one unirradiated reference set (set 1) and two irradiated sets (set 2 and 3), the RPV safety could be proven for the assessment fluence (AF) of 8*10 18 cm -2 (E > 1 MeV) using the RT(NDT) concept. Against the background of a possible long term operation and the state-of-the-art of science and technology in 1998 the NPP GKN II initiated a supplemental irradiation surveillance program with two irradiation sets (set 4 and 5) containing fracture mechanic specimens for complementary proof of safety according to the Master Curve concept. The results of the first irradiated set 4 are presented and assessed by means of the reference temperatures according to the Master Curve concept and compared to the results of the irradiation sets 1 to 3 of the conventional irradiation surveillance program. As an important outcome the existing RPV integrity assessment could be ensured by the Master Curve results. The applied approach adapts to the state-of-the-art of science and technology and is best practice to ensure the safe operation of RPV supplementary. (authors)

A Model Program for International Commerce Education.

Science.gov (United States)

Funston, Richard

To address the economy's growing reliance on international business, San Diego State University has recently introduced a program in international commerce. The program was developed by packaging coursework in three existing areas: business administration, language training, and area studies. Although still in its infancy, the international…

Microstructural characterization and model of hardening for the irradiated austenitic stainless steels of the internals of pressurized water reactors

International Nuclear Information System (INIS)

Pokor, C.

2003-01-01

The core internals of Pressurized Water Reactors (PWR) are composed of SA 304 stainless steel plates and CW 316 stainless steel bolts. These internals undergo a neutron flux at a temperature between 280 deg C and 380 deg C which modifies their mechanical properties. These modifications are due to the changes in the microstructure of these materials under irradiation which depend on flux, dose and irradiation temperature. We have studied, by Transmission Electron Microscopy, the microstructure of stainless steels SA 304, CW 316 and CW 316Ti irradiated in a mixed flux reactor (OSIRIS at 330 deg C between 0,8 dpa et 3,4 dpa) and in a fast breeder reactor at 330 deg C (BOR-60) up to doses of 40 dpa. Moreover, samples have been irradiated at 375 deg C in a fast breeder reactor (EBR-II) up to doses of 10 dpa. The microstructure of the irradiated stainless steels consists in faulted Frank dislocation loops in the [111] planes of austenitic, with a Burgers vector of [111]. It is possible to find some voids in the solution annealed samples irradiated at 375 deg C. The evolution of the dislocations loops and voids has been simulated with a 'cluster dynamic' model. The fit of the model parameters has allowed us to have a quantitative description of our experimental results. This description of the microstructure after irradiation was coupled together with a hardening model by Frank loops that has permitted us to make a quantitative description of the hardening of SA 304, CW 316 and CW 316Ti stainless steels after irradiation at a certain dose, flux and temperature. The irradiation doses studied grow up to 90 dpa, dose of the end of life of PWR internals. (author)

Brazilian Irradiation Project: CAFE-MOD1 validation experimental program

International Nuclear Information System (INIS)

Mattos, Joao Roberto Loureiro de; Costa, Antonio Carlos L. da; Esteves, Fernando Avelar; Dias, Marcio Soares

1999-01-01

The Brazilian Irradiation Project whose purpose is to provide Brazil with a minimal structure to qualify the design, fabrication and quality procedures of nuclear fuels, consists of three main facilities: IEA-R1 reactor of IPEN-CNEN/SP, CAFE-MOD1 irradiation device and a unit of hot cells. The CAFE-MOD1 is based on concepts successfully used for more than 20 years in the main nuclear institutes around the world. Despite these concepts are already proved it should be adapted to each reactor condition. For this purpose, there is an ongoing experimental program aiming at the certification of the criteria and operational limits of the CAFE-MOD1 in order to get the allowance for its installation at the IEA-R1 reactor. (author)

Dielectric parameters of blood plasma in rats at external and internal irradiation with sublethal doses

International Nuclear Information System (INIS)

Khadzhidekova, E.; Kiradzhiev, G.

1991-01-01

Sexually mature male rats have received external gamma irradiation with 50, 200 or 380 cGy, treated with 89 Sr (333 or 1665 kBq per rat, femur dose 70, resp. 290 cGy), or 144 Ce (370 kBq per rat, liver dose 70 cGy). Dielectric parameters (permittivity and conductivity) have been measured in the frequency range 1.4 - 17 Mhz on different terms (1 to 30th day after the treatment). For all groups and terms the coefficients and equations describing the relationship between the dielectric permittivity ε and the frequency ν of the changing electric field have been calculated. On the basis of dielectric parameters the relaxation time of the plasma protein molecules is determined. It has been shown that the changes in dielectric permittivity are expressed at different frequencies specific for a given dose; the same is established for the conditions of internal irradiation. The frequency dependence of the permittivity is described as an exponential curve analogous to that of the control but with a changed exponent. In applying higher doses or activities the relationship turns from exponential to parabolic. The relaxation time, expressing the changes in conformal state of macromolecules, varies but is in all cases longer than one of the controls for the whole period of study at external irradiation with 50 and 380 cGy. It is lower at irradiation with 200 cGy, as well as at internal irradiation. 3 tabs., 13 refs

Activity computer program for calculating ion irradiation activation

Science.gov (United States)

Palmer, Ben; Connolly, Brian; Read, Mark

2017-07-01

A computer program, Activity, was developed to predict the activity and gamma lines of materials irradiated with an ion beam. It uses the TENDL (Koning and Rochman, 2012) [1] proton reaction cross section database, the Stopping and Range of Ions in Matter (SRIM) (Biersack et al., 2010) code, a Nuclear Data Services (NDS) radioactive decay database (Sonzogni, 2006) [2] and an ENDF gamma decay database (Herman and Chadwick, 2006) [3]. An extended version of Bateman's equation is used to calculate the activity at time t, and this equation is solved analytically, with the option to also solve by numeric inverse Laplace Transform as a failsafe. The program outputs the expected activity and gamma lines of the activated material.

Nuclear materials control and accountability internal audit program

International Nuclear Information System (INIS)

Barham, M.A.; Abbott, R.R.

1991-01-01

This paper reports that the Department of Energy Order (DOE) 5633.3, Control and Accountability for Nuclear Materials, includes several requirements for development and implementation of an internal audit program. Martin Marietta Energy System, Inc., manages five sites in Tennessee, Kentucky, and Ohio for the DOE Field Office, Oak Ridge and has a Central Nuclear Materials Control and Accountability (NMC and A) Manager with matrixed responsibility for the NMC and A program at the five sites. The Energy Systems Central NMC and A Manager has developed an NMC and A Internal Audit Handbook which defines the functional responsibilities, performance criteria, and reporting and documentation requirements for the Energy Systems NMC and A Internal Audit Program. The initial work to develop and implement these standards was tested at the K-25 Site when the site hired an internal auditor to meet the DOE requirements for an NMC and A Internal Audit program

MONJU AS AN INTERNATIONAL ASSET: INTERNATIONAL ASSISTANCE AND COOPERATION

International Nuclear Information System (INIS)

Rodriguez, G.; Wisner, R.S.; Stuart, R.

2004-01-01

The role of the fast breeder reactor prototype Monju has expanded to meet the challenges of the 21st century. Today instead of being merely a demonstration of an economical, safe, environmentally responsible source of energy, as originally designed, it has also the capability to be transformed into a unique International Irradiations Test Facility. The potential for Monju's role in the Generation IV nuclear energy systems development, and fast reactor research and development area is clear. Its incomparable fast neutron spectrum density will be a major interest not only for Sodium Fast Reactor but for all the Generation IV concepts. As Monju's potential future role is laid out, plans for future tests can be made. Tests of advanced fuels and materials in support of the Advanced Fuel Cycle Initiative, as well as Minor Actinide Burning can be envisaged. Tests planned on transmutation of minor actinides have the objectives of an industrial demonstration of the reduction of toxic wastes and the stewardship burden of the long-lived wastes. Tests and demonstrations carried out at Monju will provide a bridge from existing Generation III fast reactor systems, now in the later stages of their projected operational lifetimes, to Generation IV nuclear energy systems. The JNC founded the International Cooperation and Technology Development Center and the International Research Fellowship program to facilitate this international effort. The Center exists specifically to formulate and perform projects ensuring the maximum technical benefit from Monju. The staff includes physicists, engineers and nuclear industry leaders from around the world. Research Fellowships center is based on several technical areas: advanced instrumentation, inspection techniques, plant reliability and safety, nucleonics, sodium handling technologies, irradiation and experiment management and coordination and advanced post-irradiation examination capabilities and techniques. This paper describes the recent

International Photovoltaic Program Plan. Volume II. Appendices

Energy Technology Data Exchange (ETDEWEB)

Costello, D.; Koontz, R.; Posner, D.; Heiferling, P.; Carpenter, P.; Forman, S.; Perelman, L.

1979-12-01

This second volume of a two-part report on the International Photovoltaic Program Plan contains appendices summarizing the results of analyses conducted in preparation of the plan. These analyses include compilations of relevant statutes and existing Federal programs; strategies designed to expand the use of photovoltaics abroad; information on the domestic photovoltaic plan and its impact on the proposed international plan; perspectives on foreign competition; industry views on the international photovoltaic market and ideas about how US government actions could affect this market; international financing issues; and information on issues affecting foreign policy and developing countries.

Promoting Success: A Professional Development Coaching Program for Interns in Medicine.

Science.gov (United States)

Palamara, Kerri; Kauffman, Carol; Stone, Valerie E; Bazari, Hasan; Donelan, Karen

2015-12-01

Residency is an intense period. Challenges, including burnout, arise as new physicians develop their professional identities. Residency programs provide remediation, but emotional support for interns is often limited. Professional development coaching of interns, regardless of their performance, has not been reported. Design, implement, and evaluate a program to support intern professional development through positive psychology coaching. We implemented a professional development coaching program in a large residency program. The program included curriculum development, coach-intern interactions, and evaluative metrics. A total of 72 internal medicine interns and 26 internal medicine faculty participated in the first year. Interns and coaches were expected to meet quarterly; expected time commitments per year were 9 hours (per individual coached) for coaches, 5 1/2 hours for each individual coachee, and 70 hours for the director of the coaching program. Coaches and interns were asked to complete 2 surveys in the first year and to participate in qualitative interviews. Eighty-two percent of interns met with their coaches 3 or more times. Coaches and their interns assessed the program in multiple dimensions (participation, program and professional activities, burnout, coping, and coach-intern communication). Most of the interns (94%) rated the coaching program as good or excellent, and 96% would recommend this program to other residency programs. The experience of burnout was lower in this cohort compared with a prior cohort. There is early evidence that a coaching program of interactions with faculty trained in positive psychology may advance intern development and partially address burnout.

A summary of recent developments in the sludge irradiation program at Sandia laboratories

International Nuclear Information System (INIS)

Morris, M.E.; Sivinski, J.S.; Brandon, J.R.; Neuhauser, K.S.; Ward, R.L.

1978-01-01

Sandia Laboratories has shifted the emphasis of its Sewage Sludge Irradiation Program toward treating dried sewage sludges rather than liquid sludges for the following reasons: (1) cities' interests in composting sewage sludge before final disposal; (2) need for disinfection of the product before sale to the public; and (3) low cost of disinfection by radiation processing. As a result of this shift, the Sandia Irradiator for Dried Sewage Solids (SIDSS), was designed and is near completion. The irradiator will treat up to 8 tons/day of solids with a 1 megarad absorbed dose. A bucket conveyor will transport the sewage sludge past a 1 megacurie cesium-137 γ-ray source. If a lower dose than 1 megarad is acceptable for disinfection, the daily throughput of the irradiator will be correspondingly increased. The irradiator is designed so that the cesium-137 γ-ray sources used to charge the facility can be manipulated underwater. After source unloading is complete, the water will be drained and the irradiator will be operated dry. Either bagged or bulk solids can be irradiated with the system. (Auth.)

Irradiated fuel performance evaluation technology development

International Nuclear Information System (INIS)

Koo, Yang Hyun; Bang, J. G.; Kim, D. H.

2012-01-01

Alpha version performance code for dual-cooled annular fuel under steady state operation, so called 'DUOS', has been developed applying performance models and proposed methodology. Furthermore, nonlinear finite element module which could be integrated into transient/accident fuel performance code was also developed and evaluated using commercial FE code. The first/second irradiation and PIE test of annular pellet for dual-cooled annular fuel in the world have been completed. In-pile irradiation test DB of annular pellet up to burnup of 10,000 MWd/MTU through the 1st test was established and cracking behavior of annular pellet and swelling rate at low temperature were studied. To do irradiation test of dual-cooled annular fuel under PWR's simulating steady-state conditions, irradiation test rig/rod design/manufacture of mock-up/performance test have been completed through international collaboration program with Halden reactor project. The irradiation test of large grain pellets has been continued from 2002 to 2011 and completed successfully. Burnup of 70,000 MWd/MTU which is the highest burnup among irradiation test pellets in domestic was achieved

Qualification program for JHR fuel elements: Irradiation of the first JHR test assembly in the BR2-Evita loop

International Nuclear Information System (INIS)

Anselmet, M.-C.; Lemoine, P.; Koonen, E.; Benoit, P.; Gouat, P.; Claes, W.; Geens, F.; Miras, G.; Brisson, S.

2010-01-01

An experimental program has been designed by CEA to qualify the behaviour of the JHR fuel under conditions representative of the reactor operating ones. This program uses the SCK.CEN facilities, irradiating JHR lead test elements in the BR2 reactor, inside its central channel which has been particularly arranged for this objective (Evita loop). As a first step in the program, a two cycle irradiation (4 weeks by cycle) started mid-July 2009 and ended mid-November (EVITA-1). After a cooling phase, this first JHR lead test element will be submitted to post-irradiation examination. The second JHR test element began its irradiation in the first quarter of 2010; its unloading is planned before the end of 2010, after 5 cycles in the BR2 reactor. The results of these two experiments are expected as input information for the Safety Authority Report. This paper presents the qualification program with the objectives assigned to each phase (irradiation, examination). A first interpretation of the irradiation data for the first element is presented, so as the information available on the progress of the following phases of the programme. (author)

Program description for the qualification of CNEA - Argentina as a supplier of LEU silicide fuel and post-irradiation examinations plan for the first prototype irradiated in Argentina

International Nuclear Information System (INIS)

Rugirello, Gabriel; Adelfang, Pablo; Denis, Alicia; Zawerucha, Andres; Marco, Agustin di; Guillaume, Eduardo; Sbaffoni, Monica; Lacoste, Pablo

1998-01-01

In this report we present a description of the ongoing and future stages of the program for the qualification of CNEA, Argentina, as a supplier of low enriched uranium silicide fuel elements for research reactor. Particularly we will focus on the characteristics of the future irradiation experiment on a new detachable prototype, the post-irradiation examinations (PIE) plan for the already irradiated prototype PO4 and an overview of the recently implemented PIE facilities and equipment. The program is divided in several steps, some of which have been already completed. It concludes: development of the uranium silicide fissile material, irradiation and PIE of several full-scale prototypes. Important investments have been already carried out in the facilities for the FE production and PIE. (author)

Literature study of the radiobiological parameters of Caesium-137 required for evaluating internal irradiation doses as a function of age; Etude bibliographique des parametres radiobiologiques du cesium-137 necessaires a l'evaluation des doses d'irradiation interne en fonction de l'age

Energy Technology Data Exchange (ETDEWEB)

Garnier, A. [Commissariat a l' Energie Atomique, 92 - Fontenay-aux-Roses (France). Centre d' Etudes Nucleaires

1968-07-01

This document reassembles information published in scientific literature on radiobiological parameters of Cs-137, necessary for the estimate of the internal irradiation dose of man according to his age (during growth). The data are completed by a commented review of the mathematical models, proposed in order to value the irradiation doses from ingested cesium and the biological parameters. (author) [French] Ce document rassemble les informations publiees dans la litterature scientifique, concernant les parametres radiobiologiqueo du cesium-137, necessaires a l'evaluation des doses d'irradiation interne de l'homme en fonction de l'age. Ces donnees sont completees par une revue commentee des modeles mathematiques proposes en vue de l'evaluation des doses d'irradiation a partir des quantites de cesium ingerees et des parametres biologiques. (auteur)

Adequate irradiation of the internal jugular lymph node chain: technical considerations

International Nuclear Information System (INIS)

Aref, Amr; Gross, Martin; Fontanesi, James; Devi, Syamala; Kopel, Christine; Thornton, Dale

1997-01-01

Purpose: This research aimed to study the anatomic relationship between the internal jugular vein with the surrounding internal jugular lymph node chain and the underlying bony anatomical structures which are commonly used as landmarks for radiation therapy planning. Methods and Materials: Twelve patients with carcinoma of the head and neck region were studied prospectively. Using our three-dimensional planning system, a beam's-eye view of the internal jugular vein was projected onto a lateral and anterior simulation film. Quantitative measurements were made in every case of the anatomic relationship between the internal jugular vein and the posterior border of the cervical vertebrae and sagittal midline. Results: The distance between the posterior border of the internal jugular vein and the posterior border of the cervical vertebrae ranged between 0 and 2.5 cm. The distances between the sagittal midline and the medial border of the internal jugular veins ranged between 2 and 4 cm. Conclusion: To ensure adequate irradiation of the internal jugular lymph nodes, the posterior border of the lateral radiation therapy upper-neck fields should be placed at least 1 cm posterior to the posterior aspect of the cervical vertebrae. The midline block used in the lower neck anterior field should not exceed 2 cm in width

Current status of food irradiation overseas. Data update from 2013

International Nuclear Information System (INIS)

Todoriki, Setsuko

2015-01-01

As the movement of international standards and specifications, the treatment standards related to food irradiation have been summarized on the basis of the ISPM 28 Annex PT-19 of International Plant Protection Convention. As the movement in the United States, there are the following tables: (1) food and radiation dose approved by FDA, (2) lowest radiation dose for the pests of each quarantine target stipulated by the USDA/APHIS as the plant quarantine authorities of the United States Department of Agriculture, (3) items and production sites of vegetables/fruits about which irradiation treatment in import phytosanitary has been approved by USDA, and (4) import volume of irradiated fruits into the United States. The following statistics have also been summarized: (1) materials and irradiation dose permitted FSANZ, which is the food safety regulatory authorities of Australia and New Zealand, and (2) irradiation-treated amount of each food in the EU territory in 2013, and treated amount in each country. In Asia, the amount and facilities of irradiation treatment are described for ten countries including China, Thailand, India, etc. As the contents of the Coordinated Research Programs (CRPs) of International Atomic Energy Agency (IAEA), the following are introduced: (1) three items including 'Development of generic irradiation doses for quarantine treatments,' and (2) three items of the contents of 'The Regional Cooperative Agreement for Research, Development and Training Related to Nuclear Science and Technology for Asia and the Pacific: RCA).' (A.O.)

76 FR 19909 - International Terrorism Victim Expense Reimbursement Program

Science.gov (United States)

2011-04-11

... 1121-AA78 International Terrorism Victim Expense Reimbursement Program AGENCY: Office of Justice... promulgating this interim-final rule for its International Terrorism Victim Expense Reimbursement Program... international terrorism. DATES: Effective date: This interim-final rule is effective April 11, 2011. Comment...

Calculation of absorbed dose of anchorage-dependent cells from internal beta-rays irradiation

International Nuclear Information System (INIS)

Chen Jianwei; Huang Gang; Li Shijun

2001-01-01

Objective: To elicit the formula of internal dosimetry in anchorage-dependent cells by beta-emitting radionuclides from uniformly distributed volume sources. Methods: By means of the definition of absorbed dose and the MIRD (Medical International Radiation Dose) scheme the formula of internal dosimetry was reasonably deduced. Firstly, studying the systems of suspension culture cells. Then, taking account of the speciality of the systems of the anchorage-dependent cells and the directions of irradiation, the absorbed dose of anchorage -dependent cells was calculated by the accumulated radioactivity, beta-ray energy, and the volume of the cultured systems. Results: The formula of internal dosimetry of suspension culture cells and anchorage-dependent cells were achieved. At the same time, the formula of internal dosimetry of suspension culture cells was compared with that of MIRD and was confirmed accurate. Conclusion: The formula of internal dosimetry is concise, reliable and accurate

Designing and Managing Successful International Joint Development Programs

Science.gov (United States)

2016-04-30

joint development programs are important because of their potential to reduce costs and increase partnership benefits such as interoperability, economies ...have actualized by discussing what characteristics research has shown as crucial to international joint development program outcomes. The study team... characteristics of international joint development programs that result in positive or negative cost, scheduling, and end-product outcomes, such as a final

Pressure control of a proton beam-irradiated water target through an internal flow channel-induced thermosyphon.

Science.gov (United States)

Hong, Bong Hwan; Jung, In Su

2017-07-01

A water target was designed to enhance cooling efficiency using a thermosyphon, which is a system that uses natural convection to induce heat exchange. Two water targets were fabricated: a square target without any flow channel and a target with a flow channel design to induce a thermosyphon mechanism. These two targets had the same internal volume of 8 ml. First, visualization experiments were performed to observe the internal flow by natural convection. Subsequently, an experiment was conducted to compare the cooling performance of both water targets by measuring the temperature and pressure. A 30-MeV proton beam with a beam current of 20 μA was used to irradiate both targets. Consequently, the target with an internal flow channel had a lower mean temperature and a 50% pressure drop compared to the target without a flow channel during proton beam irradiation. Copyright © 2017 Elsevier Ltd. All rights reserved.

What skills should new internal medicine interns have in july? A national survey of internal medicine residency program directors.

Science.gov (United States)

Angus, Steven; Vu, T Robert; Halvorsen, Andrew J; Aiyer, Meenakshy; McKown, Kevin; Chmielewski, Amy F; McDonald, Furman S

2014-03-01

The transition from medical student to intern may cause stress and burnout in new interns and the delivery of suboptimal patient care. Despite a formal set of subinternship curriculum guidelines, program directors have expressed concern regarding the skill set of new interns and the lack of standardization in that skill set among interns from different medical schools. To address these issues, the Accreditation Council for Graduate Medical Education's Next Accreditation System focuses on the development of a competency-based education continuum spanning undergraduate, graduate, and continuing medical education. In 2010, the Clerkship Directors in Internal Medicine subinternship task force, in collaboration with the Association of Program Directors in Internal Medicine survey committee, surveyed internal medicine residency program directors to determine which competencies or skills they expected from new medical school graduates. The authors summarized the results using categories of interest. In both an item rank list and free-text responses, program directors were nearly uniform in ranking the skills they deemed most important for new interns-organization and time management and prioritization skills; effective communication skills; basic clinical skills; and knowing when to ask for assistance. Stakeholders should use the results of this survey as they develop a milestone-based curriculum for the fourth year of medical school and for the internal medicine subinternship. By doing so, they should develop a standardized set of skills that meet program directors' expectations, reduce the stress of transitions across the educational continuum, and improve the quality of patient care.

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

Program for photon shielding calculations. Examination of approximations on irradiation geometries

International Nuclear Information System (INIS)

Isozumi, Yasuhito; Ishizuka, Fumihiko; Miyatake, Hideo; Kato, Takahisa; Tosaki, Mitsuo

2004-01-01

Penetration factors and related numerical data in 'Manual of Practical Shield Calculation of Radiation Facilities (2000)', which correspond to the irradiation geometries of point isotropic source in infinite thick material (PI), point isotropic source in finite thick material (PF) and vertical incident to finite thick material (VF), have been carefully examined. The shield calculation based on the PI geometry is usually performed with effective dose penetration factors of radioisotopes given in the 'manual'. The present work cleary shows that such a calculation may lead to an overestimate more than twice larger, especially for thick shield of concrete and water. Employing the numerical data in the 'manual', we have fabricated a simple computer program for the estimation of penetration factors and effective doses of radioisotopes in the different irradiation geometries, i.e., PI, PF and VF. The program is also available to calculate the effective dose from a set of radioisotopes in the different positions, which is necessary for the γ-ray shielding of radioisotope facilities. (author)

The U.S. Department of Energy Program in low-dose food irradiation

International Nuclear Information System (INIS)

Krenz, D.L.; McMullen, W.H.

1985-01-01

The U.S. Department of Energy's Byproducts Utilization Program (BUP) seeks to develop and encourage the widespread beneficial commercial use of waste byproducts produced by Department of Energy (DOE) programs. These byproducts are generally radioactive to varying degrees and consist of fission products resulting from irradiation of nuclear reactor fuel for production of special nuclear material at DOE facilities in Richland, Washington, and Savannah River, South Carolina

Internal irradiation with radon daughters in some Bulgarian polymetal mines over the period 1962-1993

International Nuclear Information System (INIS)

Presiyanov, D.; Dimotrov, M.

1993-01-01

The results of radiation monitoring of the working environment in the Bulgarian metal mines are evaluated. The irradiation levels in the Burgas Copper Mines and their variations over the years have been estimated. A radiological characteristic of the working environment is provided together with a risk assessment for workers in different mines. A retrospective risk assessment is attempted for mines where increased radon 222 levels have been detected recently. The organization of radiometric monitoring and measures to limit the risk of internal irradiation are discussed. (author)

An investigation of high-temperature irradiation test program of new ceramic materials

International Nuclear Information System (INIS)

Ishino, Shiori; Terai, Takayuki; Oku, Tatsuo

1999-08-01

The Japan Atomic Energy Research Institute entrusted the Atomic Energy Society of Japan with an investigation into the trend of irradiation processing/damage research on new ceramic materials. The present report describes the result of the investigation, which was aimed at effective execution of irradiation programs using the High Temperature Engineering Test Reactor (HTTR) by examining preferential research subjects and their concrete research methods. Objects of the investigation were currently on-going preliminary tests of functional materials (high-temperature oxide superconductor and high-temperature semiconductor) and structural materials (carbon/carbon and SiC/SiC composite materials), together with newly proposed subjects of, e.g., radiation effects on ceramics-coated materials and super-plastic ceramic materials as well as microscopic computer simulation of deformation and fracture of ceramics. These works have revealed 1) the background of each research subject, 2) its objective and significance from viewpoints of science and engineering, 3) research methodology in stages from preliminary tests to real HTTR irradiation, and 4) concrete HTTR-irradiation methods which include main specifications of test specimens, irradiation facilities and post-irradiation examination facilities and apparatuses. The present efforts have constructed the important fundamentals in the new ceramic materials field for further planning and execution of the innovative basic research on high-temperature engineering. (author)

Combination Processes in Food Irradiation. Proceedings of an International Symposium on Combination Processes in Food Irradiation

International Nuclear Information System (INIS)

1981-01-01

Processes in Food Irradiation was held by the IAEA and FAO at the Bandaranaike Memorial International Conference Hall in Colombo on 24-28 November 1980, and the present volume contains the proceedings. One of the most effective means demonstrated of increasing the efficacy of irradiation in the control of food spoilage is the combination of a low irradiation dose with a mild heat treatment. Promising results were reported for the shelf-life extension of mangoes and papayas, and the disinfestation of dried dates. Commercial application of the heat-irradiation treatment for some fruits is expected to follow soon. The Symposium covered other topics, such as the mechanisms of sensitization of microorganisms by physical and chemical agents, improvement of the microbiological quality of foods by combination processes, and the aspects of the wholesomeness and legislation of the food irradiation process. A key issue in the general discussion was the recommendation on the acceptability of food irradiated up to an overall average dose of 10 kGy. This important recommendation had been achieved at a recently convened Joint FAO/IAEA/WHO Expert Committee on the Wholesomeness of Irradiated Foods (27 October — 3 November 1980, Geneva). The breakthrough on the toxicological acceptability constitutes a firm basis for going ahead speedily with the development of practical applications of food irradiation, which should take its rightful place among other food preservation methods in helping to provide more and better food to a world in need. The sponsoring organizations hope that the publication of these proceedings will encourage further research and development of food irradiation to the benefit of mankind

Combination Processes in Food Irradiation. Proceedings of an International Symposium on Combination Processes in Food Irradiation

Energy Technology Data Exchange (ETDEWEB)

NONE

1981-09-15

Processes in Food Irradiation was held by the IAEA and FAO at the Bandaranaike Memorial International Conference Hall in Colombo on 24-28 November 1980, and the present volume contains the proceedings. One of the most effective means demonstrated of increasing the efficacy of irradiation in the control of food spoilage is the combination of a low irradiation dose with a mild heat treatment. Promising results were reported for the shelf-life extension of mangoes and papayas, and the disinfestation of dried dates. Commercial application of the heat-irradiation treatment for some fruits is expected to follow soon. The Symposium covered other topics, such as the mechanisms of sensitization of microorganisms by physical and chemical agents, improvement of the microbiological quality of foods by combination processes, and the aspects of the wholesomeness and legislation of the food irradiation process. A key issue in the general discussion was the recommendation on the acceptability of food irradiated up to an overall average dose of 10 kGy. This important recommendation had been achieved at a recently convened Joint FAO/IAEA/WHO Expert Committee on the Wholesomeness of Irradiated Foods (27 October - 3 November 1980, Geneva). The breakthrough on the toxicological acceptability constitutes a firm basis for going ahead speedily with the development of practical applications of food irradiation, which should take its rightful place among other food preservation methods in helping to provide more and better food to a world in need. The sponsoring organizations hope that the publication of these proceedings will encourage further research and development of food irradiation to the benefit of mankind.

Food Irradiation Newsletter. V.13, no. 1

International Nuclear Information System (INIS)

1989-03-01

The International Conference on the Acceptance, Control of, and Trade in Irradiated Food, jointly sponsored by FAO, IAEA, WHO and ITC-UNCTAD/GATT, Geneva, Switzerland, December 1988, recognized that (1) food irradiation has the potential to reduce the incidence of foodborne diseases; (2) food irradiation can reduce post-harvest food losses and make available a larger quantity and a wider variety of foodstuffs for consumers - It can also be an effective quarantine treatment for certain food and thus contribute to international trade; (3) international trade in irradiated foods would be facilitated by harmonization of national procedures based on internationally recognized standards for the control of food irradiation. The ''International Document on Food Irradiation'' adopted by consensus at the Conference is included in this issue, which also contains excerpts of the 5th Annual Meeting of the International Consultative Group on Food Irradiation (ICGFI), convened in Vienna, September 1988, and reports of two co-ordinated meetings, the second Research Co-ordination Meeting on the Use of Irradiation as a Quarantine Treatment of Food and Agricultural Commodities, and the Second Co-ordination Meeting on Food Irradiation Programme for Developing Countries in Middle East and Europe. 3 tabs

Food irradiation: fiction and reality

International Nuclear Information System (INIS)

1991-01-01

The International Consultative Group on Food Irradiation (IGCFI), sponsored by World Health Organization (WHO), Food and Agriculture Organization (FAO) and the International Atomic Energy Agency (IAEA), with the intention to provide to governments, especially those of developing countries, scientifically correct information about food irradiation, decided to organize a file and questions of general public interest. The document is composed by descriptive files related with the actual situation and future prospective, technical and scientific terms, food irradiation and the radioactivity, chemical transformations in irradiated food, genetic studies, microbiological safety of irradiated food, irradiation and harmlessness, irradiation and additives, packing, irradiation facilities control, process control, irradiation costs and benefits as well as consumers reaction

Study about internal friction in deformed - and irradiated pure titanium

International Nuclear Information System (INIS)

Miyada, L.T.

1979-01-01

Internal friction and modulus are measured in pure Ti at low temperature using an inverted torsion-pendulum at about 1 Hz. The presence of four relaxation peaks P' sub(d)(-140 0 C), P sub(d)(-101 0 C), P' sub(α)(-75 0 C) and P sub(α)(-50 0 C) has been found, and effects of plastic deformation, heat treatment and neutron irradiation on these peaks are investigated in detail. Activation energies and frequency factors of P sub(d) and Pα peaks are consistent with the data in higher frequency range reproted by other workers. The P sub(d) and P' sub(d) peaks grow after deformation and tend to decay after annealing at high temperatures or after neutron irradiation. Both peaks are resonably interpreted in terms of dislocation relaxation mechanisms (Bordoni type) arising from thermally activated motion of dislocations in different slip planes of h.c.f. structure. Peierls stress of dislocations giving rise to each peak have calculated based on Seeger's theory, and found to be consistent with that of f.c.c. metals. On the other hand, P sub(α) and P' sub(α) peaks grow significantly at the expense of P sub(d) and P' sub(d) peaks after neutron irradiation in deformed samples. The behaviour of these peaks as a function of irradiation dose and annealing temperatures strongly indicated that they are due to relaxations resulting from dislocations-point defects interactions (Hasiguti type). It is tentatively suggested that P sub(α) and P' sub(α) peaks are related with interactions of dislocations with divacancies and single vacancies, respectively. Application of Schiller's model showed a consistent result with regard to the P' sub(α) peak experimentally observed. (Author) [pt

International photovoltaic program. Volume 2: Appendices

Science.gov (United States)

Costello, D.; Koontz, R.; Posner, D.; Heiferling, P.; Carpenter, P.; Forman, S.; Perelman, L.

1979-01-01

The results of analyses conducted in preparation of an international photovoltaic marketing plan are summarized. Included are compilations of relevant statutes and existing Federal programs; strategies designed to expand the use of photovoltaics abroad; information on the domestic photovoltaic plan and its impact on the proposed international plan; perspectives on foreign competition; industry views on the international photovoltaic market and ideas about the how US government actions could affect this market;international financing issues; and information on issues affecting foreign policy and developing countries.

International Affairs Programs: The Air Force Versus the Army

Science.gov (United States)

2015-10-01

individual tutoring programs . Additionally RAS personnel are offered regional enhancement studies opportunities at several facilities.48 RAS personnel...AU/ACSC/2015 AIR COMMAND AND STAFF COLLEGE AIR UNIVERSITY INTERNATIONAL AFFAIRS PROGRAMS : THE AIR FORCE VERSUS THE ARMY by Robin L...5 COMPARISON: INTERNATIONAL AFFAIRS PROGRAMS AIR FORCE VERSUS ARMY 8

Heavy-section steel irradiation program. Volume 4, No. 2. Semiannual progress report, April 1993--September 1993

International Nuclear Information System (INIS)

Corwin, W.R.

1995-03-01

Maintaining the integrity of the reactor pressure vessel (RPV) in a light-water-cooled nuclear power plant is crucial in preventing and controlling severe accidents which have the potential for major contamination release. The RPV is the only key safety-related component of the plant for which a duplicate or redundant backup system does not exist. In particular, it is vital to fully understand the degree of irradiation-induced degradation of the RPV's fracture resistance which occurs during service, since without that radiation damage, it is virtually impossible to postulate a realistic scenario that would result in RPV failure. For this reason, the Heavy-Section Steel Irradiation (HSSI) Program has been established to provide a quantitative assessment of the effects of neutron irradiation on the material behavior and, in particular, the fracture toughness properties of typical pressure-vessel steels. Effects of specimen size; material chemistry; product form and microstructure; irradiation fluence, flux, temperature, and spectrum; and postirradiation annealing are being examined on a wide range of fracture properties. The HSSI Program is arranged into 14 tasks: (1) program management, (2) fracture toughness (K lc ) curve shift in high-copper welds, (3) crack-arrest toughness (K la ) curve shift in high-copper welds, (4) irradiation effects on cladding, (5) K lc and K la curve shifts in low upper-shelf (LUS) welds, (6) annealing effects in LUS welds, (7) irradiation effects in a commercial LUS weld, (8) microstructural analysis of irradiation effects, (9) in-service aged material evaluations, (10) correlation monitor materials, (11) special technical assistance, (12) Japan Power Development Reactor steel examination, (13) technical assistance for Joint Coordinating Committee on Civilian Nuclear Reactor Safety (JCCCNRS) Working Groups 3 and 12, and (14) additional requirements for materials

SISTEM PENDUKUNG KEPUTUSAN UNTUK MENGEVALUASI INTERNAL PROGRAM STUDI

Directory of Open Access Journals (Sweden)

Indhitya Rahman Padiku

2016-04-01

Full Text Available The development of major and study program cannot be separated by some internal factors weather directly influenced number of new registration students or indirectly. It needs a method to both know and to analyze internal evaluation variables in major or study program. Naive Bayes Clasifier (NBC method is the simple form of Bayesian network that assume all features are independent each other. NBC shows us a great performance entirely in accuracy and error level classification. NBC is able to differentiate irrelevance attribute and also classified some attributes in prediction needs. This research hopefully can be useful for major internal evaluating and study program in order to increase the number of new registration students. The classification by influenced of variables to evaluate the condition of both major and study program for the new registration students.

Quality assurance for the IAEA International Database on Irradiated Nuclear Graphite Properties

International Nuclear Information System (INIS)

Wickham, A.J.; Humbert, D.

2006-06-01

Consideration has been given to the process of Quality Assurance applied to data entered into current versions of the IAEA International Database on Irradiated Nuclear Graphite Properties. Originally conceived simply as a means of collecting and preserving data on irradiation experiments and reactor operation, the data are increasingly being utilised for the preparation of safety arguments and in the design of new graphites for forthcoming generations of graphite-moderated plant. Under these circumstances, regulatory agencies require assurances that the data are of appropriate accuracy and correctly transcribed, that obvious errors in the original documentation are either highlighted or corrected, etc., before they are prepared to accept analyses built upon these data. The processes employed in the data transcription are described in this document, and proposals are made for the categorisation of data and for error reporting by Database users. (author)

Food problems and food irradiation, recent trend

International Nuclear Information System (INIS)

1990-01-01

Food irradiation is to contribute to the stable security of foodstuffs which is the fundamental condition of human survival by improving the preservation of foodstuffs and food sanitation utilizing the biological effect due to irradiation. The research and development have been carried out internationally since 1950s, but after the safety declaration of irradiated foods in 1980 by the international organ concerned, the permission and practical use for foods in various foreign countries, the technology transfer to developing countries and so on have been advanced. At present, food irradiation is permitted in 38 countries, and the practical irradiation is carried out in 24 countries. In Japan, the irradiation of potatoes to prevent germination was permitted in 1972, and the practical irradiation on potatoes of yearly 15,000 t is carried out. In the near future, irradiated foods will appear in international foodstuff market, and Japan which imports foodstuffs must cope with them. Foodstuffs and the safety, food irradiation, the soundness of irradiated foods, food irradiation in various foreign countries and Japan, the trend of international organs and the criticism of food irradiation are reported. (K.I.)

Mitigation of radiation nephropathy after internal α-particle irradiation of kidneys

International Nuclear Information System (INIS)

Jaggi, Jaspreet Singh; Seshan, Surya V.; McDevitt, Michael R.; Sgouros, George; Hyjek, Elizabeth; Scheinberg, David A.

2006-01-01

Purpose: Internal irradiation of kidneys as a consequence of radioimmunotherapy, radiation accidents, or nuclear terrorism can result in radiation nephropathy. We attempted to modify pharmacologically, the functional and morphologic changes in mouse kidneys after injection with the actinium ( 225 Ac) nanogenerator, an in vivo generator of α- and β-particle emitting elements. Methods and Materials: The animals were injected with 0.35 μCi of the 225 Ac nanogenerator, which delivers a dose of 27.6 Gy to the kidneys. Then, they were randomized to receive captopril (angiotensin-converting enzyme inhibitor), L-158,809 (angiotensin II receptor-1 blocker), spironolactone (aldosterone receptor antagonist), or a placebo. Results: Forty weeks after the 225 Ac injection, the placebo-control mice showed a significant increase in blood urea nitrogen (BUN) (87.6 ± 6.9 mg/dL), dilated Bowman spaces, and tubulolysis with basement membrane thickening. Captopril treatment accentuated the functional (BUN 119.0 ± 4.0 mg/dL; p <0.01 vs. placebo controls) and histopathologic damage. In contrast, L-158,809 offered moderate protection (BUN 66.6 ± 3.9 mg/dL; p = 0.02 vs. placebo controls). Spironolactone treatment, however, significantly prevented the development of histopathologic and functional changes (BUN 31.2 ± 2.5 mg/dL; p <0.001 vs. placebo controls). Conclusions: Low-dose spironolactone and, to a lesser extent, angiotensin receptor-1 blockade can offer renal protection in a mouse model of internal α-particle irradiation

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

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

Hanford Internal Dosimetry Program Manual, PNL-MA-552

Energy Technology Data Exchange (ETDEWEB)

Carbaugh, Eugene H.; Bihl, Donald E.; Maclellan, Jay A.

2009-09-24

This manual is a guide to the services provided by the Hanford Internal Dosimetry Program (IDP), which is operated by the Pacific Northwest National Laboratory.( ) for the U.S. Department of Energy Richland Operations Office, Office of River Protection and their Hanford Site contractors. The manual describes the roles of and relationships between the IDP and the radiation protection programs of the Hanford Site contractors. Recommendations and guidance are also provided for consideration in implementing bioassay monitoring and internal dosimetry elements of radiation protection programs.

Saturation behavior of irradiation hardening in F82H irradiated in the HFIR

Energy Technology Data Exchange (ETDEWEB)

Hirose, T. [Blanket Engineering Group, Japan Atomic Energy Agency, Naka, Ibaraki (Japan); Shiba, K.; Tanigawa, H.; Ando, M. [Japan Atomic Energy Agency, Tokai-mura, Naga-gun, Ibaraki-ken (Japan); Klueh, R.L. [Oak Ridge National Laboratory, TN (United States); Stoller, R. [ORNL - Oak Ridge National Laboratory, Materials Science and Technology Div., Oak Ridge, AK TN (United States)

2007-07-01

Full text of publication follows: Post irradiation tensile tests on reduced activation ferritic/martensitic steel, F82H have been conducted over the past two decades using Japan Materials Testing Reactor (JMTR) of JAEA, and Fast Flux Testing Facility (FFTF) of PNNL and High Flux Isotope Reactor (HFIR) of ORNL, USA, under Japan/US collaboration programs. According to these results, F82H does not demonstrate irradiation hardening above 673 K up to 60 dpa. The current study has been concentrated on hardening behavior at temperature around 573 K. A series of low temperature irradiation experiment has been conducted at the HFIR under the international collaborative research between JAEA/US-DOE. In this collaboration, the irradiation condition is precisely controlled by the well matured capsule designing and instrumentation. This paper summarizes recent results of the irradiation experiments focused on F82H and its modified steels compared with the irradiation properties database on F82H. Post irradiation tensile tests have been conducted on the F82H and its modified steels irradiated at 573 K and the dose level was up to 25 dpa. According to these results, irradiation hardening of F82H is saturated by 9 dpa and the as-irradiated 0.2 % proof stress is less than 1 GPa at ambient temperature. The deterioration of total elongation was also saturated by 9 dpa irradiation. The ductility of some modified steels which showed larger total elongation than that of F82H before irradiation become the same level as that of standard F82H steel after irradiation, even though its magnitude of irradiation hardening is smaller than that of F82H. This suggests that the more ductile steel demonstrates the more ductility loss at this temperature, regardless to the hardening level. The difference in ductility loss behavior between various tensile specimens will be discussed as the ductility could depend on the specimen dimension. (authors)

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.)

Peculiarities of intestine injuries in case of internal and external irradiation: a morphometric study

International Nuclear Information System (INIS)

Ponomareva, T.V.

1988-01-01

It is shown that sterological cell parameters and indexes of their interaction may serve as an important characteristic of tissue postirradiation recovery quality permitting to give a precise quantitative characteristic of cell differentiation and dedifferentiation. It is established that enterocyte maturation is sharphy broken under irradiation. Population delamination into sublines differing in cell size takes place. The number of these cells depends on radiation doses. The most labile cell componenet is cell nucleoli. The cell differentiation breakage is more pronounced in case of internal irradiation (Ce 144 ) and in combined radiation effect. A degree of cell differentiation breakage depends on peroxidation level. The obtained data can be used in developing and evaluating radioprotective substances

Heavy-Section Steel Irradiation Program. Volume 2, No. 1: Semiannual progress report, October 1990--March 1991

International Nuclear Information System (INIS)

Corwin, W.R.

1994-07-01

Maintaining the integrity of the reactor pressure vessel (RPV) in a light-water-cooled nuclear power plant is crucial in preventing and controlling severe accidents that have the potential for major contamination release. The RPV is the only key safety-related component of the plant for which a duplicate or redundant backup system does not exist. It is therefore imperative to understand and be able to predict the capabilities and limitations of the integrity inherent in the RPV. For this reason, the Heavy-Section Steel Irradiation (HSSI) Program has been established with its primary goal to provide a thorough, quantitative assessment of the effects of neutron irradiation on the material behavior, and in particular the fracture toughness properties, of typical pressure-vessel steels as they relate to light-water reactor pressure-vessel integrity. The HSSI Program is arranged into nine tasks: (1) program management, (2) K ic curve shift in high-copper welds, (3) K ia curve shift in high-copper welds, (4) irradiation effects on cladding, (5) K ic and K ia curve shifts in low upper-shelf (LUS) weld, (6) irradiation effects in a commercial LUS weld, (7) microstructural analysis of irradiation, (8) in-service aged material evaluations, and (9) correlation monitor materials. During this period, additional analyses on the effects of precleavage stable ductile tearing on the toughness of high-copper welds 72W and 73W demonstrated that the size effects observed in the transition region are not due to substantial differences in ductile tearing behavior. Possible modifications to irradiated duplex crack-arrest specimens were examined to increase the likelihood of their successful testing. Characterization of a second batch of 72W and 73W welds was begun and results of the Charpy V-notch testing is provided. A review of literature on the annealing response of reactor pressure vessel steels was initiated

Influence of geometrical parameters of the VVER-1000 reactor construction elements to internals irradiation conditions

Directory of Open Access Journals (Sweden)

О. M. Pugach

2015-07-01

Full Text Available Investigations to determine the influences of geometrical parameters of the calculational VVER-1000 reactor model to the results of internal irradiation condition determination are carried out. It is shown that the values of appropriate sensitivity matrix elements are not dependent on a height coordinate for any core level, but there is their azimuthal dependence. Maximum possible relative biases of neutron fluence due to inexact knowledge of internal geometrical parameters are obtained for the baffle and the barrel.

Practical implications for RPV irradiation surveillance under long term operation based on latest research results

International Nuclear Information System (INIS)

Hein, H.; Keim, E.; Barthelmes, J.; Schnabel, H.

2015-01-01

The international programs CARISMA, CARINA and LONGLIFE belong to the research programs which have been performed during the last 10 years to study the irradiation behavior of RPV steels under long term operation of more than 60 years. Some characteristic but different irradiated RPV steels used in Pressurized Water Reactors have been extensively investigated in each of those three programs. Whereas the CARISMA and CARINA programs were mainly focused on material testing to study the irradiation-induced change of material properties in terms of fracture toughness, the main objective of LONGLIFE was to investigate the change of microstructure with various analysis techniques and to understand the mechanisms behind. In this way it was possible to get a comprehensive material characterization in terms of macro-physical properties and micro-structural features for a number of RPV steels which have been studied at different irradiation levels up to 8*10 19 cm -2 (E > 1 MeV). The essential macro-physical and micro-structural results are summarized, in particular regarding the impact of copper and nickel, and the neutron flux on the irradiation behavior and with respect to possible late irradiation effects under long term operation. Moreover, the change of material properties is linked with embrittlement mechanisms such as formation of element specific precipitations, segregations, and matrix defects. Well-known trend curves are also applied to the measured T 41 and T 0 data in order to assess their appropriateness for long term operation. Based on the comprehensive available data base, practical implications for RPV irradiation surveillance programs under long term operation are highlighted with respect to issues like material specific application of reference temperature concepts, data scattering, prediction of high fluence behavior and how to cope with possible late irradiation effects. Finally, best practices for RPV irradiation surveillance programs are suggested from

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)

International Mentoring Programs: Leadership Opportunities to Enhance Worldwide Pharmacy Practice.

Science.gov (United States)

Ubaka, Chukwuemeka; Brechtelsbauer, Erich; Goff, Debra A

2017-07-01

Health-system and community pharmacy practice in the United States is experiencing transformational change; however, this transformation is lagging in the international arena. As a result, efforts are being made to provide support and education to the international pharmacy leaders and practitioners. This article describes one effort, the Mandela Washington Fellows Program, and suggests areas where pharmacy leaders can be involved to help advance the practice of pharmacy on an international level. The Mandela Washington Fellows Program for young Africa leaders consists of a US-Africa pharmacy-mentoring program identified ranging from educational opportunities to collaboration for implementation of patient care programs. The specifics of the mentoring program include daily meetings, clinic and ward rounds, round table discussions with mentors, and visits to various hospital care systems. Lessons were learned and strategies for sustaining the program are discussed. These types of programs represent leadership opportunities that may not be apparent to most pharmacy directors, but expanding their view to helping international pharmacists expand their practice only strengthens the professional goal of providing patient-centered pharmacy services.

Undergraduate International Studies and Foreign Language Program

Science.gov (United States)

Office of Postsecondary Education, US Department of Education, 2012

2012-01-01

The Undergraduate International Studies and Foreign Language Program provides funds to institutions of higher education, a consortia of such institutions, or partnerships between nonprofit organizations and institutions of higher education to plan, develop, and implement programs that strengthen and improve undergraduate instruction in…

Use of studies with laboratory animals to assess the potential early health effects of combined internal alpha and beta irradiation

International Nuclear Information System (INIS)

Scott, B.R.; Hahn, F.F.; Guilmette, R.A.; Muggenburg, B.A.; Snipes, M.B.; Boecker, B.B.; McClellan, R.O.

1986-01-01

The potential health impacts of radionuclides released in nuclear accidents are of major concern to the public and to regulatory and other governmental agencies. One mode of potential exposure is by inhalation of airborne radionuclides, which could lead to combined internal irradiation by high (alpha) and low (beta) linear energy transfer (LET) radiations. Epidemiological data for health effects of human inhalation exposure are too limited to derive reliable estimates of risks of potential health effects. However, results of studies in which beagle dogs were exposed by inhalation to insoluble radioactive aerosols can be used to estimate expected effects in humans. Data for mortality from radiation pneumonitis and pulmonary fibrosis caused by internal irradiation of dog lungs by alpha or beta radiations are used to derive the relative biological effectiveness (RBE) of alpha irradiation compared to beta irradiation; predict the expected combined effects of alpha and beta irradiation of dog lungs; and extrapolate the results to humans. The extrapolation to humans assumed that, for similar ages at exposure, dog and human lungs have similar sensitivities to lung irradiation. Results of theoretical calculations related to mortality from early effects indicated that the synergistic effects of high- and low-LET radiations should depend on the percentages of the total dose contributed by high- and low-LET radiations, and for very low or very high doses, synergistic effects should be negligible. 23 refs., 8 figs

Executive strategy plan for beneficial uses program: cesium-137 sewage sludge irradiation

International Nuclear Information System (INIS)

1981-07-01

Energy-efficient disinfection of sewage sludge, permitting its use as a fertilizer and soil conditioner in areas open to public access or on certain food chain crops, is possible using the process technology developed by Sandia National Laboratories under DOE and EPA joint support. This process accomplishes disinfection by gamma ray irradiation with cesium-137, a by-product isotope recovered from reprocessing of defense production waste. Disinfection with cesium-137 gamma irradiation provides an energy-efficient option for the Nation's cities to beneficially utilize sewage sludge, while at the same time conserving energy by utilizing a radioisotope, traditionally considered waste, in a beneficial manner. While the Sandia sludge irradiation technology has successfully completed its research and development phase, a major consideration remains: the introduction of a new technology into a marketplace which traditionally is skeptical of new products or process technologies until their performance is well proven. This document analyzes the factors important to market introduction of this new technology, develops options, and recommends a program strategy for transfer of the Sandia sludge irradiation technology to the marketplace by developing public awareness and acceptance, and by stimulating private sector commercialization interest

International program activities in magnetic fusion energy

International Nuclear Information System (INIS)

1986-03-01

The following areas of our international activities in magnetic fusion are briefly described: (1) policy; (2) background; (3) strategy; (4) strategic considerations and concerns; (5) domestic program inplications, and (6) implementation. The current US activities are reviewed. Some of our present program needs are outlined

Organizational Structures that Support Internal Program Evaluation

Science.gov (United States)

Lambur, Michael T.

2008-01-01

This chapter explores how the structure of large complex organizations such as Cooperative Extension affects their ability to support internal evaluation of their programs and activities. Following a literature review of organizational structure and its relation to internal evaluation capacity, the chapter presents the results of interviews with…

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.

An overview of the Cooperative IASCC Research (CIR) program

International Nuclear Information System (INIS)

Pathania, R.; Gott, K.; Scott, P.

2007-01-01

Irradiation-Assisted Stress Corrosion Cracking (IASCC) has affected reactor core internal structures fabricated from austenitic stainless steels in both Pressurized Water Reactors (PWR) and Boiling Water Reactors (BWR). The Cooperative IASCC Research (CIR) Program is an international research effort designed to address irradiation-assisted stress corrosion cracking (IASCC) in light water reactor (LWR) components. The objectives of the CIR program are to develop a mechanistic understanding of IASCC initiation and crack growth, to derive a predictive model of IASCC, if possible based on a mechanistic understanding, and thus to identify possible countermeasures to IASCC. It complements other more applied programs by concentrating on the underlying physical causes of IASCC. This paper provides an overview of the current status and achievements of the CIR program, which has been running since 1995. Two phases of the program have been completed and a final extension program is in progress which is scheduled to finish in 2008. The extent to which the CIR program has met its objectives, or will meet them with its current plans extending into 2008, is assessed. (author)

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)

Second program of materials irradiation within VISA-2 Project, Parts I-II, Part I; Drugi program ozracivanja materijala po projektu VISA-2, I-II Deo, I Deo

Energy Technology Data Exchange (ETDEWEB)

Pavicevic, M; Smokovic, Z [Institute of Nuclear Sciences Boris Kidric, Odeljenje za reaktorsku eksperimentalnu tehniku, Vinca, Beograd (Serbia and Montenegro)

1965-03-15

This second program of irradiating the materials in special VISA-2 experimental channels includes irradiation of 8 capsules with French graphite, magnesium and aluminium oxides, zircaloy, leak tight capsules with Zirconium and steel samples; capsules with domestic graphite, iron, domestic steel and molybdenum samples. The samples are irradiated in the integral fast neutron flux of 2 10{sup 20} n/cm{sup 2}. Temperature of the samples is measured continuously. This task includes activities which are necessary for completing the irradiation procedures.

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

A Comprehensive Wellness Program for International Students.

Science.gov (United States)

Fisher, Millard J.; Ozaki, Roger H.

This document presents a model wellness program for international college students in the United States and strategies to aid them in staying healthy during their stay. It notes that, without parents or other support groups, international students run the risk of developing serious health problems because of inadequate diet and sleep, substandard…

34 CFR 655.3 - What regulations apply to the International Education Programs?

Science.gov (United States)

2010-07-01

... Foreign Language and Area Studies or Foreign Language and International Studies); (2) 34 CFR part 657 (Foreign Language and Area Studies Fellowships Program); (3) 34 CFR part 658 (Undergraduate International Studies and Foreign Language Program); (4) 34 CFR part 660 (International Research and Studies Program...

NASA and the Federal Management Intern Program.

Science.gov (United States)

Pound, Jack K.; Slack, Vivian M.

A review of NASA Federal Management Intern (MI) programs indicates potential for identification, attraction, and early development of successful administrative management employees, but suggests that successful development of managers is a function of the long-term care with which an agency pursues MI programs. A recent study of separations in…

Complications related to conventional self-expandable metal stent insertion and internal irradiation stent insertion in patients with advanced esophageal carcinoma: an analysis of 32 cases

International Nuclear Information System (INIS)

Xu Xingwen; Di Haiting; Zhu Jun; Shi Jian

2011-01-01

Objective: To compare the occurrence of complications between conventional self-expandable metal stent and internal irradiation stent insertion in treating patients with advanced esophageal carcinomas. Methods: A total of 32 patients with advanced esophageal carcinoma were randomly divided into irradiation stent group (n=15) and conventional stent group (n=17). Internal irradiation stent loaded with 125 I seeds was employed in patients of irradiation stent group, while conventional self-expandable metal stent was used in patients of conventional stent group. After the treatment, clinical follow-up was regularly conducted. Postoperative complications such as fever, severe chest pain, cough, esophageal perforation, pneumonia, hemorrhage, stent migration and restenosis, etc. were observed. Results: No significant difference in the occurrence of fever, severe chest pain, esophageal perforation and hemorrhage existed between the two groups (P>0.05). The difference in the occurrence of long-term complications such as stent migration or restenosis between the two groups was out statistically significant (P>0.05). However, the restenosis in irradiation stent group occurred obviously much later than that in conventional stent group. Conclusion: For the treatment of advanced esophageal carcinomas, the insertion of internal irradiation esophageal stent is safe. It dose not increase the incidence of postoperative complications. Therefore, it is worth popularizing this technique in clinical practice. (authors)

Literature study of the radiobiological parameters of Caesium-137 required for evaluating internal irradiation doses as a function of age

International Nuclear Information System (INIS)

Garnier, A.

1968-01-01

This document reassembles information published in scientific literature on radiobiological parameters of Cs-137, necessary for the estimate of the internal irradiation dose of man according to his age (during growth). The data are completed by a commented review of the mathematical models, proposed in order to value the irradiation doses from ingested cesium and the biological parameters. (author) [fr

The future Jules Horowitz material test reactor: A major European research infrastructure for sustaining the international irradiation capacity

International Nuclear Information System (INIS)

Parrat, D.; Bignan, G.; Chauvin, J.; Gonnier, C.

2011-01-01

Multipurpose experimental reactors are now key infrastructures, in complement of prediction capabilities gained thanks to progresses in the modelling, for supporting nuclear energy in terms of safety, ageing management, innovation capacity, economical performances and training. However the European situation in this field is characterized by ageing large infrastructures, which could face to operational issues in the coming years and could jeopardize the knowledge acquisition and the nuclear product qualification. Moreover some specific supplies related to the public demand could be strongly affected (e.g. radiopharmaceutical targets). To avoid a lack in the experimental capacity offer at the European level, the CEA has launched the Jules Horowitz material test reactor (JHR) international program, in the frame of a Consortium gathering EDF (FR), AREVA (FR), the European Commission (EU), SCK.CEN (BE), VTT (FI), CIEMAT (SP), VATTENFALL (SE), UJV (CZ), JAEA (JP) and the DAE (IN). The JHR will be a 100 MW tank pool reactor and will have several experimental locations either inside the reactor core or outside the reactor tank in a reflector constituted by beryllium blocks. Excavation works started mid-2007 on the CEA Cadarache site in the southeast of France. After the construction permit delivery gained in September 2007, building construction began at the beginning of 2009. Reactor start-up is scheduled in 2016. The JHR is designed to offer up-to-date irradiation experimental capabilities for studying nuclear material and fuel behaviour under irradiation in a modern safety frame, mainly due to: 1) High values of fast and thermal neutron fluxes in the core and high thermal neutron flux in the reflector (producing typically twice more material damages per year than available today in European MTRs); 2) A large variety of experimental devices capable to reproduce environment conditions of mainly light water reactors (LWRs) and sodium fast reactors; 3) Several equipment

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)

[Resource allocation analysis for international cooperation program for HIV/AIDS prevention and control].

Science.gov (United States)

Li, Hui; Xue, Hui; Liu, Hui; Guo, Hao-yan; Zhang, Hua; Sun, Jiang-ping

2008-12-01

To provide evidence for resource allocation and cooperation between domestic and international HIV/AIDS programs in China by analyzing the needs and current levels of resource input in provinces. National and provincial international cooperation program investment and allocation data from 2000 to 2006 were collected. Several factors in each province were analyzed through multiple regression analysis in order to determine whether they had a statistical correlation to the distribution of international HIV/AIDS program resources in China, including: the Gross Domestic Product (GDP), the number of accumulated people living with HIV/AIDS, and the number of accumulated people living with AIDS. Then the Z values were calculated at each provincial level and compared with related international investment. The resource allocation in different program areas were compared with the level of resource input by international and central government HIV/AIDS prevention and control programs through Chi-square test. The international cooperation program investment at local level from 2000 to 2006 were 4893, 24 669, 50 567, 52 950, 112 143, 363 396 and 247 045 thousand RMB respectively, and at national level were 3007, 19 726, 29 035, 37 530, 77 500, 105 786 and 77 035 thousand RMB respectively. There was a statistical correlation between international HIV/AIDS program resource input and the accumulated number of people living with AIDS (R is 0.56 and 0.69 accordingly, and P international resource input and the GDP of each province. International HIV/AIDS cooperation programs did not invest in each province according to its practical needs (R = 0.066, P = 0.725). The international cooperation program investments and needs in different province could not meet completely. The ranks of Z value in Guangdong, Shandong and Jiangsu were 3, 5 and 6, but the ranks of international cooperation program in those provinces were 18, 13 and 28 respectively. The investment proportion for national

Ten years of Developing International Volcanology Graduate Study Programs

Science.gov (United States)

Rose, W. I.

2010-12-01

In 2000 I reported at this symposium about multi-institutional graduate field trips to IAVCEI events, such as the Bali meeting and its importance in building international collegiality and awareness among the volcanology doctoral students. NSF was an enthusiastic supporter of these field sessions and this support has continued through the highly successful Pucon and Reykjavik sessions. International volcanology graduate program development began with several exchange programs. EHaz was a highly successful program (McGill, Simon Fraser, Michigan Tech, Buffalo, UNAM and Universidad de Colima) funded by the Department of Education (FIPSE) that moved students across North America where dozens of graduate students spent semesters of their study abroad and shared annual field trips and online student led graduate seminar classes. Michigan Tech’s volcanology graduate program started a Masters International program that combined Peace Corps service with hazards mitigation graduate study and students were placed by Peace Corps in countries with prominent natural hazards. The new program funded 2 year residences in foreign environments, principally in Pacific Latin America. NSF strongly supported this program from its inception, and eventually it gained NSF PIRE support. Dozens of students have initiated the 3 year program (15 completed) to date. A similar PIRE developed at UAF with a link to volcanology in the Russian Far East. One gain is the development of many socially-conscious research selections. Beginning this year transatlantic dual degree masters programs in volcanology are being offered by a consortium of US and European volcanology programs (Michigan Tech, Buffalo, Clermont Ferrand and University of Milan Bicocca), again aided by FIPSE funding. Students have dual advisors on both sides of the Atlantic and spend about half of their two year programs in Europe and half in US. Faculty also travel in the program and the four campuses are increasingly linked by

Associations between quality indicators of internal medicine residency training programs

Science.gov (United States)

2011-01-01

Background Several residency program characteristics have been suggested as measures of program quality, but associations between these measures are unknown. We set out to determine associations between these potential measures of program quality. Methods Survey of internal medicine residency programs that shared an online ambulatory curriculum on hospital type, faculty size, number of trainees, proportion of international medical graduate (IMG) trainees, Internal Medicine In-Training Examination (IM-ITE) scores, three-year American Board of Internal Medicine Certifying Examination (ABIM-CE) first-try pass rates, Residency Review Committee-Internal Medicine (RRC-IM) certification length, program director clinical duties, and use of pharmaceutical funding to support education. Associations assessed using Chi-square, Spearman rank correlation, univariate and multivariable linear regression. Results Fifty one of 67 programs responded (response rate 76.1%), including 29 (56.9%) community teaching and 17 (33.3%) university hospitals, with a mean of 68 trainees and 101 faculty. Forty four percent of trainees were IMGs. The average post-graduate year (PGY)-2 IM-ITE raw score was 63.1, which was 66.8 for PGY3s. Average 3-year ABIM-CE pass rate was 95.8%; average RRC-IM certification was 4.3 years. ABIM-CE results, IM-ITE results, and length of RRC-IM certification were strongly associated with each other (p ITE scores were higher in programs with more IMGs and in programs that accepted pharmaceutical support (p < 0.05). RRC-IM certification was shorter in programs with higher numbers of IMGs. In multivariable analysis, a higher proportion of IMGs was associated with 1.17 years shorter RRC accreditation. Conclusions Associations between quality indicators are complex, but suggest that the presence of IMGs is associated with better performance on standardized tests but decreased duration of RRC-IM certification. PMID:21651768

Advanced Post-Irradiation Examination Capabilities Alternatives Analysis Report

Energy Technology Data Exchange (ETDEWEB)

Jeff Bryan; Bill Landman; Porter Hill

2012-12-01

An alternatives analysis was performed for the Advanced Post-Irradiation Capabilities (APIEC) project in accordance with the U.S. Department of Energy (DOE) Order DOE O 413.3B, “Program and Project Management for the Acquisition of Capital Assets”. The Alternatives Analysis considered six major alternatives: ? No Action ? Modify Existing DOE Facilities – capabilities distributed among multiple locations ? Modify Existing DOE Facilities – capabilities consolidated at a few locations ? Construct New Facility ? Commercial Partnership ? International Partnerships Based on the alternatives analysis documented herein, it is recommended to DOE that the advanced post-irradiation examination capabilities be provided by a new facility constructed at the Materials and Fuels Complex at the Idaho National Laboratory.

Quality assurance program of a respiratory gating irradiation system based on external and internal fiducial markers; Programa de garantia de calidad de un sistema de irradiacion con control respiratorio basado en marcadores fiduciales externos e internos

Energy Technology Data Exchange (ETDEWEB)

Zucca Aparicio, D.; Perez Moreno, J. M.; Fernandez Leton, P.; Garcia Ruiz-Zorrilla, J.; Minambres Moro, A.

2011-07-01

Respiratory Gating involves the administration of radiation during treatment delivery within a particular portion of the patients breathing cycle, so the absorbed dose administration with respiratory control techniques requires specific quality control to ensure the correctness of the delivered dose. The establishment of a Quality Control Program (QC) is proposed for the Respiratory Gating based techniques in order to have a better understanding of how this system works and to know its associated dosimetric impact. The influence of the CT acquisition under respiratory motion conditions has been analyzed for the treatment isocenter localization, using internal and external fiducial markers with IGRT techniques that allow the correlation of the isocenter positioning with the phase of the respiratory cycle. Radiation delivery in the presence of intra fraction organ motion causes an averaging or blurring of the static dose distribution over the path of motion increasing the beam penumbra of the radiation field and reducing the therapeutic region when the irradiation is not breath controlled. The feasibility of intensity modulated treatments (IMRT) for both static and dynamic techniques, managed by respiratory control has been tested, demonstrating the possibility of synchronizing the movement of the leaves in the microfluorimeter collimator (mMLC) with the gated beam irradiation. (Author) 45 refs.

Simulation of gamma-ray irradiation of lettuce leaves in a 137Cs irradiator using MCNP

International Nuclear Information System (INIS)

Kim, Jongsoon; Moreira, Rosana G.; Braby, Leslie A.

2010-01-01

Ionizing radiation effectively reduces the number of common microbial pathogens in fresh produce. However, the efficacy of the process for pathogens internalized into produce tissue is unknown. The objective of this study was to understand gamma irradiation of lettuce leaf structure exposed in a 137 Cs irradiator using MCNP. The simulated 137 Cs irradiator is a self-shielded device, and its geometry and sources are described in the MCNP input file. When the irradiation chamber is filled with water, lower doses are found at the center of the irradiation volume and the dose uniformity ratio (maximum dose/minimum dose) is 1.76. For randomly oriented rectangular lettuce leaf segments in the irradiation chamber, the dose uniformity ratio is 1.25. It shows that dose uniformity in the Cs irradiator is strongly dependent of the density of the sample. To understand dose distribution inside the leaf, we divided a lettuce leaf into a low density (flat) region (0.72 g/cm 3 ) and high density (rib) region (0.86 g/cm 3 ). Calculated doses to the rib are 61% higher than doses to the flat region of the leaf. This indicates that internalized microorganisms can be inactivated more easily than organisms on the surface. This study shows that irradiation can effectively reduce viable microorganism internalized in lettuce. (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...

Second program of materials irradiation within VISA-2 Project, Parts I-II, Part II; Drugi program ozracivanja materijala po projektu VISA-2, I-II Deo, II Deo

Energy Technology Data Exchange (ETDEWEB)

Pavicevic, M; Smokovic, Z [Institute of Nuclear Sciences Boris Kidric, Odeljenje za reaktorsku eksperimentalnu tehniku, Vinca, Beograd (Serbia and Montenegro)

1965-03-15

This second program of irradiating the materials in special VISA-2 experimental channels includes irradiation of 8 capsules with French graphite, magnesium and aluminium oxides, zircaloy, leak tight capsules with Zirconium and steel samples; capsules with domestic graphite, iron, domestic steel and molybdenum samples. This volume of the report includes design specification and engineering drawings of VISA-2 different irradiation capsules to be used and of the devices needed for completing the task.

US/Japan collaborative program on fusion reactor materials: Summary of the tenth DOE/JAERI Annex I technical progress meeting on neutron irradiation effects in first wall and blanket structural materials

International Nuclear Information System (INIS)

Rowcliffe, A.F.

1989-01-01

This meeting was held at Oak Ridge National Laboratory on March 17, 1989, to review the technical progress on the collaborative DOE/JAERI program on fusion reactor materials. The purpose of the program is to determine the effects of neutron irradiation on the mechanical behavior and dimensional stability of US and Japanese austenitic stainless steels. Phase I of the program focused on the effects of high concentrations of helium on the tensile, fatigue, and swelling properties of both US and Japanese alloys. In Phase II of the program, spectral and isotropic tailoring techniques are fully utilized to reproduce the helium:dpa ratio typical of the fusion environment. The Phase II program hinges on a restart of the High Flux Isotope Reactor by mid-1989. Eight target position capsules and two RB* position capsules have been assembled. The target capsule experiments will address issues relating to the performance of austenitic steels at high damage levels including an assessment of the performance of a variety of weld materials. The RB* capsules will provide a unique and important set of data on the behavior of austenitic steels irradiated under conditions which reproduce the damage rate, dose, temperature, and helium generation rate expected in the first wall and blanket structure of the International Thermonuclear Experimental Reactor

Food irradiation makes progress

International Nuclear Information System (INIS)

Kooij, J. van

1984-01-01

In the past fifteen years, food irradiation processing policies and programmes have been developed both by a number of individual countries, and through projects supported by FAO, IAEA and WHO. These aim at achieving general acceptance and practical implementation of food irradiation through rigorous investigations of its wholesomeness, technological and economic feasibility, and efforts to achieve the unimpeded movement of irradiated foods in international trade. Food irradiation processing has many uses

Ten-Year Survival Results of a Randomized Trial of Irradiation of Internal Mammary Nodes After Mastectomy

International Nuclear Information System (INIS)

Hennequin, Christophe; Bossard, Nadine; Servagi-Vernat, Stéphanie; Maingon, Philippe; Dubois, Jean-Bernard; Datchary, Jean; Carrie, Christian; Roullet, Bernard; Suchaud, Jean-Philippe; Teissier, Eric; Lucardi, Audrey; Gerard, Jean-Pierre; Belot, Aurélien

2013-01-01

Purpose: To evaluate the efficacy of irradiation of internal mammary nodes (IMN) on 10-year overall survival in breast cancer patients after mastectomy. Methods and Patients: This multicenter phase 3 study enrolled patients with positive axillary nodes (pN+) or central/medial tumors with or without pN+. Other inclusion criteria were age <75 and a Karnofsky index ≥70. All patients received postoperative irradiation of the chest wall and supraclavicular nodes and were randomly assigned to receive IMN irradiation or not. Randomization was stratified by tumor location (medial/central or lateral), axillary lymph node status, and adjuvant therapy (chemotherapy vs no chemotherapy). The prescribed dose of irradiation to the target volumes was 50 Gy or equivalent. The first 5 intercostal spaces were included in the IMN target volume, and two-thirds of the dose (31.5 Gy) was given by electrons. The primary outcome was overall survival at 10 years. Disease-free survival and toxicity were secondary outcomes. Results: T total of 1334 patients were analyzed after a median follow-up of 11.3 years among the survivors. No benefit of IMN irradiation on the overall survival could be demonstrated: the 10-year overall survival was 59.3% in the IMN-nonirradiated group versus 62.6% in the IMN-irradiated group (P=.8). According to stratification factors, we defined 6 subgroups (medial/central or lateral tumor, pN0 [only for medial/central] or pN+, and chemotherapy or not). In all these subgroups, IMN irradiation did not significantly improve overall survival. Conclusions: In patients treated with 2-dimensional techniques, we failed to demonstrate a survival benefit for IMN irradiation. This study cannot rule out a moderate benefit, especially with more modern, conformal techniques applied to a higher risk population

AGC-2 Irradiation Report

Energy Technology Data Exchange (ETDEWEB)

Rohrbaugh, David Thomas [Idaho National Lab. (INL), Idaho Falls, ID (United States); Windes, William [Idaho National Lab. (INL), Idaho Falls, ID (United States); Swank, W. David [Idaho National Lab. (INL), Idaho Falls, ID (United States)

2016-06-01

The Next Generation Nuclear Plant (NGNP) will be a helium-cooled, very high temperature reactor (VHTR) with a large graphite core. In past applications, graphite has been used effectively as a structural and moderator material in both research and commercial high temperature gas cooled reactor (HTGR) designs.[ , ] Nuclear graphite H 451, used previously in the United States for nuclear reactor graphite components, is no longer available. New nuclear graphites have been developed and are considered suitable candidates for the new NGNP reactor design. To support the design and licensing of NGNP core components within a commercial reactor, a complete properties database must be developed for these current grades of graphite. Quantitative data on in service material performance are required for the physical, mechanical, and thermal properties of each graphite grade with a specific emphasis on data related to the life limiting effects of irradiation creep on key physical properties of the NGNP candidate graphites. Based on experience with previous graphite core components, the phenomenon of irradiation induced creep within the graphite has been shown to be critical to the total useful lifetime of graphite components. Irradiation induced creep occurs under the simultaneous application of high temperatures, neutron irradiation, and applied stresses within the graphite components. Significant internal stresses within the graphite components can result from a second phenomenon—irradiation induced dimensional change. In this case, the graphite physically changes i.e., first shrinking and then expanding with increasing neutron dose. This disparity in material volume change can induce significant internal stresses within graphite components. Irradiation induced creep relaxes these large internal stresses, thus reducing the risk of crack formation and component failure. Obviously, higher irradiation creep levels tend to relieve more internal stress, thus allowing the

Irradiation testing of miniature fuel plates for the RERTR program

Energy Technology Data Exchange (ETDEWEB)

Senn, R L; Martin, M M [Oak Ridge National Laboratory, Oak Ridge, TN 37830 (United States)

1983-08-01

An irradiation test facility, which provides a test bed for irradiating a variety of miniature fuel plates miniplates) for the Reduced Enrichment Research and Test Reactors (RERTR) program, has been placed into operation. The objective of these tests is to screen various candidate fuel materials as to their suitability for replacing the highly enriched uranium fuel materials currently used by the world's test and research reactors with a lower enrichment fuel material, without significantly degrading reactor operating characteristics and power levels. The use of low uranium enrichment of about 20% {sup 235}U in place of highly enriched fuel for these reactors would reduce the potential for {sup 235}U diversion. Fuel materials currently being evaluated in this first phase of these screening tests include aluminum-base dispersion-type fuel plates with fuel cores of 1) high uranium content U{sup 3}){sup 8}-Al being developed by ORNL, 2) high uranium content UAI{sub x}-Al being developed by EG and G Idaho, Inc., and 3) very high uranium content U{sub 3}Si-Al- being developed by ANL. The miniplates are 115-mm long by 50-mm wide with overall plate thicknesses of 1.27 or 1.52 mm. The fuel core dimensions vary according to overall plate thicknesses with a minimal clad thickness requirement of 0.20 mm. Sixty such miniplates (thirty of each thickness) can be irradiated in one test facility. The irradiation test facility, designated as HFED-1 is operating in core position E-7 in the Oak Ridge Research Reactor (ORR), a 30-MW water-moderated reactor. The peak neutron flux measured for this experiment is 1.96 x 10{sup 18} neutrons m{sub -2} s{sub -1}. The various types of miniplates will achieve burnups of up to approximately 2.2x10{sup 27} fissions/m{sup 3} of fuel, which will require approximately eight full power months of irradiation. During reactor shutdown periods, the experiment is removed from the reactor, moved to a special poolside station, disassembled, and inspected

Non-destructive tests of capsules for JMTR irradiation examination

International Nuclear Information System (INIS)

Tanaka, Hidetaka; Nagao, Yoshiharu; Sato, Masashi; Osawa, Kenji

2007-03-01

Irradiation examination are increasing in advanced irradiation research for accurate prediction control and evaluation of irradiation parameter such as neutron fluence, etc. by using JMTR. Irradiation capsule internals are therefore structurally complicated recently. This report described the procedure of non destructive tests such as radiographic test, penetrant test, ultrasonic test, etc. for inspection of irradiation capsules in JMTR, and the result of Test-case of confirmation procedure for internal parts of irradiation capsules. (author)

Irradiation of Northwest agricultural products

International Nuclear Information System (INIS)

Eakin, D.E.; Tingey, G.L.; Anderson, D.B.; Hungate, F.P.

1985-01-01

Irradiation of food for disinfestation and preservation is increasing in importance because of increasing resrictions on various chemical treatments. Irradiation treatment is of particular interest in the Northwest because of a growing supply of agricultural products and the need to develop new export markets. Several products have, or could potentially have, significant export markets if stringent insect control procedures are developed and followed. Due to the recognized potential benefits of irradiation, Pacific Northwest Laboratory (PNL) is conducting this program to evaluate the benefits of using irradiation on Northwest agricultural products under the US Department of Energy (DOE) Defense Byproducts Production and Utilization Program. Commodities currently included in the program are cherries, apples, asparagus, spices, hay, and hides

Irradiation of Northwest agricultural products

International Nuclear Information System (INIS)

Eakin, D.E.; Tingey, G.L.

1985-02-01

Irradiation of food for disinfestation and preservation is increasing in importance because of increasing restrictions on various chemical treatments. Irradiation treatment is of particular interest in the Northwest because of a growing supply of agricultural products and the need to develop new export markets. Several products have, or could potentially have, significant export markets if stringent insect control procedures are developed and followed. Due to the recognized potential benefits of irradiation, Pacific Northwest Laboratory (PNL) is conducting this program to evaluate the benefits of using irradiation on Northwest agricultural products under the US Department of Energy (DOE) Defense Byproducts Production and Utilization Program. Commodities currently included in the program are cherries, apples, asparagus, spices, hay, and hides

Functional and Logic Programming - 14th International Symposium (FLOPS 2018)

DEFF Research Database (Denmark)

This volume contains the proceedings of the 14th International Symposium on Functional and Logic Programming - FLOPS 2018 - held in Nagoya, Japan, May 9 - 11, 2018......This volume contains the proceedings of the 14th International Symposium on Functional and Logic Programming - FLOPS 2018 - held in Nagoya, Japan, May 9 - 11, 2018...

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)

Capsule Development and Utilization for Material Irradiation Tests

Energy Technology Data Exchange (ETDEWEB)

Kim, Bong Goo; Kang, Y H; Cho, M S [and others

2007-06-15

The essential technology for an irradiation test of materials and nuclear fuel has been successively developed and utilized to meet the user's requirements in Phase I(July 21, 1997 to March 31, 2000). It enables irradiation tests to be performed for a non-fissile material under a temperature control(300{+-}10 .deg. C) in a He gas environment, and most of the irradiation tests for the internal and external users are able to be conducted effectively. The basic technology was established to irradiate a nuclear fuel, and a creep capsule was also developed to measure the creep property of a material during an irradiation test in HANARO in Phase II(April 1, 2000 to March 31, 2003). The development of a specific purpose capsule, essential technology for a re-irradiation of a nuclear fuel, advanced technology for an irradiation of materials and a nuclear fuel were performed in Phase III(April 1, 2003 to February 28, 2007). Therefore, the technology for an irradiation test was established to support the irradiation of materials and a nuclear fuel which is required for the National Nuclear R and D Programs. In addition, an improvement of the existing capsule design and fabrication technology, and the development of an instrumented capsule for a nuclear fuel and a specific purpose will be able to satisfy the user's requirements. In order to support the irradiation test of materials and a nuclear fuel for developing the next generation nuclear system, it is also necessary to continuously improve the design and fabrication technology of the existing capsule and the irradiation technology.

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.)

International greenhouse gas trading programs: a discussion of measurement and accounting issues

International Nuclear Information System (INIS)

Vine, Edward; Kats, Gregory; Sathaye, Jayant; Joshi, Hemant

2003-01-01

There is general scientific consensus that global warming is occurring and that this results from human activities, primarily burning fossil fuels. There is also a growing international consensus that the most cost-effective way to slow global warming is to establish international climate change trading programs that let institutions sell greenhouse gas (GHG) reductions in an international trading program. A well designed international GHG trading program could save billions or tens of billions of dollars and could result in a more rapid transfer of cleaner, more modern energy generating, transmitting and using technologies to developing nations. Establishing an international GHG trading program will require the development of international consensus rules on how to value and credit investments, for example in energy efficiency, that result in reduced emissions of greenhouse gases. Such a program would require the development of an international technical agreement on how to value emissions reductions attributed to energy-efficiency investments that reflect realistic estimates of future energy savings--and emissions reductions--that come from those investments. This paper examines five possible approaches for valuing energy savings which might serve as the basis for an international agreement, discusses the strengths and weaknesses of each approach, and discusses lessons learned from conducting this evaluation process

Recent developments in the Sandia Laboratories' sewage sludge irradiation program

International Nuclear Information System (INIS)

Sivinski, H.D.; Brandon, J.R.; Morris, M.E.; Neuhauser, K.S.; Ward, R.L.; McCaslin, B.; Smith, G.S.

1977-11-01

Pathogen reduction studies have shown that a 1 Mrad treatment (or less at elevated temperatures) is very effective in eliminating pathogenic bacteria and viable parasite ova in liquid sludges. Heat is effective in reducing levels not only of pathogenic bacteria and Ascaris ova, but viruses as well. Ammonia has been shown to be virucidal to poliovirus and several other enteric viruses. Sludge processing costs are seen to be marginally competitive with heat treatment for liquid sludges and relatively economical for composted or dried sludges. Physical/chemical effects studies have shown that the effects of irradiation of sludges on dewatering properties are not significant when compared to polymers, nor is the combined effect synergistic. Dried, irradiated undigested sludge has been shown to be of significant nutritional value when used as a feed supplement for sheep and cattle, as well as in agronomic uses. No significant harmful effects have been demonstrated in the feeding program thus far. Product enhancement studies are currently under way, including schemes for removing nitrogen from effluent streams for addition as ammonium salts to sludges

34 CFR 661.1 - What is the Business and International Education Program?

Science.gov (United States)

2010-07-01

... 34 Education 3 2010-07-01 2010-07-01 false What is the Business and International Education... (Continued) OFFICE OF POSTSECONDARY EDUCATION, DEPARTMENT OF EDUCATION BUSINESS AND INTERNATIONAL EDUCATION PROGRAM General § 661.1 What is the Business and International Education Program? The Business and...

Internal stress distribution for generating closure domains in laser-irradiated Fe–3%Si(110) steels

International Nuclear Information System (INIS)

Iwata, Keiji; Imafuku, Muneyuki; Orihara, Hideto; Sakai, Yusuke; Ohya, Shin-Ichi; Suzuki, Tamaki; Shobu, Takahisa; Akita, Koichi; Ishiyama, Kazushi

2015-01-01

Internal stress distribution for generating closure domains occurring in laser-irradiated Fe–3%Si(110) steels was investigated using high-energy X-ray analysis and domain theory based on the variational principle. The measured triaxial stresses inside the specimen were compressive and the stress in the rolling direction became more dominant than stresses in the other directions. The calculations based on the variational principle of magnetic energy for closure domains showed that the measured triaxial stresses made the closure domains more stable than the basic domain without closure domains. The experimental and calculation results reveal that the laser-introduced internal stresses result in the occurrence of the closure domains

Global pest management program wins international award

OpenAIRE

Rich, Miriam Sommers

2009-01-01

An agricultural research program managed at Virginia Tech has won an international award for its work with pest-management practices that show economic benefits with minimal impact on health and the environment.

Irradiation temperature measurements in the surveillance program

International Nuclear Information System (INIS)

Pav, T.; Krhounek, V.

1991-01-01

Evaluation of the diamond monitor method for the determination of the irradiation temperature in the surveillance programme of WWER-440 reactors is discussed. One of the difficulties with the practical application of the method is that the measured values of irradiation temperature are unlikely high. Using a thermodynamical model of the processes in the annealing of the irradiated diamond crystals, it was shown that experimental difficulties came from the principles of the method used. An analysis was performed of the thermal field inside the capsule of the surveillance chain in operational conditions, using the finite element method. The diamond monitor method was suggested to be eliminated from the surveillance programme and the use was proposed of the value of 273+-3 degC (as the most likely value) for the irradiation temperature of surveillance samples in WWER-440 reactors. (Z.S.). 3 tabs., 6 figs., 4 refs

Japan's international cooperation programs on seismic safety of nuclear power plants

International Nuclear Information System (INIS)

Sanada, Akira

1997-01-01

MITI is promoting many international cooperation programs on nuclear safety area. The seismic safety of nuclear power plants (NPPs) is a one of most important cooperation areas. Experts from MITI and related organization join the multilateral cooperation programs carried out by international organization such as IAEA, OECD/NEA etc. MITI is also promoting bilateral cooperation programs such as information exchange meetings, training programs and seminars on nuclear safety with several countries. Concerning to the cooperation programs on seismic safety of NPPs such as information exchange and training, MITI shall continue and expand these programs. (J.P.N.)

The International Heliophysical Year Education and Outreach Program

Science.gov (United States)

Rabello-Soares, M.; Morrow, C.; Thompson, B.

2006-12-01

The International Heliophysical Year (IHY) will celebrate the 50th anniversary of the International Geophysical Year (IGY) and will continue its tradition of international research collaboration. The term "heliophysical" is an extension of the term "geophysical", where the Earth, Sun & Solar System are studied not as separate domains but through the universal processes governing the heliosphere. IHY represents a logical next-step, extending the studies into the heliosphere and thus including the drivers of geophysical change. The main goal of IHY Education and Outreach Program is to create more global access to exemplary resources in space and earth science education and public outreach. By taking advantage of the IHY organization with representatives in every nation and in the partnership with the United Nations Basic Space Science Initiative (UNBSSI), we aim to promote new international partnerships. Our goal is to assist in increasing the visibility and accessibility of exemplary programs and in the identification of formal or informal educational products that would be beneficial to improve the space and earth science knowledge in a given country; leaving a legacy of enhanced global access to resources and of world-wide connectivity between those engaged in education and public outreach efforts that are related to IHY science. Here we describe the IHY Education and Outreach Program, how to participate and the benefits in doing so. ~

Aging Management Strategy and Requirements of Pressurized Water Reactor Internal Components

Energy Technology Data Exchange (ETDEWEB)

Yang, Jun Seog; Oh, Sung Jin; Won, Se Yol; Jeong, Sun Mi [KHNP, Daejeon (Korea, Republic of)

2016-05-15

The demonstration that the effects of degradation in the components of PWR internals are adequately managed is essential for maintaining a healthy fleet and ensuring the continued functionality of the reactor internals. It is also very important to determine when and where irradiation susceptibility may occur for the continued operation. This paper introduces the aging management strategies and requirements for PWR internals components and discusses effects of irradiation aging results from the functionality assessments based on the categorization of internal components. This paper introduces aging management strategies and requirements for PWR internals components. The aging management requirements for PWR internals are specified in four final component groups, which are Primary, Expansion, Existing Program and No Additional Measures. Among these groups, Primary groups include any restriction on general applicability, degradation mechanism, forward link to any Expansion components, examination method, initial examination and frequency, and examination coverage and accessibility. Expansion groups are backward link to the Primary component.

Efigie: a computer program for calculating end-isotope accumulation by neutron irradiation and radioactive decay

International Nuclear Information System (INIS)

Ropero, M.

1978-01-01

Efigie is a program written in Fortran V which can calculate the concentration of radionuclides produced by neutron irradiation of a target made of either a single isotope or several isotopes. The program includes optimization criteria that can be applied when the goal is the production of a single nuclide. The effect of a cooling time before chemical processing of the target is also accounted for.(author) [es

Establishment of experimental equipments in irradiation technology development building (2)

International Nuclear Information System (INIS)

Shibata, Hiroshi; Nakano, Hiroko; Suzuki, Yoshitaka; Ohtsuka, Noriaki; Nishikata, Kaori; Takeuchi, Tomoaki; Hirota, Noriaki; Tsuchiya, Kunihiko

2018-01-01

From the viewpoints of utilization improvement of the Japan Materials Testing Reactor (JMTR), the experimental devices have been established for the out-pile tests in the irradiation technology development building. The devices for the irradiation capsule assembly, material tests and inspections were established at first and experimental data were accumulated before the neutron irradiation tests. On the other hand, after the Great East Japan Earthquake, the repairs and earthquake-resistant measures of the existing devices were carried out. New devices and equipments were also established for the R and D program for power plant safety enhancement of the Agency for Natural Resources and Energy, Ministry of Economy, Trade and Industry (METI) and 99 Mo/ 99m Tc production development under the Tsukuba International Strategic Zone. This report describes the outline and basic operation manuals of the devices established from 2011 to 2016 and the management points for the safety works in the irradiation technology development building. (author)

Research in radiobiology. Annual report of work in progress in the internal irradiation program

International Nuclear Information System (INIS)

Miller, S.C.

1983-01-01

Research progress on studies of the effects of internally deposited radionuclides in dogs, mice, and humans is reported. The studies include toxicity of plutonium 239, radium 226, and radium 224, the kinetics of actinides in beagles, and dosimetry of internal emitters

RPV-1: A Virtual Test Reactor to simulate irradiation effects in light water reactor pressure vessel steels

International Nuclear Information System (INIS)

Jumel, Stephanie; Van-Duysen, Jean Claude

2005-01-01

Many key components in commercial nuclear reactors are subject to neutron irradiation which modifies their mechanical properties. So far, the prediction of the in-service behavior and the lifetime of these components has required irradiations in so-called 'Experimental Test Reactors'. This predominantly empirical approach can now be supplemented by the development of physically based computer tools to simulate irradiation effects numerically. The devising of such tools, also called Virtual Test Reactors (VTRs), started in the framework of the REVE Project (REactor for Virtual Experiments). This project is a joint effort among Europe, the United States and Japan aimed at building VTRs able to simulate irradiation effects in pressure vessel steels and internal structures of LWRs. The European team has already built a first VTR, called RPV-1, devised for pressure vessel steels. Its inputs and outputs are similar to those of experimental irradiation programs carried out to assess the in-service behavior of reactor pressure vessels. RPV-1 is made of five codes and two databases which are linked up so as to receive, treat and/or convey data. A user friendly Python interface eases the running of the simulations and the visualization of the results. RPV-1 is sensitive to its inputs (neutron spectrum, temperature, ...) and provides results in conformity with experimental ones. The iterative improvement of RPV-1 has been started by the comparison of simulation results with the database of the IVAR experimental program led by the University of California Santa Barbara. These first successes led 40 European organizations to start developing RPV-2, an advanced version of RPV-1, as well as INTERN-1, a VTR devised to simulate irradiation effects in stainless steels, in a large effort (the PERFECT project) supported by the European Commission in the framework of the 6th Framework Program

Fruit irradiation

International Nuclear Information System (INIS)

Anon.

1977-01-01

Food spoilage is a common problem when marketing agricultural products. Promising results have already been obtained on a number of food irradiating applications. A process is described in this paper where irradiation of sub-tropical fruits, especially mangoes and papayas, combined with conventional heat treatment results in effective insect and fungal control, delays ripening and greatly improves the quality of fruit at both export and internal markets

Internal quality control program for individual monitoring service

Energy Technology Data Exchange (ETDEWEB)

Mauricio, Claudia L.P.; Moura Junior, Jose; Patrao, Karla C.S. [Instituto de Radioprotecao e Dosimetria (IRD/CNEN-RJ), Rio de Janeiro, RJ (Brazil)]. E-mail: claudia@ird.gov.br; moura@ird.gov.br; karla@ird.gov.br

2007-07-01

With a focus on continuous improvement, since 2002, a special internal procedure for following and checking the performance of our individual monitoring services has been implemented. A fictitious installation, named 'Fantasma' has been created, initially, with 4 film badges and 7 thermoluminescent dosimetric ring users. Since 2005, this quality control program includes also the albedo neutron individual monitoring service. Monthly, the 'Fantasma' test monitors are irradiated by traceable Cs-137 and Am-Be sources. The calibration quantities are: the photon dose equivalent (H{sub x}) for the photographic individual monitor, the maximum dose equivalent (MADE) for the albedo neutron individual monitor and the personal dose equivalent at 0.07 mm depth (H{sub p}(0.07)) for ring monitor. Up to now, all results show compliance with the specific trumpet curves acceptance limits. Once, a small sub-evaluation tendency has been noted and this information was used to improve the film system. For the photographic film system, the evaluated value to reference dose ratios range from 0.71 to 1.12, with a mean value of 0.91 {+-} 0.12. For the ring system, the ratio ranges from 0.69 to 1.40, with a mean value of 1.02 {+-} 0.07. For the neutron system, which presents intrinsic larger uncertainties, the ratio ranged from 0.67 to 1.88, with mean value of 1.16 {+-} 0.27. (author)

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)

Development and utilization of irradiational capsule - Mechanical and thermal performance analysis and development of design program on the cylindrical structures with multi-holes

Energy Technology Data Exchange (ETDEWEB)

Lee, Young Shin; Choi, M. H.; Shin, D. S. [Chungnam National University, Taejon (Korea)

2000-04-01

Irradiation tests in the research reactor are used with the specially designed capsules for irradiation test and loop. Accordingly, suitable instrumented capsule for HANARO must be designed and manufactured. To satisfy the requirements of users and to conduct irradiation test effectively, the accurate informations on the thermal and mechanical characteristics of capsule should be understood. The structural analysis results show that stress characteristics of the cylinder with multi-holes is not significantly effected by the sizes of specimen hole, numbers of specimen and eccentric characteristics. The thermal and structural analysis of the capsule with multi-holes under thermal loading shows that the peak temperature in the circular cylinder is occurred in the specimens inserted in the center or specimen holes and is significantly effected by gap size between the holder and the external tube. In this study, CAPSYS program is developed by interfacing finite element analysis program, ANSYS with graphic user interface program, VISUAL C++. This program will be useful on the design and safety analysis of the capsule for material irradiation test. 20 refs., 37 figs., 9 tabs. (Author)

Overview of international fusion technology programs

International Nuclear Information System (INIS)

Coffman, F.E.; Baublitz, J.E.; Beard, D.S.; Cohen, M.M.; Dalder, E.N.C.; Finfgeld, C.R.; Haas, G.M.; Head, C.R.; Murphy, M.R.; Nardella, G.R.

1979-01-01

World fusion technology programs, as well as current progress and future plans for the U.S., are discussed. Regarding conceptual design, the international INTOR tokamak study, the Garching Ignition Test Reactor Study, the U.S. Engineering Test Facility conceptual design, the Argonne National Laboratory Commercial Tokamak Study, mirror conceptual designs, and alternate concepts and applications studies are summarized. With regard to magnetics, progress to date in the large coil program and pulsed coil program is summarized. In the area of plasma heating and fueling and exhaust, work on a new positive ion source research and development program at Lawrence Berkeley Laboratory and Oak Ridge National Laboratory is described, as is negative ion work. Tradeoff considerations for radio-frequency heating alternatives are made, and a new 60-100 GHz electron cyclotron heating research and development program is discussed. Progress and plans for solid hydrogen pellet injector development are analyzed, as are plans for a divertor technology initiative. A brief review of the U.S. alternate applications and environment and safety program is included

A study by internal friction of defects produced in iron and nickel irradiated at very low temperatures; Etude au moyen du frottement interne des defauts crees par irradiation a tres basse temperature dans le fer et le nickel

Energy Technology Data Exchange (ETDEWEB)

Keating-Hart, G de [Commissariat a l' Energie Atomique, Grenoble (France). Centre d' Etudes Nucleaires

1969-07-01

This work represents a contribution to the study of point defects in metals. After a brief review of the theory of internal friction we will discuss some technical innovations aimed at increasing the flexibility of the apparatus at our disposal. These innovations have allowed us to extend our range of measurements down to 20 deg. K. We will then discuss our experimental results. Firstly, we describe preliminary experiments on electron irradiated iron and the evidence for a laminar structure. Secondly, we present and account of the first measurements on nickel after neutron irradiation at 27 deg. K. We will compare the results with those obtained by other methods in this laboratory. Essentially we have observed transitory peaks at low temperature due to close Frenkel pairs and we have noticed the absence of a peak which would correspond to the magnetic after effect band of stage I{sub E}. An attempt is made to explain the disappearance of the observed peaks upon the application of an internal saturating magnetic field. (author) [French] Ce memoire constitue une contribution a l'etude des defauts ponctuels dans les metaux. Apres un bref apercu theorique sur le frottement interne, nous presenterons quelques realisations techniques destinees a accroitre les possibilites des instruments qui nous ont ete confies. Ces dernieres nous ont permis d'etendre la gamme des mesures jusqu'a 20 deg. K. Nous parlerons ensuite de nos resultats experimentaux. En premier lieu, ceux obtenus au cours de premieres experiences, sur le fer irradie aux electrons mettent en evidence des structures de laminage. En second lieu, nous exposerons les premieres mesures realisees sur du nickel irradie aux neutrons; nous comparerons ces resultats avec ceux obtenus par d'autres moyens experimentaux dans le laboratoire. Nous avons observe essentiellement des pics fugitifs a basse temperature dus aux paires proches de Frenckel et nous avons constate l'absence d'un pic correspondant a la bande de tramage

Irradiation Microstructure of Austenitic Steels and Cast Steels Irradiated in the BOR-60 Reactor at 320°C

Science.gov (United States)

Yang, Yong; Chen, Yiren; Huang, Yina; Allen, Todd; Rao, Appajosula

Reactor internal components are subjected to neutron irradiation in light water reactors, and with the aging of nuclear power plants around the world, irradiation-induced material degradations are of concern for reactor internals. Irradiation-induced defects resulting from displacement damage are critical for understanding degradation in structural materials. In the present work, microstructural changes due to irradiation in austenitic stainless steels and cast steels were characterized using transmission electron microscopy. The specimens were irradiated in the BOR-60 reactor, a fast breeder reactor, up to 40 dpa at 320°C. The dose rate was approximately 9.4x10-7 dpa/s. Void swelling and irradiation defects were analyzed for these specimens. A high density of faulted loops dominated the irradiated-altered microstructures. Along with previous TEM results, a dose dependence of the defect structure was established at 320°C.

Legislative and administrative control of processing of and trade in irradiated food

International Nuclear Information System (INIS)

Loaharanu, P.

1992-01-01

This presentation will focus on regulatory and administrative procedures recently developed to strengthen the control aspect of commercial use of food irradiation. Most of these developed by the International Consultative Group on Food Irradiation (ICGFI) established under the aegis of FAO, IAEA and WHO since 1984. ICGFI has produced a number of guidelines/codes of practice to assist national authorities in regulating the commercial use of food irradiation. The following regulatory control provisions will be highlighted: 1. Codes of good irradiation practice for specific application of food irradiation. 2. International inventory of authorised food irradiation facilities. 3. International training programmes for operators/plant managers of irradiation facilities and food inspectors. 4. International Dose Assurance Service (IDAS). 5. Labelling. 6. Certificate of irradiated food. (orig.) [de

The significance of neuroendocrine system state in estimation of nonstochastic effects of small doses of internal irradiation. (An experimental study)

International Nuclear Information System (INIS)

Dedov, V.I.; Norets, T.A.; Stepanenko, V.F.; Dedenkov, A.N.

1987-01-01

Data on long-term complex investigations of nonstochastic effects of low doses of internal irradiation on the level of a whole organism are presented. Experiments have been carried out with mongrel rats of both sexes and different ages up to the moment of introduction of radioactive compounds. Action of relatively and uniformly distributing in the organism radiactive compounds of selenium - 75 and sulfur - 35, which were introduced once intravenously in quantities forming absorbed doses in average on the whole body and ovaries (0.5 Gy), on endocrine glands and critical organs (up to 1.0 Gy) has been used as models of internal radiation. Data, testifying to the fact that the neuroendocrinal system, despite the existing opinion, is sensitive to action of low doses of internal irradiation compared with the recommended one as an ultimate permissible one for nonstochastic effects ( 0.5 Sv), that permits to suggest for using factors of the functional state of the neuroendocrine system as an informative and sensitive criterium of estimation of biological action of low doses of internal radiation, have been obtained. These factors along with doses on critical organs permit to estimate the degree of dangerous action of different radionuclides on the organism level. Dynamic studying of activity factors of the neuroendocrine system with simultaneous analysis of the state of harmonically dependent processes permits to estimate functional possibilities of irradiated organism, its viability, especially under conditions requiring increased stress, as well as to take into account such factors modifying a biological effect as age, animal sex, the character of absorbed dose distribution

Detection methods for irradiated foods

International Nuclear Information System (INIS)

Dyakova, A.; Tsvetkova, E.; Nikolova, R.

2005-01-01

In connection with the ongoing world application of irradiation as a technology in Food industry for increasing food safety, it became a need for methods of identification of irradiation. It was required to control international trade of irradiated foods, because of the certain that legally imposed food laws are not violated; supervise correct labeling; avoid multiple irradiation. Physical, chemical and biological methods for detection of irradiated foods as well principle that are based, are introducing in this summary

Foodstuff irradiation

International Nuclear Information System (INIS)

1982-01-01

Report written on behalf of the Danish Food Institute summarizes national and international rules and developments within food irradiation technology, chemical changes in irradiated foodstuffs, microbiological and health-related aspects of irradiation and finally technological prospects of this conservation form. Food irradiatin has not been hitherto applied in Denmark. Radiation sources and secondary radiation doses in processed food are characterized. Chemical changes due to irradiation are compared to those due to p.ex. food heating. Toxicological and microbiological tests and their results give no unequivocal answer to the problem whether a foodstuff has been irradiated. The most likely application fields in Denmark are for low radiation dosis inhibition of germination, riping delay and insecticide. Medium dosis (1-10 kGy) can reduce bacteria number while high dosis (10-50 kGy) will enable total elimination of microorganisms and viruses. Food irradiation can be acceptable as technological possibility with reservation, that further studies follow. (EG)

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)

Acceptance, control of and trade in irradiated food

International Nuclear Information System (INIS)

1989-01-01

Proceedings of an International Conference on the Acceptance, Control of and Trade in Irradiated Food jointly organized by the Food and Agriculture Organization of the United Nations, the World Health Organization, the International Atomic Energy Agency and the International Trade Centre-UNCTAD/GATT and held in Geneva, 12-16 December 1988. The Conference was prompted by the lack of acceptance by some governments, which do not see a need for the application of food irradiation technology in their own countries, and as a consequence may hamper its use in other countries where its application could significantly improve consumer health and nutrition, as well as national economic and trading potential. This publication contains discussions on the key issues of the wholesomeness of irradiated food, the contribution of this technology to public health, food security and international trade, the control of the process to ensure its correct application for consumer protection, and the acceptance of irradiated food by industry and consumers. The proceedings include the International Document on Food Irradiation, highlighting the major issues related to the acceptance of irradiated food by consumers, governmental and intergovernmental activities, the control of the process, and trade. A number of Member States formally expressed their views on this International Document, expressing either endorsement or reservation, and their statements are included in these proceedings. Refs, fig and tabs

Experience of European LWR irradiated fuel transport: the first five hundred tonnes

International Nuclear Information System (INIS)

Curtis, H.W.

1978-01-01

The paper describes the service provided by an international company specializing in the transport of LWR irradiated fuel throughout Europe. Methods of transport used to the reprocessing plants at La Hague and Windscale include road transport of 38 te flasks over the whole route; transport of flasks between 55 and 105 te by rail, with rail-head and the reprocessing plant, where required, performed by road using heavy trailers; roll-on, roll-off sea ferries; and charter ships. Different modes of transport have been developed to cater for the various limitations on access to reactor sites arising from geographical and routing considerations. The experience of transporting more than 500 tonnes of irradiated uranium from twenty-one power reactors is used to illustrate the flexibility which the transport organization requires when the access and handling facilities are different at almost every reactor. Variations in fuel cross sections and lengths of fuel elements used in first generation reactors created the need for first generation flasks with sufficient variants to accommodate all reactor fuels but the trend now is towards standardization of flasks to perhaps two basic types. The safety record of irradiated fuel transport is examined with explanation of the means whereby this has been achieved. The problems of programming the movement of a pool of eighteen flasks for twenty-one reactors in eight countries are discussed together with the steps taken to ensure that the service operates fairly to give priority to those reactors with the greatest problems. The transport of irradiated fuel across several national frontiers is an international task which requires an international company. The transport of European irradiated fuel can be presented as an example of international collaboration which works

Capsule Development and Utilization for Material Irradiation Tests

Energy Technology Data Exchange (ETDEWEB)

Kim, Bong Goo; Kang, Y. H.; Cho, M. S. (and others)

2007-06-15

The essential technology for an irradiation test of materials and nuclear fuel has been successively developed and utilized to meet the user's requirements in Phase I(July 21, 1997 to March 31, 2000). It enables irradiation tests to be performed for a non-fissile material under a temperature control(300{+-}10 .deg. C) in a He gas environment, and most of the irradiation tests for the internal and external users are able to be conducted effectively. The basic technology was established to irradiate a nuclear fuel, and a creep capsule was also developed to measure the creep property of a material during an irradiation test in HANARO in Phase II(April 1, 2000 to March 31, 2003). The development of a specific purpose capsule, essential technology for a re-irradiation of a nuclear fuel, advanced technology for an irradiation of materials and a nuclear fuel were performed in Phase III(April 1, 2003 to February 28, 2007). Therefore, the technology for an irradiation test was established to support the irradiation of materials and a nuclear fuel which is required for the National Nuclear R and D Programs. In addition, an improvement of the existing capsule design and fabrication technology, and the development of an instrumented capsule for a nuclear fuel and a specific purpose will be able to satisfy the user's requirements. In order to support the irradiation test of materials and a nuclear fuel for developing the next generation nuclear system, it is also necessary to continuously improve the design and fabrication technology of the existing capsule and the irradiation technology.

Internal irradiation by radon daughters in Bulgarian uranium mines over the period 1956-1990

International Nuclear Information System (INIS)

Dimitrov, M.; Presiyanov, D.

1993-01-01

The results of over 30-years' radiation monitoring in Bulgarian uranium mines are summed up in retrospect. The overall organization and the parameters monitored during the different periods are discussed. A radiological characteristic of the working environment is presented which includes radon and its decay products. The internal irradiation levels during different time periods and in different mines have been estimated. The health costs of uranium mining in Bulgaria are discussed and conclusions and recommendations for radiological control are made. (author)

SATURN-S - a program system for the description of the thermomechanical behaviour of reactor fuel pins under irradiation

International Nuclear Information System (INIS)

Pesl, R.; Freund, D.; Gaertner, H.; Steiner, H.

1987-07-01

On the basis of post irradiation examination results of various irradiation experiments with different fuel types real case calculations showed many of the existing models to be applicable to a restricted extent only. Therefore a re- and partially new formulation of models was necessary. Furthermore, the data base had been actualized and numerical procedures had been improved. This, together with the capabilities of modern computer systems, conducted the development of the program system SATURN-S with a strictly modular structure, specified by the requirements of the determination of the superposition of effects. In the present report the program SATURN-S as well as some analysis results are presented. (orig./HP) [de

The Development of International Programs in a School of Social Work

Directory of Open Access Journals (Sweden)

Frank B. Raymond

2014-04-01

Full Text Available During the last decade increasing numbers of schools of social work have adopted an international mission and have developed a variety of activities to reflect their global perspective. In earlier years, however, relatively few schools expressed a global mission, offered coursework on international social work, provided field placements or other opportunities to expose students to international learning, or extended components of their academic programs to other countries. An early leader in doing such things was the College of Social Work at the University of South Carolina (COSW, where the author was privileged to serve as dean for 22 years (1980-2002 when many of these developments occurred. This paper will discuss how this school acquired an international mission and developed various programs to manifest this commitment. The paper will describe, in particular, the college’s signature achievement in international social work education – the development and implementation of a Korea-based MSW program. The COSW was the first school of social work in the US to offer a master’s degree in its entirety in a foreign country. It is hoped that the recounting of this school’s experiences will offer guidance to other social work education programs that are exploring ways of expanding their international initiatives.

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

Dark Skies Awareness Programs for the International Year of Astronomy

Science.gov (United States)

Walker, C. E.; Pompea, S. M.

2008-12-01

The loss of a dark night sky as a natural resource is a growing concern. It impacts not only astronomical research, but also our environment in terms of ecology, health, safety, economics and energy conservation. For this reason, "Dark Skies are a Universal Resource" is a cornerstone project for the U.S. International Year of Astronomy (IYA) program in 2009. Its goal is to raise public awareness of the impact of artificial lighting on local environments by getting people involved in a variety of dark skies-related programs. These programs focus on citizen-scientist sky-brightness monitoring programs, a planetarium show, podcasting, social networking, a digital photography contest, the Good Neighbor Lighting Program, Earth Hour, National Dark Skies Week, a traveling exhibit, a video tutorial, Dark Skies Discovery Sites, Astronomy Nights in the (National) Parks, Sidewalk Astronomy, and a Quiet Skies program. Many similar programs are available internationally through the "Dark Skies Awareness" Global Cornerstone Project. Working groups for both the national and international dark skies cornerstone projects are being chaired by the National Optical Astronomy Observatory (NOAO). The presenters from NOAO will provide the "know-how" and the means for session participants to become community advocates in promoting Dark Skies programs as public events at their home institutions. Participants will be able to get information on jump-starting their education programs through the use of well-developed instructional materials and kits. For more information, visit http://astronomy2009.us/darkskies/ and http://www.darkskiesawareness.org/.

Revealing by secondary electronic emission of internal electric fields in the yttriated zirconia, irradiated by electrons of 1 MeV

International Nuclear Information System (INIS)

Blaise, G.; Paris-11 Univ., 91 - Orsay

2007-01-01

The defects due to irradiation in a dielectric material present an activity which can generate macroscopic internal electric fields. A method of investigation of these fields, based on the measure of the Secondary Electronic Emission coefficient, has been developed on a scanning electric microscope. This ones contains two low noise detectors which respectively measure the influence current I IC produced by the charges trapping in the material and the current I SB due to secondary and backscattered electrons which come from the sample. The Secondary Emission coefficient is given by σ=I SB /(I SB +I IC ). The charges trapping during an electrons injection leads to a variation of σ for its intrinsic value σ 0 relative to the uncharged material, until the stationary value σ st =1 corresponding to the auto-regulated condition. This variation is due to the development of an internal electric field produced by the accumulation of the charges trapped during injection. In comparing the evolutions of σ of a fresh yttriated zirconia and of an yttriated zirconia irradiated by electrons of 1 MeV with a dose rate of 10 18 e/cm 2 , it has been revealed that an internal field (due to irradiation) of about 0.5*10 6 V/m exists at a depth of the micron order. This field, directed towards the outside of the material surface, is attributed to the F + defects and to the T centers produced by the impact of the electrons of 1 MeV. In carrying out annealings until 1000 K, a progressive disappearance of this field is observed in the temperature range of 400-600 K, directly due to the F + defects and T centers recovery, as it has been observed by ESR. An internal field three times weaker than the preceding ones has been revealed at a few nm under the surface. Its disappearance from a temperature of 1000 K suggests that it is due to the redistribution of the chemical species into the surface, during the irradiation with electrons of 1 MeV. (O.M.)

Effect of irradiation in design of LMFBR internals

International Nuclear Information System (INIS)

Tavassoli, A.A.; Cowan, A.; Vries, M. de; Heesen, E.

1990-01-01

Internal structures of nuclear power reactors are essentially made with the austenitic stainless steels Types 304L and 316L. In service these structures receive low to moderate neutron doses. In this paper, the work undertaken by the European Fast Breeder Working Group is reviewed. Conclusions drawn to this date are presented and tentative reduction factors to be used in design are discussed in terms of the number of displacements per atom (dpa) and the quantity of helium generated in the steel (appm He). For the lower core structure which operates at about 400 0 C existing design rules can be used for parts which are subjected to less than 2 dpa despite a reduction in ductility and toughness which occurs above about 0.8 dpa. For the above core structure which operates at about 550 0 C interim and rather conservative stress reduction factors are proposed which can become effective at helium levels as low as 10 -4 appm. Particular attention is paid to: - irradiation temperature, - neutron flux and fluence, - steel type and grade, - heat treatment and boron distribution, - weld metal composition and procedure (TIG,MMA,...), to ensure that service conditions are represented as closely as possible

International Experience with Key Program Elements of IndustrialEnergy Efficiency or Greenhouse Gas Emissions Reduction Target-SettingPrograms

Energy Technology Data Exchange (ETDEWEB)

Price, Lynn; Galitsky, Christina; Kramer, Klaas Jan

2008-02-02

Target-setting agreements, also known as voluntary ornegotiated agreements, have been used by a number of governments as amechanism for promoting energy efficiency within the industrial sector. Arecent survey of such target-setting agreement programs identified 23energy efficiency or GHG emissions reduction voluntary agreement programsin 18 countries. International best practice related to target-settingagreement programs calls for establishment of a coordinated set ofpolicies that provide strong economic incentives as well as technical andfinancial support to participating industries. The key program elementsof a target-setting program are the target-setting process,identification of energy-saving technologies and measures usingenergy-energy efficiency guidebooks and benchmarking as well as byconducting energy-efficiency audits, development of an energy-savingsaction plan, development and implementation of energy managementprotocols, development of incentives and supporting policies, monitoringprogress toward targets, and program evaluation. This report firstprovides a description of three key target-setting agreement programs andthen describes international experience with the key program elementsthat comprise such programs using information from the three keytarget-setting programs as well as from other international programsrelated to industrial energy efficiency or GHG emissionsreductions.

Rupture of an internal carotid artery pseudoaneurysm after irradiation for a nasopharyngeal carcinoma. Case report

International Nuclear Information System (INIS)

Hanada, Yukiko; Nakamura, Megumi; Sasai, Hisanori; Kamakura, Aya; Sakata, Yoshiharu; Miyahara, Hiroshi

2013-01-01

The primary treatment of nasopharyngeal carcinoma (NPC) has been external radiotherapy. Rupture of an internal carotid artery (ICA) pseudoaneurysm is a rare complication of irradiation therapy for a nasopharyngeal carcinoma. A 78 years old man had a history of NPC treated with radiotherapy in 1993. He was admitted to the hospital because of epistaxis. Angiography showed an ICA pseudoaneurysm pointing medially to the nasopharynx. Coil embolization of the ICA was performed, but cerebral infarction occurred. Internal carotid artery (ICA) pseudoaneurysms are an uncommon but potentially lethal condition. Angiography is the mainstay of diagnosis of the aneurysm and planning the embolization of the ICA. We should be more aware of this complication in NPC patients. (author)

Analysis of Core Physics Experiments on Irradiated BWR MOX Fuel in REBUS Program

International Nuclear Information System (INIS)

Yamamoto, Toru; Ando, Yoshihira; Hayashi, Yamato

2008-01-01

As part of analyses of experimental data of a critical core containing a irradiated BWR MOX test bundle in the REBUS program, depletion calculations was performed for the BWR MOX fuel assemblies from that the MOX test rods were selected by using a general purpose neutronics code system SRAC. The core analyses were carried out using SRAC and a continuous energy Monte Carlo code MVP. The calculated k eff s were compared with those of the core containing a fresh MOX fuel bundle in the program. The SRAC-diffusion calculation underestimates k eff s of the both cores by 1.0 to 1.3 %dk and the k eff s of MVP are 1.001. The difference in k eff between the irradiated BWR MOX test bundle core and the fresh MOX one is 0.4 %dk in the SRAC-diffusion calculation and 0.0 %dk in the MVP calculation. The calculated fission rate distributions are in good agreement with the measurement in the SRAC-diffusion and MVP calculations. The calculated neutron flux distributions are also in good agreement with the measurement. The calculated burnup reactivity in the both calculations well reproduce the measurements. (authors)

KEY RESULTS FROM IRRADIATION AND POST-IRRADIATION EXAMINATION OF AGR-1 UCO TRISO FUEL

Energy Technology Data Exchange (ETDEWEB)

Demkowicz, Paul A.; Hunn, John D.; Petti, David A.; Morris, Robert N.

2016-11-01

The AGR-1 irradiation experiment was performed as the first test of tristructural isotropic (TRISO) fuel in the US Advanced Gas Reactor Fuel Development and Qualification Program. The experiment consisted of 72 right cylinder fuel compacts containing approximately 3×105 coated fuel particles with uranium oxide/uranium carbide (UCO) fuel kernels. The fuel was irradiated in the Advanced Test Reactor for a total of 620 effective full power days. Fuel burnup ranged from 11.3 to 19.6% fissions per initial metal atom and time average, volume average irradiation temperatures of the individual compacts ranged from 955 to 1136°C. This paper focuses on key results from the irradiation and post-irradiation examination, which revealed a robust fuel with excellent performance characteristics under the conditions tested and have significantly improved the understanding of UCO coated particle fuel irradiation behavior within the US program. The fuel exhibited a very low incidence of TRISO coating failure during irradiation and post-irradiation safety testing at temperatures up to 1800°C. Advanced PIE methods have allowed particles with SiC coating failure to be isolated and meticulously examined, which has elucidated the specific causes of SiC failure in these specimens. The level of fission product release from the fuel during irradiation and post-irradiation safety testing has been studied in detail. Results indicated very low release of krypton and cesium through intact SiC and modest release of europium and strontium, while also confirming the potential for significant silver release through the coatings depending on irradiation conditions. Focused study of fission products within the coating layers of irradiated particles down to nanometer length scales has provided new insights into fission product transport through the coating layers and the role various fission products may have on coating integrity. The broader implications of these results and the application of

Lack of grading agreement among international hemostasis external quality assessment programs

OpenAIRE

Olson, John D.; Jennings, Ian; Meijer, Piet; Bon, Chantal; Bonar, Roslyn; Favaloro, Emmanuel J.; Higgins, Russell A.; Keeney, Michael; Mammen, Joy; Marlar, Richard A.; Meley, Roland; Nair, Sukesh C.; Nichols, William L.; Raby, Anne; Reverter, Joan C.

2018-01-01

Laboratory quality programs rely on internal quality control and external quality assessment (EQA). EQA programs provide unknown specimens for the laboratory to test. The laboratory's result is compared with other (peer) laboratories performing the same test. EQA programs assign target values using a variety of methods statistical tools and performance assessment of ‘pass’ or ‘fail’ is made. EQA provider members of the international organization, external quality assurance in thrombosis and h...

Development of an irradiation system for a small size continuous run multipurpose gamma irradiator; Desenvolvimento do sistema de irradiacao em um irradiador multiproposito de cobalto-60 tipo compacto

Energy Technology Data Exchange (ETDEWEB)

Calvo, Wilson Aparecido Parejo

2005-07-01

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{sup 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

Status report of the US Department of Energy's International Nuclear Safety Program

International Nuclear Information System (INIS)

1994-12-01

The US Department of Energy (DOE) implements the US Government's International Nuclear Safety Program to improve the level of safety at Soviet-designed nuclear power plants in Central and Eastern Europe, Russia, and Unkraine. The program is conducted consistent with guidance and policies established by the US Department of State (DOS) and the Agency for International Development and in close collaboration with the Nuclear Regulatory Commission. Some of the program elements were initiated in 1990 under a bilateral agreement with the former Soviet Union; however, most activities began after the Lisbon Nuclear Safety Initiative was announced by the DOS in 1992. Within DOE, the program is managed by the International Division of the Office of Nuclear Energy. The overall objective of the International Nuclear Safety Program is to make comprehensive improvements in the physical conditions of the power plants, plant operations, infrastructures, and safety cultures of countries operating Soviet-designed reactors. This status report summarizes the Internatioal Nuclear Safety Program's activities that have been completed as of September 1994 and discusses those activities currently in progress

Food preservation by irradiation

International Nuclear Information System (INIS)

Labots, H.; Huis in 't Veld, G.J.P.; Verrips, C.T.

1985-01-01

After a review of several methods for the preservation of food and the routes of food infections, the following chapters are devoted to the preservation by irradiation. Applications and legal aspects of food irradiation are described. Special reference is made to the international situation. (Auth.)

The International Studies Minor in Practice: Program Offerings and Student Choices

Science.gov (United States)

Breuning, Marijke; Quinn, John James

2011-01-01

International studies programs are increasingly popular at colleges and universities across the United States, and most prior research and efforts have been has focused on the international studies major. However, institutions may often find it much easier to create a minor rather than a major program given scarce resources and a preexisting…

System program information of internal occupational radiation exposure in Syria (SORIES)

International Nuclear Information System (INIS)

Bitar, A.; Moghrabi, M.

2014-01-01

The present work describes personal-computer-based software, SORIES, which enables users to estimate intake activity and the resulting internal doses for all radionuclides existing in ICRP /78/ and IAEA Safety Reports Series No.37. The program forms a useful tool to get a database containing all the information related to occupational internal monitoring program. Furthermore, SORIES offers the possibility to obtain different reports of results. The SORIES program was built to be easy-to-use and user friendly. The program is based on Microsoft FoxPro database program and runs on Microsoft Windows 97-XP. SORIES software is distributed by Atomic Energy Commission in Syria.(author)

Food preservation by irradiation

International Nuclear Information System (INIS)

Gottschalk, M.

1978-01-01

In November, 1977, an International Symposium on Food Preservation by Irradiation was held at Wageningen, the Netherlands. About 200 participants attended the Symposium which was organised by the International Atomic Energy Agency, the Food and Agriculture Organization of the United Nations and the World Health Organization; a reflection of the active interest which is being shown in food irradiation processing, particularly among developing countries. The 75 papers presented provided an excellent review of the current status of food irradiation on a wide range of different topics, and the Symposium also afforded the valuable opportunity for informal discussion among the participants and for developing personal contacts. A brief survey of the salient aspects discussed during the course of the meeting are reported on. (orig.) [de

Food irradiation seminar: Asia and the Pacific

International Nuclear Information System (INIS)

Mitchell, G.E.

1986-01-01

The report covers the Seminar for Asia and the Pacific on the practical application of food irradiation. The seminar assessed the practical application of food irradiation processes, commercial utilisation and international trade of irradiated food

75 FR 53640 - Call for Applications for the International Buyer Program Calendar Year 2012

Science.gov (United States)

2010-09-01

... addition, the applicant should describe in detail the international marketing program to be conducted for... DEPARTMENT OF COMMERCE International Trade Administration [Docket No.: 100806330-0330-01] Call for Applications for the International Buyer Program Calendar Year 2012 AGENCY: International Trade Administration...

Regulatory aspect of food irradiation

International Nuclear Information System (INIS)

Harrison Aziz

1985-01-01

Interest in the process of food irradiation is reviewed once again internationally. Although food irradiation has been thoroughly investigated, global acceptance is still lacking. Factors which impede the progress of the technology are discussed here. (author)

High activity gamma irradiators developed in Hungary

International Nuclear Information System (INIS)

Stenger, V.

1997-01-01

The development of high activity Gamma irradiators began in Hungary already in the early years of 60s. The very first designs were serving research in irradiation chemistry, radiation physics, food and agricultural research, radiation sterilization, plastic radiation chemistry, radiobiology, cancer therapy, personal and high dose dosimetry, following the international trends. Domestic and new international demands forced us to design and construct High Activity Gamma Irradiators: Multipurpose Pilot, Portable and Large scale bulk, Multipurpose Industrial scale types

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

76 FR 54428 - Call for Applications for the International Buyer Program Calendar Year 2013

Science.gov (United States)

2011-09-01

... in detail the international marketing program to be conducted for the event, and explain how efforts... DEPARTMENT OF COMMERCE International Trade Administration [Docket No. 110729450-1450-01] Call for Applications for the International Buyer Program Calendar Year 2013 AGENCY: International Trade Administration...

Innovative approaches to the Management of Irradiated Nuclear Graphite Wastes: Addressing the Challenges through International Collaboration with Project 'GRAPA'

International Nuclear Information System (INIS)

Wickham, A.J.; Ojovan, M.; O'Sullivan, P.; )

2017-01-01

There exists more than 250.000 tonnes of irradiated (and therefore radioactive) nuclear graphite (i-graphite) in the world, primarily as a result of the development of graphite-moderated power-reactor systems, initially for defence and subsequently for commercial purposes. Only a very small number of such plants have been dismantled and, for most cases, the final destiny of the irradiated graphite remains unresolved. Future high-temperature reactor programmes, such as the Chinese HTR-PM development, will produce more graphite and carbonaceous wastes from both structural components and the fuel pebbles (which are approximately 96% carbonaceous), the latter producing a continuous stream of so-called 'operational waste'. The problem of dismantling irradiated graphite reactor stacks, possibly distorted through neutron damage and in some cases degraded further by radiation-chemical attack by gaseous coolants, and then finding the appropriate treatments and final destiny of the material, has exercised both the European Union and the International Atomic Energy Agency for more than 25 years, seeking to address the different issues and available disposal solutions in different IAEA Member States. An IAEA collaborative research programme on treatment options has recently been completed, and an active group of international specialists in this area has now been established as part of the IAEA International Decommissioning Network under the envelope of Project 'GRAPA' (Irradiated Graphite Processing Approaches), which includes representatives from Belgium, China, France, Germany, India, Italy, Lithuania, Rep. of Korea, Romania, Spain, Switzerland, Ukraine and the Russian Federation with direct responsibilities for various parts of the decommissioning and graphite-disposal process in a variety of reactor designs. Interest has also been expressed by colleagues from Sweden and Japan. Work is in progress on a number of topic areas where weaknesses in the

Development of very-high-density fuels by the RERTR program

International Nuclear Information System (INIS)

Snelgrove, J.L.; Hofman, G.L.; Trybus, C.L.; Wiencek, T.C.

1996-01-01

The RERTR program has recently begun an aggressive effort to develop dispersion fuels for research and test reactors with uranium densities of 8 to 9 g U/cm 3 , based on the use of γ-stabilized uranium alloys. Fabrication development teams and facilities are being put into place, and preparations for the first irradiation test are in progress. The first screening irradiations are expected to begin in late April 1997 and the first results should be available by the end of 1997. Discussions with potential international partners in fabrication development and irradiation testing have begun

Detection methods of irradiated foodstuffs

Energy Technology Data Exchange (ETDEWEB)

Ponta, C C; Cutrubinis, M; Georgescu, R [IRASM Center, Horia Hulubei National Institute for Physics and Nuclear Engineering, PO Box MG-6, RO-077125 Magurele-Bucharest (Romania); Mihai, R [Life and Environmental Physics Department, Horia Hulubei National Institute for Physics and Nuclear Engineering, PO Box MG-6, RO-077125 Magurele-Bucharest (Romania); Secu, M [National Institute of Materials Physics, Bucharest (Romania)

2005-07-01

Full text: Food irradiation has, in certain circumstances, an important role to play both in promoting food safety and in reducing food losses. The safety and availability of nutritious food are essential components of primary health care. WHO actively encourages the proper use of food irradiation in the fight against foodborne diseases and food losses. To this end, it collaborates closely with FAO and IAEA. Food irradiation can have a number of beneficial effects, including delay of ripening and prevention of sprouting; control of insects, parasites, helminths, pathogenic and spoilage bacteria, moulds and yeasts; and sterilization, which enables commodities to be stored unrefrigerated for long periods. The 1990s witnessed a significant advancement in food irradiation processing. As a result, progress has been made in commercialization of the technology, culminating in greater international trade in irradiated foods and the implementation of differing regulations relating to its use in many countries. Codex General Standard for Irradiated Foodstuffs and Recommended International Code of Practice for the Operation of Irradiation Facilities Used for the Treatment of Foods regulate food irradiation at international level. At European Union level there are in power Directive 1999/2/EC and Directive1999/3/EC. Every particular country has also its own regulations regarding food irradiation. In Romania, since 2002 the Norms Regarding Foodstuffs and Food Ingredients Treated by Ionizing Radiation are in power. These Norms are in fact the Romanian equivalent law of the European Directives 1999/2/EC and 1999/3/EC. The greater international trade in irradiated foods has led to the demand by consumers that irradiated food should be clearly labeled as such and that methods capable of differentiating between irradiated and nonirradiated products should be available. Thus a practical basis was sought to allow consumers to exercise a free choice as to which food they purchase. If a

Recent developments in the Sandia Laboratories' sewage sludge irradiation program

Energy Technology Data Exchange (ETDEWEB)

Sivinski, H.D.; Brandon, J.R.; Morris, M.E.; Neuhauser, K.S.; Ward, R.L.; McCaslin, B.; Smith, G.S.

1977-11-01

Pathogen reduction studies have shown that a 1 Mrad treatment (or less at elevated temperatures) is very effective in eliminating pathogenic bacteria and viable parasite ova in liquid sludges. Heat is effective in reducing levels not only of pathogenic bacteria and Ascaris ova, but viruses as well. Ammonia has been shown to be virucidal to poliovirus and several other enteric viruses. Sludge processing costs are seen to be marginally competitive with heat treatment for liquid sludges and relatively economical for composted or dried sludges. Physical/chemical effects studies have shown that the effects of irradiation of sludges on dewatering properties are not significant when compared to polymers, nor is the combined effect synergistic. Dried, irradiated undigested sludge has been shown to be of significant nutritional value when used as a feed supplement for sheep and cattle, as well as in agronomic uses. No significant harmful effects have been demonstrated in the feeding program thus far. Product enhancement studies are currently under way, including schemes for removing nitrogen from effluent streams for addition as ammonium salts to sludges.

Japan`s international cooperation programs on seismic safety of nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Sanada, Akira [Agency of Natural Resources and Energy, Tokyo (Japan)

1997-03-01

MITI is promoting many international cooperation programs on nuclear safety area. The seismic safety of nuclear power plants (NPPs) is a one of most important cooperation areas. Experts from MITI and related organization join the multilateral cooperation programs carried out by international organization such as IAEA, OECD/NEA etc. MITI is also promoting bilateral cooperation programs such as information exchange meetings, training programs and seminars on nuclear safety with several countries. Concerning to the cooperation programs on seismic safety of NPPs such as information exchange and training, MITI shall continue and expand these programs. (J.P.N.)

Aging management of reactor internals and license renewal of US PWR plants

Energy Technology Data Exchange (ETDEWEB)

Tang, H. T. [Electric Power Research Institute, EPRI, 3420 Hillview Avenue, Palo Alto, California 94304 (United States)

2006-09-15

Age-related degradation mechanisms of key components are subject to aging management review by utilities considering plant license renewal. The management of aging effects in PWR internals must be demonstrated as specified in the US NRC Standard Review. The US NRC staff has also issued a Generic Aging Lessons Learned (GALL) report that documents the staff's basis for determining when existing generic programs are adequate to manage aging without change and when existing generic programs should be augmented for license renewal. The EPRI Materials Reliability Program (MRP) has been conducting studies to develop technical bases and guidelines to support aging management of PWR internals, with a particular attention to utility License Renewal commitments. The strategic approach taken by the MRP includes: developing an overall aging management framework, defining degradation mechanism screening values, categorizing and ranking internals components based on screening, performing functionality analyses and safety evaluation, and developing inspection and evaluation guidelines associated with each category of components. Screening criteria are developed for the following potential internals degradation mechanisms: - Stress Corrosion Cracking [Excluding Irradiation Effects]; - Irradiation-Assisted Stress Corrosion Cracking; - Thermal Aging Embrittlement; - Irradiation Embrittlement; - Void Swelling; - Stress Relaxation and Creep [Irradiation-enhanced]; - Wear; - Fatigue. The ranking and categorization calls to bin internals components into four categories: - Category A: component items for which aging degradation significance is minimal and aging effects are below the screening criteria; - Category C: 'lead' component items for which aging degradation significance is high or moderate and aging effects are above screening levels; - Category B: component items above screening levels but are not 'lead' component items and aging degradation significance

Status of fuel irradiation tests in HANARO

International Nuclear Information System (INIS)

Kim, Hark Rho; Lee, Choong Sung; Lee, Kye Hong; Jun, Byung Jin; Lee, Ji Bok

1999-01-01

Since 1996 after finishing the long-term operational test, HANARO (High-Flux Advanced Neutron Application Reactor) has been extensively used for material irradiation tests, beam application research, radioisotope production and neutron activation analysis. This paper presents the fuel irradiation test activities which are now conducted or have been finished in HANARO. KAERI developed LEU fuel using an atomization method for the research reactors. Using this LEU, we have set up and conducted three irradiation programs: (1) medium power irradiation test using a short-length mini-assembly made of 3.15 gU/cc U 3 Si, (2) high power irradiation tests using full-length test assemblies made of 3.15 gU/cc U 3 Si, and (3) irradiation test using a short-length mini-plate made of 4.8 gU/cc U 3 Si 2 . DUPIC (Direct Use of spent PWR fuels in CANDU Reactors) simulation fuel pellets, of which compositions are very similar to DUPIC pellets to keep the similarity in the thermo-mechanical property, were developed. Three mini-elements including 5 pellets each were installed in a capsule. This capsule has been irradiated for 2 months and unloaded from the HANARO core at the end of September 1999. Another very important test is the HANARO fuel qualification program at high power, which is required to resolve the licensing issue. This test is imposed on the HANARO operation license due to insufficient test data under high power environment. To resolve this licensing issue, we have been carrying out the required irradiation tests and PIE (Post-irradiation Examination) tests. Through this program, it is believed that the resolution of the licensing issue is achieved. In addition to these programs, several fuel test plans are under way. Through these vigorous activities of fuel irradiation test programs, HANARO is sure to significantly contribute to the national nuclear R and D programs. (author)

Comparison of advanced reactors program of different international vendors

International Nuclear Information System (INIS)

Agnihotri, N.K.

2001-01-01

The full text follows. Proposal for presenting a paper on Advanced Reactor Program Given below is the abstract for Track 6 session on Advanced Reactor at the ninth International Conference on Nuclear Engineering being held in Nice, France from April 8. through 12. 2001. This paper will provide an update on Advanced Reactor Program of different vendors in the United States, Japan, and Europe. Specifically the paper will look at the history of different Advanced Reactor Programs, international experience, aspect of economy due to standardization, and the highlights of technical specifications. The paper will also review aspects of Economy due to standardization, public acceptance, required construction time, and the experience of different vendors. The objective of the presentation is to underscore the highlights of the Reactor Program of different vendors in order to keep the attendees of the conference up-to-date. The presentation will be an impartial overview from an outsider's (not part of the Nuclear Steam Supply System's staff). (author)

Alaskan Commodities Irradiation Project

International Nuclear Information System (INIS)

Zarling, J.P.; Swanson, R.B.; Logan, R.R.

1988-01-01

The ninety-ninth US Congress commissioned a six-state food irradiation research and development program to evaluate the commercial potential of this technology. Hawaii, Washington, Iowa, Oklahoma and Florida as well as Alaska have participated in the national program; various food products including fishery products, red meats, tropical and citrus fruits and vegetables have been studied. The purpose of the Alaskan study was to review and evaluate those factors related to the technical and economic feasibility of an irradiator in Alaska. This options analysis study will serve as a basis for determining the state's further involvement in the development of food irradiation technology. 40 refs., 50 figs., 53 tabs

Food irradiation: Technology transfer in Asia, practical experiences

Science.gov (United States)

Kunstadt, Peter; Eng, P.

1993-10-01

Nordion International Inc., in cooperation with the Thai Office of Atomic Energy for Peace (OAEP) and the Canadian International Development Agency (CIDA) recently completed a unique food irradiation technology transfer project in Thailand. This complete food irradiation technology transfer project included the design and construction of an automatic multipurpose irradiation facility as well as the services of construction and installation management and experts in facility operation, maintenance and training. This paper provides an insight into the many events that led to the succesful conclusion of the world's first complete food irradiation technology transfer project.

Food irradiation: technology transfer in Asia, practical experiences

International Nuclear Information System (INIS)

Kunstadt, P.

1993-01-01

Nordion International Inc., in cooperation with the Thai Office of Atomic Energy for Peace (OAEP) and the Canadian International Development Agency (CIDA) recently completed a unique food irradiation technology transfer project in Thailand. This complete food irradiation technology transfer project included the design and construction of an automatic multipurpose irradiation facility as well as the services of construction and installation management and experts in facility operation, maintenance and training. This paper provides an insight into the many events that led to the successful conclusion of the world's first complete food irradiation technology transfer project. (Author)

Characterization program, management and isotopic inventory calculation, radiological and fuel thermal irradiated in nuclear power Cofrentes

International Nuclear Information System (INIS)

Albendea, M.; Diego, J. L. de; Urrea, M.

2012-01-01

Characterization is a very detailed and user-friendly program takes into account the history of irradiation individualized and real all the fuel, even taking into account the interim periods are periods of discharge and recharge cycles and which have not been used.

34 CFR 660.1 - What is the International Research and Studies Program?

Science.gov (United States)

2010-07-01

... the HEA by governmental, educational, and private-sector organizations and other studies assessing the... 34 Education 3 2010-07-01 2010-07-01 false What is the International Research and Studies Program...) OFFICE OF POSTSECONDARY EDUCATION, DEPARTMENT OF EDUCATION THE INTERNATIONAL RESEARCH AND STUDIES PROGRAM...

Application of advanced irradiation analysis methods to light water reactor pressure vessel test and surveillance programs

International Nuclear Information System (INIS)

Odette, R.; Dudey, N.; McElroy, W.; Wullaert, R.; Fabry, A.

1977-01-01

Inaccurate characterization and inappropriate application of neutron irradiation exposure variables contribute a substantial amount of uncertainty to embrittlement analysis of light water reactor pressure vessels. Damage analysis involves characterization of the irradiation environment (dosimetry), correlation of test and surveillance metallurgical and dosimetry data, and projection of such data to service conditions. Errors in available test and surveillance dosimetry data are estimated to contribute a factor of approximately 2 to the data scatter. Non-physical (empirical) correlation procedures and the need to extrapolate to the vessel may add further error. Substantial reductions in these uncertainties in future programs can be obtained from a more complete application of available damage analysis tools which have been developed for the fast reactor program. An approach to reducing embrittlement analysis errors is described, and specific examples of potential applications are given. The approach is based on damage analysis techniques validated and calibrated in benchmark environments

Comparison of normal tissue dose with three-dimensional conformal techniques for breast cancer irradiation including the internal mammary nodes

NARCIS (Netherlands)

van der Laan, Hans Paul; Dolsma, Willemtje; van t Veld, Aart; Bijl, HP; Langendijk, JA

2005-01-01

PURPOSE: To compare the Para Mixed technique for irradiation of the internal mammary nodes (IMN) with three commonly used strategies, by analyzing the dose to the heart and other organs at risk. METHODS AND MATERIALS: Four different three-dimensional conformal dose plans were created for 30 breast

Women's Center Volunteer Intern Program: Building Community While Advancing Social and Gender Justice

Science.gov (United States)

Murray, Margaret A.; Vlasnik, Amber L.

2015-01-01

This program description explores the purpose, structure, activities, and outcomes of the volunteer intern program at the Wright State University Women's Center. Designed to create meaningful, hands-on learning experiences for students and to advance the center's mission, the volunteer intern program builds community while advancing social and…

Post irradiation examination technology exchange

International Nuclear Information System (INIS)

Sozawa, Shizuo; Ito, Masayasu; Taguchi, Taketoshi; Nakagawa, Tetsuya; Lee, Hyung-Kwon

2012-01-01

Under the KAERI and JAEA agreement, in a part of the program 18 (Post Irradiation Examination (PIE) and Evaluation Technique of Irradiated Materials), an eddy current test was proposed as a round robin test, and it has been being progressed in both organizations in order to enhance the post irradiation examination technology. Up to now, several data are obtained by both PIE facilities. In this paper, the round robin test program is shown, and also shown obtained data with discussion from applicability as a nondestructive test in the hot cell. (author)

Campus Support Services, Programs, and Policies for International Students

Science.gov (United States)

Bista, Krishna, Ed.; Foster, Charlotte, Ed.

2016-01-01

Study abroad programs have proven beneficial for both the international student as well as the domestic community and school population interacting with the student. In an effort to promote cultural awareness, intercultural communications as well as opportunities for future study abroad program success, universities must take care to provide…

Irradiation experiments and materials testing capabilities in High Flux Reactor in Petten

International Nuclear Information System (INIS)

Luzginova, N.; Blagoeva, D.; Hegeman, H.; Van der Laan, J.

2011-01-01

The text of publication follows: The High Flux Reactor (HFR) in Petten is a powerful multi-purpose research and materials testing reactor operating for about 280 Full Power Days per year. In combination with hot cells facilities, HFR provides irradiation and post-irradiation examination services requested by nuclear energy research and development programs, as well as by industry and research organizations. Using a variety of the custom developed irradiation devices and a large experience in executing irradiation experiments, the HFR is suitable for fuel, materials and components testing for different reactor types. Irradiation experiments carried out at the HFR are mainly focused on the understanding of the irradiation effects on materials; and providing databases for irradiation behavior of materials to feed into safety cases. The irradiation experiments and materials testing at the HFR include the following issues. First, materials irradiation to support the nuclear plant life extensions, for instance, characterization of the reactor pressure vessel stainless steel claddings to insure structural integrity of the vessel, as well as irradiation of the weld material coupons to neutron fluence levels that are representative for Light Water Reactors (LWR) internals applications. Secondly, development and qualification of the structural materials for next generation nuclear fission reactors as well as thermo-nuclear fusion machines. The main areas of interest are in both conventional stainless steel and advanced reduced activation steels and special alloys such as Ni-base alloys. For instance safety-relevant aspects of High Temperature Reactors (HTR) such as the integrity of fuel and structural materials with increasing neutron fluence at typical HTR operating conditions has been recently assessed. Thirdly, support of the fuel safety through several fuel irradiation experiments including testing of pre-irradiated LWR fuel rods containing UO 2 or MOX fuel. Fourthly

International Trade and Education: Issues and Programs. AACJC Issues Series, No. 2.

Science.gov (United States)

Mahoney, James R., Ed.; Sakamoto, Clyde, Ed.

This technical assistance monograph on international trade education was designed to give college officials insights into programs and services offered by a number of postsecondary institutions; to identify problems experienced by program administrators; and to share the perspectives of leaders in international trade education. First, introductory…

Relationship between chromosomal aberration of bone marrow cells and dosage of irradiation after 46Sc internal pollution and external low dose X-irradiation in mice

International Nuclear Information System (INIS)

Li Guofu; Li Zhang; Wu Yin

1989-01-01

The relationship between chromosomal aberration of bone marrow cells and dosage in mice 24 h after 46 Sc internal pollution combined with external low dose whole body X-irradiation was quantiatively studied. The results showed that the relationship between chromosomal aberration and dosage was expressed in a linear regression equation. The chromosomal aberration rate was lower in the combined exposure than that of the sum of internal and external exposures, but higher than that of either the internal or external exposure singly. The relationship between chromosomal aberration and time was expressed in the following three phase exponential function: Y(t) = 2.9078 exp 0.27668t + 2.9371 exp -0.0778t + 2.3786 -0.01788t . By means of fit test, there was no significant difference between the determined and the theoretical values. The 90% theoretical values got from all the equations distributed over the determined values

International Code Assessment and Applications Program: Annual report

International Nuclear Information System (INIS)

Ting, P.; Hanson, R.; Jenks, R.

1987-03-01

This is the first annual report of the International Code Assessment and Applications Program (ICAP). The ICAP was organized by the Office of Nuclear Regulatory Research, United States Nuclear Regulatory Commission (USNRC) in 1985. The ICAP is an international cooperative reactor safety research program planned to continue over a period of approximately five years. To date, eleven European and Asian countries/organizations have joined the program through bilateral agreements with the USNRC. Seven proposed agreements are currently under negotiation. The primary mission of the ICAP is to provide independent assessment of the three major advanced computer codes (RELAP5, TRAC-PWR, and TRAC-BWR) developed by the USNRC. However, program activities can be expected to enhance the assessment process throughout member countries. The codes were developed to calculate the reactor plant response to transients and loss-of-coolant accidents. Accurate prediction of normal and abnormal plant response using the codes enhances procedures and regulations used for the safe operation of the plant and also provides technical basis for assessing the safety margin of future reactor plant designs. The ICAP is providing required assessment data that will contribute to quantification of the code uncertainty for each code. The first annual report is devoted to coverage of program activities and accomplishments during the period between April 1985 and March 1987

Recent advances in detection of irradiated foods

International Nuclear Information System (INIS)

Kawamura, Yoko

1996-01-01

Food irradiation has been applied in many countries and it is desirable to establish the analytical methods needed to determine whether food has been treated or not by irradiation. These methods would serve to check the compliance with labelling regulations in permitting countries and to prevent the illegal import of irradiated foods in prohibiting countries. Initially, it was difficult to find parameters for such detection, since the irradiation treatment has few effects on food quality. Recently, detection techniques are rapidly advancing as a result of international cooperation programs of FAO/IAEA and BCR, and are very close to practicable routine application. The methods for the detection of irradiated foods are required not only discrimination but also specificity, sensitivity, stability and so on. Attempts have been made to apply physical, chemical and biological forms of measurement, and several techniques have been developed for routine analysis. The following techniques will be presented concerning their principle, applicable foods, method, detection limit and so on. Electron Spin Resonance (ESR) Method, Thermoluminescence (TL) Method, Photostimulated Luminescence (PSL) Method, Impedance Method, Viscosity Method, Volatile Hydrocarbon Method, Cyclobutanone Method, DNA Method (Mitochondrial DNA, Comet Assay), Immunochemical Detection Method, Direct Epifluorescent Filter Technique/Aerobic Plate Count (DEFT/APC) Method, Half-embryo Method. Most foodstuffs, which would be practically irradiated, could be detected if the most suitable method is used. The TL method has already been adopted as the official method of the United Kingdom (UK), and the standardized protocol of TL, ESR, Volatile Hydrocarbon and Cyclobutanone Methods could soon be established by the European Committee for Standardization (CEN). The detection technique for irradiated foods could be applied to practicable routine analysis. (author)

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

International program on linear electric motors

Energy Technology Data Exchange (ETDEWEB)

Dawson, G.E.; Eastham, A.R.; Parker, J.H.

1992-05-01

The International Program on Linear Electric Motors (LEM) was initiated for the purposes of commumication and coordination between various centers of expertise in LEM technology in Germany, Japan and Canada. Furthermore, it was intended to provide assessment and support of the planning of technological developments and for dissemination of information to researchers, service operators and policy makers, and to ensure that full advantage can be taken if opportunities for technology transfer occur. In the process, the program was able to provide closer contacts between researchers, to enhance and encourage collaborative research and development, and to facilitate joint ventures in advanced transportation technologies. Work done under the program is documented, and seminar materials presented by Canadian researchers in Italy, and by Italian researchers at Queen's University in Canada are presented. Five separate abstracts have been prepared for the main body of the report and the seminar materials.

Progress of the RERTR program in 2001

International Nuclear Information System (INIS)

Travelli, A.

2002-01-01

This paper describes the 2001 progress achieved by the Reduced Enrichment for Research and Test Reactors (RERTR) Program in collaboration with its many international partners. Postirradiation examinations of microplates have continued to reveal excellent irradiation behavior of U-Mo dispersion fuels in a variety of compositions and irradiating conditions. Irradiation of two new batches of mini plates of greater sizes was completed in the ATR to investigate the swelling behavior of these fuels under prototypic conditions. These materials hold the promise of achieving the program goal of developing LEU research reactor fuels with uranium densities in the 8-9 g/cm 3 range. Qualification of the U-Mo dispersion fuels has been declared by a patent issue involving KAERI. Test fuel elements with uranium density of 6 g/cm 3 are being fabricated by BWXT and are expected to begin undergoing irradiation in the HFR-Petten reactor around March 2003, with a goal of qualifying this fuel by mid 2005. U-Mo fuel with uranium density of 8-9 g/cm 3 is expected to be qualified by mid 2007. Final irradiation tests of LEU 99 Mo targets in the RAS-GAS reactor at BATAN, in Indonesia, had to be postponed because of the 9/11 attacks, but the results collected to date indicate that these targets will soon be ready for commercial production. Excellent cooperation is also in progress with the CNEA in Argentina, MDSN/ AECL in Canada, and ANSTO in Australia. Irradiation testing of five WWR-M2 tube-type fuel assemblies fabricated by the NZChK and containing LEU UO 2 dispersion fuel was successfully completed within the Russian RERTR program. A new LEU U-Mo pin-type fuel that could be used to convert most Russian-designed research reactors has been developed by VNIJNM and is ready for testing. Four additional shipments containing 822 spent fuel assemblies from foreign research reactors were accepted by the U.S. by September 30, 2001. Altogether, 4'562 spent fuel assemblies from foreign research

Progress of the RERTR program in 2001

Energy Technology Data Exchange (ETDEWEB)

Travelli, A. [Technology Development Division Argonne National Laboratory, 9700 South Cass Avenue, Argonne, Illinois 60439-4841 (United States)

2002-07-01

This paper describes the 2001 progress achieved by the Reduced Enrichment for Research and Test Reactors (RERTR) Program in collaboration with its many international partners. Postirradiation examinations of microplates have continued to reveal excellent irradiation behavior of U-Mo dispersion fuels in a variety of compositions and irradiating conditions. Irradiation of two new batches of mini plates of greater sizes was completed in the ATR to investigate the swelling behavior of these fuels under prototypic conditions. These materials hold the promise of achieving the program goal of developing LEU research reactor fuels with uranium densities in the 8-9 g/cm{sup 3} range. Qualification of the U-Mo dispersion fuels has been declared by a patent issue involving KAERI. Test fuel elements with uranium density of 6 g/cm{sup 3} are being fabricated by BWXT and are expected to begin undergoing irradiation in the HFR-Petten reactor around March 2003, with a goal of qualifying this fuel by mid 2005. U-Mo fuel with uranium density of 8-9 g/cm{sup 3} is expected to be qualified by mid 2007. Final irradiation tests of LEU {sup 99}Mo targets in the RAS-GAS reactor at BATAN, in Indonesia, had to be postponed because of the 9/11 attacks, but the results collected to date indicate that these targets will soon be ready for commercial production. Excellent cooperation is also in progress with the CNEA in Argentina, MDSN/ AECL in Canada, and ANSTO in Australia. Irradiation testing of five WWR-M2 tube-type fuel assemblies fabricated by the NZChK and containing LEU UO{sub 2} dispersion fuel was successfully completed within the Russian RERTR program. A new LEU U-Mo pin-type fuel that could be used to convert most Russian-designed research reactors has been developed by VNIJNM and is ready for testing. Four additional shipments containing 822 spent fuel assemblies from foreign research reactors were accepted by the U.S. by September 30, 2001. Altogether, 4'562 spent fuel

The Lunar and Planetary Institute Summer Intern Program in Planetary Science

Science.gov (United States)

Kramer, G. Y.

2017-12-01

Since 1977, the Lunar and Planetary Institute (LPI) Summer Intern Program brings undergraduate students from across the world to Houston for 10 weeks of their summer where they work one-on-one with a scientist at either LPI or Johnson Space Center on a cutting-edge research project in the planetary sciences. The program is geared for students finishing their sophomore and junior years, although graduating seniors may also apply. It is open to international undergraduates as well as students from the United States. Applicants must have at least 50 semester hours of credit (or equivalent sophomore status) and an interest in pursuing a career in the sciences. The application process is somewhat rigorous, requiring three letters of recommendation, official college transcripts, and a letter describing their background, interests, and career goals. The deadline for applications is in early January of that year of the internship. More information about the program and how to apply can be found on the LPI website: http://www.lpi.usra.edu/lpiintern/. Each advisor reads through the applications, looking for academically excellent students and those with scientific interest and backgrounds compatible with the advisor's specific project. Interns are selected fairly from the applicant pool - there are no pre-arranged agreements or selections based on who knows whom. The projects are different every year as new advisors come into the program, and existing ones change their research interest and directions. The LPI Summer Intern Program gives students the opportunity to participate in peer-reviewed research, learn from top-notch planetary scientists, and preview various careers in science. For many interns, this program was a defining moment in their careers - when they decided whether or not to follow an academic path, which direction they would take, and how. While past interns can be found all over the world and in a wide variety of occupations, all share the common bond of

Policy plan for the early approval for irradiated meat products and the promotion of irradiated meats in market

Energy Technology Data Exchange (ETDEWEB)

Lee, Ju Woon [Team for Radiation Food Science and Biotechnology, Advanced Radiation Technology Institute, Korea Atomic Energy Research Institute, Jeongeup (Korea, Republic of); Kim, Wang Geun [Ministry of Education, Science and Technology, Seoul (Korea, Republic of); Kim, Kyong Su [Dept. of Food and Nutrition, Chosun University, Gwangju (Korea, Republic of); Yook, Hong Sun [Dept. of Food and Nutrition, Chungnam National University, Daejeon (Korea, Republic of); Kim, Cheon Jei [Division of Animal Life Science, Konkuk University, Seoul (Korea, Republic of)

2008-11-15

The consumption of meat products is gradually being increased by the development of livestock raising technology, industrialized farm management and international trade. This increased consumption also created new market for ready-to-eat and ready-to-cook meat products. However, these convenience meat products can be easily contaminated during the processing and storage by pathogens, and there have been many reported cases of food borne illness by meats. One of the most effective methods for the decontamination of meat products is the radiation technology. Food irradiation was the established, well-recognized and safe sterilization method. Many other countries researched the effect of irradiation on the meat products and approved the irradiation. In this article, the effectiveness, the international acceptance, the economics and the research trend of irradiation on meat products have been reviewed. Also, the policy plans for the early approval of the irradiated meat products in Korea and the promotion policy of irradiated meats in market were discussed.

Policy plan for the early approval for irradiated meat products and the promotion of irradiated meats in market

International Nuclear Information System (INIS)

Lee, Ju Woon; Kim, Wang Geun; Kim, Kyong Su; Yook, Hong Sun; Kim, Cheon Jei

2008-01-01

The consumption of meat products is gradually being increased by the development of livestock raising technology, industrialized farm management and international trade. This increased consumption also created new market for ready-to-eat and ready-to-cook meat products. However, these convenience meat products can be easily contaminated during the processing and storage by pathogens, and there have been many reported cases of food borne illness by meats. One of the most effective methods for the decontamination of meat products is the radiation technology. Food irradiation was the established, well-recognized and safe sterilization method. Many other countries researched the effect of irradiation on the meat products and approved the irradiation. In this article, the effectiveness, the international acceptance, the economics and the research trend of irradiation on meat products have been reviewed. Also, the policy plans for the early approval of the irradiated meat products in Korea and the promotion policy of irradiated meats in market were discussed

Promoting Dark Skies Awareness Programs Beyond the International Year of Astronomy 2009

Science.gov (United States)

Walker, Constance E.; Dark Skies Working Group

2010-01-01

The preservation of dark skies is a growing global concern, yet it is one of the easiest environmental problems people can address on local levels. For this reason, the goal of the International Year of Astronomy 2009 (IYA2009) Dark Skies Awareness Cornerstone Project is to raise public awareness of the impact of artificial lighting on local environments by getting people worldwide involved in a variety of programs. These programs provide resources on light pollution for new technologies like a presence in Second Life and podcasts, for local thematic events at national parks and observatory open houses, for international thematic events like International Dark Skies Week and Earth Hour, for a program in the arts like an international photo contest, for global citizen-science programs that measure night sky brightness worldwide, and for educational materials like a kit with a light shielding demonstration. These programs have been successfully used around the world during IYA2009 to raise awareness of the effects of light pollution on public health, economic issues, ecological consequences, energy conservation, safety and security, and astronomy. The poster will provide an update, take a look ahead at the project's sustainability, and describe how people can be involved in the future. Information about the programs is at www.darkskiesawareness.org.

International Piping Integrity Research Group (IPIRG) Program. Final report

International Nuclear Information System (INIS)

Wilkowski, G.; Schmidt, R.; Scott, P.

1997-06-01

This is the final report of the International Piping Integrity Research Group (IPIRG) Program. The IPIRG Program was an international group program managed by the U.S. Nuclear Regulatory Commission and funded by a consortium of organizations from nine nations: Canada, France, Italy, Japan, Sweden, Switzerland, Taiwan, the United Kingdom, and the United States. The program objective was to develop data needed to verify engineering methods for assessing the integrity of circumferentially-cracked nuclear power plant piping. The primary focus was an experimental task that investigated the behavior of circumferentially flawed piping systems subjected to high-rate loadings typical of seismic events. To accomplish these objectives a pipe system fabricated as an expansion loop with over 30 meters of 16-inch diameter pipe and five long radius elbows was constructed. Five dynamic, cyclic, flawed piping experiments were conducted using this facility. This report: (1) provides background information on leak-before-break and flaw evaluation procedures for piping, (2) summarizes technical results of the program, (3) gives a relatively detailed assessment of the results from the pipe fracture experiments and complementary analyses, and (4) summarizes advances in the state-of-the-art of pipe fracture technology resulting from the IPIRG program

International Piping Integrity Research Group (IPIRG) Program. Final report

Energy Technology Data Exchange (ETDEWEB)

Wilkowski, G.; Schmidt, R.; Scott, P. [and others

1997-06-01

This is the final report of the International Piping Integrity Research Group (IPIRG) Program. The IPIRG Program was an international group program managed by the U.S. Nuclear Regulatory Commission and funded by a consortium of organizations from nine nations: Canada, France, Italy, Japan, Sweden, Switzerland, Taiwan, the United Kingdom, and the United States. The program objective was to develop data needed to verify engineering methods for assessing the integrity of circumferentially-cracked nuclear power plant piping. The primary focus was an experimental task that investigated the behavior of circumferentially flawed piping systems subjected to high-rate loadings typical of seismic events. To accomplish these objectives a pipe system fabricated as an expansion loop with over 30 meters of 16-inch diameter pipe and five long radius elbows was constructed. Five dynamic, cyclic, flawed piping experiments were conducted using this facility. This report: (1) provides background information on leak-before-break and flaw evaluation procedures for piping, (2) summarizes technical results of the program, (3) gives a relatively detailed assessment of the results from the pipe fracture experiments and complementary analyses, and (4) summarizes advances in the state-of-the-art of pipe fracture technology resulting from the IPIRG program.

Internal Contamination Program in hospital and biomedical research institutions

International Nuclear Information System (INIS)

Tellez de Cepeda, M.; Macias, M.T.; Plaza, R.; Martinez Hidalgo, C.

1992-01-01

Program and the criteria for establishing such program to control the internal contamination from a point of view, not yet systematized and standardized in Hospital and Biomedical Research centers. The main purpose of this work is to review our own situation, to establish and systematize an operative program with variable means (instruments) and the use of external means if need. This program will be established taking into account the new recommendations of I.C.R.P. and the new criteria A.L.I. (author)

Influence of ion irradiation on internal residual stress in DLC films

Energy Technology Data Exchange (ETDEWEB)

Karaseov, Platon A., E-mail: platon.karaseov@rphf.spbstu.r [St. Petersburg State Polytechnic University, Polytechnicheskaya St. 29, 195251 St. Petersburg (Russian Federation); Podsvirov, Oleg A.; Karabeshkin, Konstantin V. [St. Petersburg State Polytechnic University, Polytechnicheskaya St. 29, 195251 St. Petersburg (Russian Federation); Vinogradov, Andrei Ya. [Ioffe Physicotechnical Institute RAS, Polytechnicheskaya 26, 195252 St. Petersburg (Russian Federation); Azarov, Alexander Yu. [St. Petersburg State Polytechnic University, Polytechnicheskaya St. 29, 195251 St. Petersburg (Russian Federation); Karasev, Nikita N. [State University of Information Technologies, Mechanics and Optics, Sablinskaya Str. 14, 197101 St. Petersburg (Russian Federation); Titov, Andrei I.; Smirnov, Alexander S. [St. Petersburg State Polytechnic University, Polytechnicheskaya St. 29, 195251 St. Petersburg (Russian Federation)

2010-10-01

The dependence of internal residual stress in thin diamond-like carbon films grown on Si substrate by PECVD technique on most important growth parameters, namely RF-power, DC bias voltage and substrate temperature, is described. Results show that compressive stress reaches the highest value of 2.7 GPa at low RF-power and DC bias. Increase of substrate temperature from 250 to 350 {sup o}C leads to nonlinear increase of stress value. Inhomogeneity of residual stress along the film surface disappears when film is deposited at temperatures above 275 {sup o}C. Post-growth film irradiation by P{sup +} and In{sup +} ions cause decrease of compressive stress followed by its inversion to tensile. For all ion energy combinations used residual stress changes linearly with normalized fluence up to 0.2 DPA with slope (8.7 {+-} 1.3) GPa/DPA.

International electives in neurology training: a survey of US and Canadian program directors.

Science.gov (United States)

Lyons, Jennifer L; Coleman, Mary E; Engstrom, John W; Mateen, Farrah J

2014-01-14

To ascertain the current status of global health training and humanitarian relief opportunities in US and Canadian postgraduate neurology programs. There is a growing interest among North American trainees to pursue medical electives in low- and middle-income countries. Such training opportunities provide many educational and humanitarian benefits but also pose several challenges related to organization, human resources, funding, and trainee and patient safety. The current support and engagement of neurology postgraduate training programs for trainees to pursue international rotations is unknown. A survey was distributed to all program directors in the United States and Canada (December 2012-February 2013) through the American Academy of Neurology to assess the training opportunities, institutional partnerships, and support available for international neurology electives. Approximately half of responding programs (53%) allow residents to pursue global health-related electives, and 11% reported that at least 1 trainee participated in humanitarian relief during training (survey response rate 61%, 143/234 program directors). Canadian programs were more likely to allow residents to pursue international electives than US programs (10/11, 91% vs 65/129, 50%, p = 0.023). The number of trainees participating in international electives was low: 0%-9% of residents (55% of programs) and 10%-19% of residents (21% of programs). Lack of funding was the most commonly cited reason for residents not participating in global health electives. If funding was available, 93% of program directors stated there would be time for residents to participate. Most program directors (75%) were interested in further information on global health electives. In spite of high perceived interest, only half of US neurology training programs include international electives, mostly due to a reported lack of funding. By contrast, the majority of Canadian programs that responded allow international

Can the sentinel lymph node technique affect decisions to offer internal mammary chain irradiation?

International Nuclear Information System (INIS)

Bourre, Jean-Cyril; Payan, Raoul; Collomb, Delphine; Gallazzini-Crepin, Celine; Calizzano, Alex; Desruet, Marie-Dominique; Pasquier, Dominique; Bolla, Michel; Fagret, Daniel; Vuillez, Jean-Philippe

2009-01-01

Identification of the sentinel lymph node (SLN) for small mammary tumours (cT1N0) sometimes leads to detection of internal mammary chain (IMC) drainage. This information is often ignored by physicians. The present study sought to determine the frequency with which an internal mammary SLN was identified by peritumoral injection of radioactive tracer, and then to determine the patients in whom identification of an internal mammary SLN could have an impact on the radiation treatment plan. Between March 2002 and March 2008, 622 SLN biopsies performed in a cohort of 608 patients were analysed. Technetium-labelled nanocolloids were administered via three peritumoral injections, completed by a deep prepectoral injection, with the entire procedure performed under echographic guidance. The SLN was identified in 607 of the 622 patients, including 174 (28.7%) in the IMC. A total of 161 successful internal mammary biopsies were performed. Of the 622 patients, 18 showed SLN involvement in the IMC. In 7 of these patients, only the internal mammary SLN was affected. Prophylactic irradiation of the IMC was indicated in 376 patients, but only in 18 (4.8%) of these patients was there effectively IMC involvement; internal mammary SLN biopsy failed in 7 patients (1.9%). SLN detection by peritumoral injection, combined with the systematic removal of the internal mammary SLN, enabled the involvement of this region to be found in a nonnegligible number of patients. Such information should make it possible to personalize treatment for patients with stage cT1 mammary cancer and thereby avoid needless internal mammary radiation therapy in a large number of patients (93.4% in our study). (orig.)

Summary of FAO/IAEA Seminar on Food Irradiation for Developing Countries in Asia and the Pacific

International Nuclear Information System (INIS)

1982-01-01

A summary is presented of papers submitted to the FAO/IAEA Seminar on Food Irradiation for Developing Countries in Asia and the Pacific, held in Tokyo, 9-13 November 1981. Five reviewed papers on the status of national and international programs on food irradiation, and four communications on irradiation of dried fishery products were presented. The moisture content of fishery products typically ranged from 6 to 40% and the salt content from 0 to 11%. Six papers were presented on the preservation of root crops. Four papers dealt with hygienic conditions of spices and meat products. Five papers were presented on insect disinfestation of fruits and four papers were presented in the session on the commercial use of food irradiation. The round table discussion is summed up and adopted recommendations listed

Irradiation damage

International Nuclear Information System (INIS)

Howe, L.M.

2000-01-01

There is considerable interest in irradiation effects in intermetallic compounds from both the applied and fundamental aspects. Initially, this interest was associated mainly with nuclear reactor programs but it now extends to the fields of ion-beam modification of metals, behaviour of amorphous materials, ion-beam processing of electronic materials, and ion-beam simulations of various kinds. The field of irradiation damage in intermetallic compounds is rapidly expanding, and no attempt will be made in this chapter to cover all of the various aspects. Instead, attention will be focused on some specific areas and, hopefully, through these, some insight will be given into the physical processes involved, the present state of our knowledge, and the challenge of obtaining more comprehensive understanding in the future. The specific areas that will be covered are: point defects in intermetallic compounds; irradiation-enhanced ordering and irradiation-induced disordering of ordered alloys; irradiation-induced amorphization

Irradiation damage

Energy Technology Data Exchange (ETDEWEB)

Howe, L.M

2000-07-01

There is considerable interest in irradiation effects in intermetallic compounds from both the applied and fundamental aspects. Initially, this interest was associated mainly with nuclear reactor programs but it now extends to the fields of ion-beam modification of metals, behaviour of amorphous materials, ion-beam processing of electronic materials, and ion-beam simulations of various kinds. The field of irradiation damage in intermetallic compounds is rapidly expanding, and no attempt will be made in this chapter to cover all of the various aspects. Instead, attention will be focused on some specific areas and, hopefully, through these, some insight will be given into the physical processes involved, the present state of our knowledge, and the challenge of obtaining more comprehensive understanding in the future. The specific areas that will be covered are: point defects in intermetallic compounds; irradiation-enhanced ordering and irradiation-induced disordering of ordered alloys; irradiation-induced amorphization.

Quality evaluation of garlic irradiated in Argentine and stored in Brazil

International Nuclear Information System (INIS)

Curzio, Osvaldo A.; Croci, Clara A.; Domarco, Rachel E.; Spoto, Marta H.F.; Blumer, Lucimara; Walder, Julio M.M.

1997-01-01

This work was undertaken to evaluate the quality of garlic Colorado, irradiated in Argentina and stored for long period of time under environmental conditions in Brazil. Two samples of 100 kg each were selected from high quality garlic harvested in December/1995 from a region close to the Universidad Nacional del Sur. At 30 days after harvesting one of the samples were irradiated with a dose of 60 Gy. Both samples, irradiated and non irradiated, were transported by road from the Laboratorio de Radioisotopos of the Universidad Nacional del Sur, Bahia Blanca, Argentina, to the Centro de Energia Nuclear na Agriculture (CENA-USP), Piracicaba, Sao Paulo, Brazil. The effects of irradiation on weigh loss , discard, germination and sensorial analysis were nonthly observed on CENA among 30and 180 days of storage. The evaluation of germination evidences the benefits of the radioinhibition process. The irradiated bulbs did not exhibit any intern bud, however the non-irradiated bulbs exhibit any intern bud, however the non-irradiated bulbs exhibit any intern bud, however the non-irradiated bulbs exhibit 100% of germination on the period of storage. At the end of the period of storage, the weigh loss of the irradiated garlic was smaller than the non-irradiate one. The percentage of discard, evaluated as intern germination, scatying and whitering, was 43% on the irradiated sample. The analysis of sensorial parameters shows no difference between irradiated and non-irradiated garlic, so irradaition did not affect the sensorial quality of the product. (author). 12 refs., 8 tabs

Food irradiation: Some regulatory and technical aspects

International Nuclear Information System (INIS)

1985-10-01

An Advisory Group by IAEA and FAO on Regulatory and Technological Requirements for Authorization of the Food Irradiation Process was held at IAEA Headquarters in Vienna from 5 to 9 November 1984. The task of the Advisory Group was to advise on the scientific and technological considerations affecting the implementation of the food irradiation process, with particular reference to the facilitation of international trade in irradiated foods and to develop guidance on how the various provisions of the Codex General Standard on Irradiated Foods could be incorporated into national legislation in order to facilitate international trade and avoid the occurence of trade barriers. Separate abstracts were prepared for the various presentations at this meeting

Improving the efficiency of CDTN's Gamma Irradiation Laboratory with additional designed turntables

International Nuclear Information System (INIS)

Silva, Luiz Leite da; Albino, Sergio Celeghini; Candido, Marcos Antonio; Grossi, Pablo Andrade; Correa, Ricardo Ferracini; Pinto, Fausto Carvalho

2007-01-01

The Gamma Irradiation Laboratory (LIG) of CDTN was originally supplied with four turntables. Operating with this configuration was a loss of time and irradiation volume, what induced the Irradiator's staff creating an optimisation production program. Firstly, the staff requests the Gamma Irradiator Manufacturer a quotation for new turntables, but the price was very high. Secondly, the CDTN Design Group was invited to develop new LIG turntables. The groups worked together and found a very good solution. The new turntables are much cheaper and their rotating plate diameters are increased in 5 cm and four of them were made to attend the LIG demand. They have been in operation without significant problems for 1.5 years and absorbed an estimated dose of 7 MGy. This fact confirms the design and materials good quality. Operating with the eight turntables was possible to improve the LIG irradiation capacity in six times in weigh and in volume. Irradiation time is reduced; nowadays doses up to 5 KGy can be done in the same day. For irradiation doses greater than 5 KGy, the process was speeded up by positioning the new turntables in the spaces between the original ones. With this operational configuration the samples receive the dose escaped in those spaces. Calculation of the new dose necessary for the sample is done and it is repositioned in the internals turntables to finish the irradiation process. With this technique the samples do not need to wait so much on the line. The scope of the research program includes day and night operation. Continuously operating in association with the four new turntables enhanced the original operational capacity of the LIG fifteen times. The objectives of this work are to present the developed turntables characteristics and the results acquired. (author)

High Burnup Effects Program

International Nuclear Information System (INIS)

Barner, J.O.; Cunningham, M.E.; Freshley, M.D.; Lanning, D.D.

1990-04-01

This is the final report of the High Burnup Effects Program (HBEP). It has been prepared to present a summary, with conclusions, of the HBEP. The HBEP was an international, group-sponsored research program managed by Battelle, Pacific Northwest Laboratories (BNW). The principal objective of the HBEP was to obtain well-characterized data related to fission gas release (FGR) for light water reactor (LWR) fuel irradiated to high burnup levels. The HBEP was organized into three tasks as follows: Task 1 -- high burnup effects evaluations; Task 2 -- fission gas sampling; and Task 3 -- parameter effects study. During the course of the HBEP, a program that extended over 10 years, 82 fuel rods from a variety of sources were characterized, irradiated, and then examined in detail after irradiation. The study of fission gas release at high burnup levels was the principal objective of the program and it may be concluded that no significant enhancement of fission gas release at high burnup levels was observed for the examined rods. The rim effect, an as yet unquantified contributor to athermal fission gas release, was concluded to be the one truly high-burnup effect. Though burnup enhancement of fission gas release was observed to be low, a full understanding of the rim region and rim effect has not yet emerged and this may be a potential area of further research. 25 refs., 23 figs., 4 tabs

ERG [Engineering Review Group] review of the SRP [Salt Repository Project] salt irradiation effects program: Technical report

International Nuclear Information System (INIS)

Clark, D.E.

1986-11-01

The Engineering Review Group (ERG) was established by the Office of Nuclear Waste Isolation (ONWI) to help evaluate engineering-related issues in the US Department of Energy's nuclear waste repository program. The August 1985 meeting of the ERG reviewed the Salt Repository Project (SRP) salt irradiation effects program. This report documents the ERG's comments and recommendations on these subjects and the ONWI response to the specific points raised by the ERG

Minority International Research Training Program: Global Collaboration in Nursing Research.

Science.gov (United States)

McElmurry, Beverly J.; Misner, Susan J.; Buseh, Aaron G.

2003-01-01

The Minority International Research Training Program pairs minority nursing students with faculty mentors at international sites for short-term research. A total of 26 undergraduate, 22 graduate, and 6 postdoctoral students have participated. Challenges include recruitment, orientation, and preparation of students; identification and preparation…

Issues in food irradiation

International Nuclear Information System (INIS)

Mills, S.

1987-04-01

This discussion paper has two goals: first, to raise public awareness of food irradiation, an emerging technology in which Canada has the potential to build a new industry, mainly oriented to promising overseas markets; and second, to help build consensus among government and private sector decision makers about what has to be done to realize the domestic and export potential. The following pages discuss the potential of food irradiation; indicate how food is irradiated; outline the uses of food irradiation; examine questions of the safety of the equipment and both the safety and nutritional value of irradiated food; look at international commercial developments; assess the current and emerging domestic scene; and finally, draw some conclusions and offer suggestions for action

Design of single-walled NaK capsules for fast breeder fuel pins irradiation (IVO-FR2-Vg7 program)

International Nuclear Information System (INIS)

Lopez Jimenez, J.; Hafner, H.E.

1979-01-01

In Frame of the Joint Irradiation Program IVO-FR2 between the Nuclear Research Centre of Karlsruhe (RFA) and the Junta de Energia Nuclear (Spain) is carried out in the FR2 reactor (Karlsruhe) the irradiation of 12 mixed-oxide fuel rods of 172 mm length. These test rods are first irradiated under various conditions in four modified FR2 capsule (Typ 7). Two versions of single-walled NaK (78% K) are used for this purpose. This report contains the design and description of these two capsule versions as well as the considerations required to oftain the operations licence, supplemented by the relevant figures. (author)

New developments in food irradiation

International Nuclear Information System (INIS)

Molins, R.

1996-01-01

Food irradiation technology is rapidly gaining worldwide acceptance as a promising tool to help alleviate some important food security and safety concerns, and to facilitate the international trade in food. Because of the different priorities that these issues receive in various countries, food irradiation is being considered by developing countries as the technology of choice over chemical fumigants in applications related to the reduction of food losses such as the insect disinfestation of stored staple and export commodities and the inhibition of sprouting of bulb and tuber crops. In contrast, the use of irradiation as a 'cold pasteurization' method to improve the hygienic quality and safety of foods is emerging as the primary field of application in developed countries. Moreover, the use of irradiation as an alternative, non-chemical quarantine treatment for fresh fruits, vegetables and other agricultural commodities entering international trade will no doubt benefit exporting as well as importing countries. 4 figs

Year-End Clinic Handoffs: A National Survey of Academic Internal Medicine Programs.

Science.gov (United States)

Phillips, Erica; Harris, Christina; Lee, Wei Wei; Pincavage, Amber T; Ouchida, Karin; Miller, Rachel K; Chaudhry, Saima; Arora, Vineet M

2017-06-01

While there has been increasing emphasis and innovation nationwide in training residents in inpatient handoffs, very little is known about the practice and preparation for year-end clinic handoffs of residency outpatient continuity practices. Thus, the latter remains an identified, yet nationally unaddressed, patient safety concern. The 2014 annual Association of Program Directors in Internal Medicine (APDIM) survey included seven items for assessing the current year-end clinic handoff practices of internal medicine residency programs throughout the country. Nationwide survey. All internal medicine program directors registered with APDIM. Descriptive statistics of programs and tools used to formulate a year-end handoff in the ambulatory setting, methods for evaluating the process, patient safety and quality measures incorporated within the process, and barriers to conducting year-end handoffs. Of the 361 APDIM member programs, 214 (59%) completed the Transitions of Care Year-End Clinic Handoffs section of the survey. Only 34% of respondent programs reported having a year-end ambulatory handoff system, and 4% reported assessing residents for competency in this area. The top three barriers to developing a year-end handoff system were insufficient overlap between graduating and incoming residents, inability to schedule patients with new residents in advance, and time constraints for residents, attendings, and support staff. Most internal medicine programs do not have a year-end clinic handoff system in place. Greater attention to clinic handoffs and resident assessment of this care transition is needed.

Food irradiation

International Nuclear Information System (INIS)

Anon.

1984-01-01

Food preservation by irradiation is one part of Eisenhower's Atoms for Peace program that is enjoying renewed interest. Classified as a food additive by the Food, Drug, and Cosmetic Act of 1958 instead of a processing technique, irradiation lost public acceptance. Experiments have not been done to prove that there are no health hazards from gamma radiation, but there are new pressures to get Food and Drug Administration approval for testing in order to make commercial use of some radioactive wastes. Irradiation causes chemical reactions and nutritional changes, including the destruction of several vitamins, as well as the production of radiolytic products not normally found in food that could have adverse effects. The author concludes that, lacking epidemiological evidence, willing buyers should be able to purchase irradiated food as long as it is properly labeled

In-pile irradiation test program and safety analysis report of the KAERI fuel for HANARO

Energy Technology Data Exchange (ETDEWEB)

Hwang, Wan; Ryu, Woo Suck; Byun, Taek Sang; Park, Jong Man; Lee, Byung Chul; Kim, Hack No; Park, Hee Tae; Kim, Chang Kyu [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

1996-05-01

Localization of HANARO fuel has been carried out successfully, and design and fabrication technologies of the fuel are recently arrived the final stage of development. The performance of the fuel which has been fabricated in KAERI is confirmed through out-of-pile characterization, and the quality assurance procedure and assessment criteria are described. In order to verify the KAERI fuel, thus, in-pile irradiation test program of the KAERI fuel is scheduled in HANARO. This report summarizes the in-pile testing schedule, design documents of test rods and assemblies, fabrication history and out-of-pile characteristics of test rods, irradiation test condition and power history, post-irradiation examination scheme, linear power generation distribution, and safety analysis results. The design code for HANARO fuel is used to analyze the centerline temperature and swelling of the KAERI fuels. The results show that at 120 kW/m of linear power the maximum centerline temperature is 267 deg C which is much lower than the limitation temperature of 350 deg C, and that the swelling is 9.3 % at 95 at% lower than criterion of 20 %. Therefore, the KAERI fuels of this in-pile irradiation test is assessed to show good performance of integrity and safety in HANARO. 10 tabs., 7 figs., 3 refs. (Author).

Components production and assemble of the irradiation capsule of the Surveillance Program of Materials of the nuclear power plant of Laguna Verde

International Nuclear Information System (INIS)

Medrano, A.

2009-01-01

To predict the effects of the neutrons radiation and the thermal environment about the mechanical properties of the reactor vessel materials of the nuclear power plant of Laguna Verde, a surveillance program is implemented according to the outlines settled by Astm E185-02 -Standard practice for design of surveillance programs for light-water moderated nuclear power reactor vessels-. This program includes the installation of three irradiation capsules of similar materials to those of the reactor vessels, these samples are test tubes for mechanical practices of impact and tension. In the National Institute of Nuclear Research and due to the infrastructure as well as of the actual human resources of the Pilot Plant of Nuclear Fuel Assembles Production it was possible to realize the materials rebuilding extracted in 2005 of Unit 2 of nuclear power plant of Laguna Verde as well as the production, assemble and reassignment of the irradiation capsule made in 2006. At the present time the surveillance materials extracted in 2008 of Unit 1 of the nuclear power plant of Laguna Verde are reconstituting and the components are manufactured for the assembles of the irradiation capsule that will be reinstalled in the reactor vessel in 2010. The purpose of the present work is to describe the necessary components as well as its disposition during the assembles of the irradiation capsule for the surveillance program of the reactors vessel of the nuclear power plant of Laguna Verde. (Author)

Food irradiation for phytosanitary and quarantine treatment

Science.gov (United States)

Irradiation at doses less than 1 kGy is an effective phytosanitary measure with minimal adverse effects on the quality of most fresh produce. There are internationally recognized guidelines for the use of irradiation as a phytosanitary measure and for the conduct of trade in irradiated fresh produce...

Assessment of necessary regularity of internal irradiation monitoring on the basis of direct and indirect methods of dosimetry

International Nuclear Information System (INIS)

Malykhin, V.M.; Ivanova, N.I.

1981-01-01

It is shown that when assessing the necessary periodicity of internal irradiation monitoring, it is required to take account of the nature (rhythm) of radionuclide intake to the organism during the monitoring period, the effective period of radionuclide biological half-life, its activity in the organism, sensitivity of the technique applied and the labour-consumig character of the monitoring method [ru

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)

Potato irradiation technology in Japan

International Nuclear Information System (INIS)

Takehisa, M.

1981-01-01

After the National research program on potato irradiation, the public consumption of potatoes irradiated to a maximum of 15 krad was authorized by the Ministry of Welfare. Shihoro Agricultural Cooperative Association, one of the largest potato producers in Japan with an annual production of 200,000 tons, intended an application of the irradiation to their potato storage system. This paper describes the technological background of the potato irradiation facility and operational experience. (author)

Palliative Care Exposure in Internal Medicine Residency Education: A Survey of ACGME Internal Medicine Program Directors.

Science.gov (United States)

Edwards, Asher; Nam, Samuel

2018-01-01

As the baby boomer generation ages, the need for palliative care services will be paramount and yet training for palliative care physicians is currently inadequate to meet the current palliative care needs. Nonspecialty-trained physicians will need to supplement the gap between supply and demand. Yet, no uniform guidelines exist for the training of internal medicine residents in palliative care. To our knowledge, no systematic study has been performed to evaluate how internal medicine residencies currently integrate palliative care into their training. In this study, we surveyed 338 Accreditation Council for Graduate Medical Education-accredited internal medicine program directors. We queried how palliative care was integrated into their training programs. The vast majority of respondents felt that palliative care training was "very important" (87.5%) and 75.9% of respondents offered some kind of palliative care rotation, often with a multidisciplinary approach. Moving forward, we are hopeful that the data provided from our survey will act as a launching point for more formal investigations into palliative care education for internal medicine residents. Concurrently, policy makers should aid in palliative care instruction by formalizing required palliative care training for internal medicine residents.

Selection of irradiator for potato preservation

Energy Technology Data Exchange (ETDEWEB)

Kinsara, A R; Melaibari, A G; Abulfaraj, W H; Mamoon, A M; Kamal, S E [Nuclear Engineering Department, Faculty of Engineering, King Abdulaziz University P.O.Box 9027, Jeddah-21413, (Saudi Arabia)

1997-12-31

A formal decision methodology is a sound approach for assisting in decision making needed for the selection of irradiators for Potato preservation. A formal analysis is preferred over an informal intuitive analysis which has limitations. This will focus on substantial issues and provide the basis for a compromise between conflicting objectives. All critical issues in selection of irradiators for Potato preservation can be addressed within the decision analysis framework. Of special significance is the treatment of the uncertainly associated with consequences of a decision and the preferences of the experts. A decision theory is employed in providing a strategy for implementation of the irradiator selection for food preservation for Saudi Arabia. To select a suitable decision methodology for the present case, a detailed survey of available decision methods was conducted. These methods have been developed and applied with varying degrees of success to many diverse areas of interest. Based on detailed surveys, the Analytic Hierarchy process (AHP) was selected to evaluate the various irradiators for Potato irradiation. These are electron accelerators, X-ray irradiators, and gamma irradiators. The purpose was to determine the optimal. The set of factors impacting irradiator selection were developed and defined to provide comprehensive and realistic variables that judge the represented irradiator alternatives. The factors developed are economic considerations, technical considerations, safety aspects, and compatibility with local environment. The AHP computer program was developed to computerize the tedious complicated computations towards implementing the AHP systematic procedures to solve the present problem. The program was developed using FOXPRO. Based upon the available data, and employing the APH computer program, the results show superiority of {sup 60} Co gamma-ray irradiator over other irradiators for saudi arabia`s present circumstances. 2 figs.,7 tabs.

Study of bixin oxidation by ionizing irradiation

International Nuclear Information System (INIS)

Fonseca, Thais N.; Teixeira, Paula S.; Moura, Eduardo de; Geraldo, Áurea Beatriz C.

2017-01-01

Brazil is the world's largest producer of anatto, followed by Kenya and Peru. The fruit of the annatto tree is constituted by a capsule containing external spines and internal seeds with reddish coloration, providing a natural pigment which is environmentally efficient, being able to replace synthetic pigments and dyes. The active substance of the pigment is Bixin, which is a type of carotenoid which constitutes a greater percentage of pigment in these seeds and has a lipo soluble character. Bixin reacts with NaOH in a saponification reaction giving norbixin, which is water soluble. It is known that the destination of the dye extracted from the fruit is intended for industry, especially the food industry. The culture of annatto tree brings prospects of development in agricultural programs for medium and small producers, which are able to use decadent areas of other crops. In addition to the food sector, new applications for the pigment helps the development of family farming. The pigment extracted from annatto undergoes a natural oxidation; this work aims to evaluate this phenomenon and also the oxidation of the pigment after the irradiation process. This work also evaluates of the how the oxidation process is affected by irradiation and the modifications introduced to irradiated pigments. Irradiated and nonirradiated samples were characterized by thermogravimetry, UV-vis spectrophotometry and infrared spectroscopy (FTIR). The results are then discussed. (author)

The International Coal Statistics Data Base program maintenance guide

International Nuclear Information System (INIS)

1991-06-01

The International Coal Statistics Data Base (ICSD) is a microcomputer-based system which contains information related to international coal trade. This includes coal production, consumption, imports and exports information. The ICSD is a secondary data base, meaning that information contained therein is derived entirely from other primary sources. It uses dBase III+ and Lotus 1-2-3 to locate, report and display data. The system is used for analysis in preparing the Annual Prospects for World Coal Trade (DOE/EIA-0363) publication. The ICSD system is menu driven and also permits the user who is familiar with dBase and Lotus operations to leave the menu structure to perform independent queries. Documentation for the ICSD consists of three manuals -- the User's Guide, the Operations Manual, and the Program Maintenance Manual. This Program Maintenance Manual provides the information necessary to maintain and update the ICSD system. Two major types of program maintenance documentation are presented in this manual. The first is the source code for the dBase III+ routines and related non-dBase programs used in operating the ICSD. The second is listings of the major component database field structures. A third important consideration for dBase programming, the structure of index files, is presented in the listing of source code for the index maintenance program. 1 fig

International Energy Agency Solar Heating and Cooling Program

Science.gov (United States)

Brooks, A. J.

This trip was undertaken to participate in and represent the United States Industry at the International Energy Agency (IEA) Solar Heating and Cooling Program (SHCP) Task 14 Workshop. The meeting took place at the A1 Bani Hotel in Rome Italy.

Guidelines for acceptance of food irradiation

International Nuclear Information System (INIS)

1987-09-01

The purpose of the meeting was to develop an action plan which can be applied in countries with varying philosophies towards food irradiation, but which would help foster a common international attitude to what is undoubtedly a controversial issue. Basic recommendations were to: Identify target groups which influence policy in regard to food irradiation; Establish a cohesive marketing strategy with flexibility to meet varied national needs; Implement an ongoing communications system designed to reach and inform decision-makers; Work in each country through an information ''chain'' commencing with irradiation processors; Promote to - and through - the food industry as potentially the greatest beneficiaries; Set up an administrative ''Clearing House'' in each country to co-ordinate promotion efforts; Assemble ''Seeding Groups'' who will contact and communicate with other organizations; Aim for common international branding and packaging identification for irradiated foods

Needs and Acculturative Stress of International Students in CACREP Programs

Science.gov (United States)

Behl, Malvika; Laux, John M.; Roseman, Christopher P.; Tiamiyu, Mojisola; Spann, Sammy

2017-01-01

International students enrolled in programs accredited by the Council for Accreditation of Counseling and Related Educational Programs provided acculturative stress and needs data. Acculturative stress was correlated with academic, social, language, and cultural needs. Furthermore, relationships were found between students' types of needs.…

Evaluating Security Assistance Programs: Performance Evaluation and the Expanded International Military Education and Training (E-IMET) Program

National Research Council Canada - National Science Library

Calhoun, Todd

1998-01-01

In 1991 the International Military Education and Training (IMET) program was expanded to include training programs focusing on civilian control over the military, respect for human rights, and responsible defense resource management...

International Coordination of and Contributions to Environmental Satellite Programs.

Science.gov (United States)

1985-06-01

the international coordination of, and contributions to, environmental satellite programs. It re- views the background and history of international...Earth’s atmos- phere, surface temperature, cloud cover, water-ice boundaries, * and proton and electron flux near the Earth. They have the capability of...Islands Madagascar Sweden Chile Malaysia Switzerland China, People’s Rep. of Mali Syria Colombia Malta Tahiti Costa Rica Martinique Taiwan Curacao

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)

Irradiation experiment conceptual design parameters for MURR LEU U-Mo fuel conversion

International Nuclear Information System (INIS)

Stillman, J.; Feldman, E.; Stevens, J.; Wilson, E.

2013-03-01

This report contains the results of reactor design and performance calculations for conversion of the University of Missouri Research Reactor (MURR) from the use of highly-enriched uranium (HEU) fuel to the use of low-enriched uranium (LEU) fuel. The analyses were performed by staff members of the Global Threat Reduction Initiative (GTRI) Reactor Conversion Program at the Argonne National Laboratory (ANL) and the MURR Facility. The core conversion to LEU is being performed with financial support from the U. S. government. In the framework of its non-proliferation policies, the international community presently aims to minimize the amount of nuclear material available that could be used for nuclear weapons. In this geopolitical context most research and test reactors, both domestic and international, have started a program of conversion to the use of LEU fuel. A new type of LEU fuel based on an alloy of uranium and molybdenum (U-Mo) is expected to allow the conversion of U.S. domestic high performance reactors like MURR. This report presents the nominal steady-state irradiation conditions of a key set of plates containing peak irradiation parameters found in MURR cores fueled with the LEU monolithic U-Mo alloy fuel with 10 wt% Mo.

Irradiation techniques at BR2 reactor

International Nuclear Information System (INIS)

Hebel, W.

1978-01-01

Since 1963 the material testing reactor BR2 at Mol is operated for the realisation of numerous research programs and experiments on the behavior of materials under nuclear radiation and in particular under intensive neutron exposure. During this period special irradiation techniques and experimental devices were developed according to the desiderata of the different experiments and to the irradiation possibilities offered at BR2. The design and the operating characteristics of quite a number of those irradiation rigs of proven reliability may be used or can be made available for new irradiation experiments. A brief description is given of some typical irradiation devices designed and constructed by CEN/SCK, Technology and Energy Dpt. They are compiled according to their main use for the different research and development programs realized at BR2. Their eventual application however for different objectives could be possible. A final chapter summarizes the principal irradiation conditions offered by BR2 reactor. (author)

Safety factors influencing the acceptance of food irradiation technology

International Nuclear Information System (INIS)

1989-01-01

The International Consultative Group on Food Irradiation convened a Task Force Meeting on Public Information of Food Irradiation at the French Commissariat a l'Energie Atomique (CEA), Cadarache from 18 to 21 April 1988. A compilation of scientific papers on subjects of public interest on food irradiation was made by internationally-recognized experts. The report of the meeting and the review papers presented at the meeting are included in this publication. Refs, figs and tabs

Proceedings of 2012 JAEA/KAERI joint seminar on advanced irradiation and PIE technologies

International Nuclear Information System (INIS)

Ishihara, Masahiro; Ishitsuka, Etsuo; Suzuki, Masahide

2012-12-01

Under the 'Arrangement for Corporation in the field of peaceful uses of Nuclear Energy between the Japan Atomic Energy Agency (JAEA) and the Korean Atomic Energy Research Institute (KAERI)', the 2012 JAEA/KAERI Joint Seminar on Advanced Irradiation and PIE (post-irradiation examination) Technologies has been held at Mito, Japan from March 28 to 30, 2012. This triennial seminar is the seventh in series of bilateral exchange of irradiation and PIE technologies and research reactor management. Since the first joint seminar on the PIE Technology between JAERI (Japan Atomic Energy Research Institute, former agency of JAEA) and KAERI was held at JAERI Oarai Research Institute, Japan in 1992, the international cooperation program between JAEA and KAERI has been actively carried out in the field of neutron irradiation. At the fifth seminar in 2005 and sixth in 2008, the irradiation technology and the research reactor management fields were included, respectively, to the joint seminar, and it covers whole areas of irradiation using research reactors. In this seminar total 37 presentations were made in three technical sessions, which are 'research reactor management', 'advanced irradiation technology' and 'post-irradiation examination technology', and active information exchange was done among participants. Papers or manuscripts presented in the 2012 JAEA/KAERI Joint Seminar on Advanced Irradiation and PIE Technologies are contained in the proceedings. (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)

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)

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)

R and D programs of the International Energy Agency

International Nuclear Information System (INIS)

Dyne, P.J.

1989-01-01

This paper provides a description of the collaborative research program of the International Energy Agency. Focusing on the organization of the program, rather than attempting to cover the technical content of the research, the discussion conveys how its operation is facilitated through a framework that takes account of the interests of participating governments as well as technical objectives. Some Canadian activities in the IEA program are briefly described as illustration and a list of current IEA Research Agreements and associated activities is presented in an Appendix

The Text of an Agreement for Collaboration in an International Programme on Irradiation of Fruit and Fruit Juices

Energy Technology Data Exchange (ETDEWEB)

NONE

1965-08-12

The text of the Agreement between the Agency, the Osterreichische Studiengesellschaft fuer Atomenergie GmbH and the Organisation for Economic Co-operation and Development for Collaboration in an International Programme on Irradiation of Fruit and Fruit Juices, which was signed on 16 September 1964 and entered into force on 1 January 1965, is reproduced in this document for the information of all Members of the Agency,.

The Text of an Agreement for Collaboration in an International Programme on Irradiation of Fruit and Fruit Juices

International Nuclear Information System (INIS)

1965-01-01

The text of the Agreement between the Agency, the Osterreichische Studiengesellschaft fuer Atomenergie GmbH and the Organisation for Economic Co-operation and Development for Collaboration in an International Programme on Irradiation of Fruit and Fruit Juices, which was signed on 16 September 1964 and entered into force on 1 January 1965, is reproduced in this document for the information of all Members of the Agency,

75 FR 26945 - International Education Programs Service-Fulbright-Hays Group Projects Abroad Program

Science.gov (United States)

2010-05-13

.... Schools and/or departments of education have a role to play in creating greater exposure since they are... DEPARTMENT OF EDUCATION International Education Programs Service--Fulbright-Hays Group Projects... Postsecondary Education, Department of Education. ACTION: Notice of proposed priorities. SUMMARY: The Assistant...

Investigations of fuel cladding chemical interaction in irradiated LMFBR type oxide fuel pins

International Nuclear Information System (INIS)

Roake, W.E.; Adamson, M.G.; Hilbert, R.F.; Langer, S.

1977-01-01

subassemblies in EBR-II and selected encapsulated tests irradiated in GETR. Other comparative tests in thermal reactors indicate that fast flux and thermal flux results are similar. An adequate understanding of FCCI requires integration of in reactor tests and out-of-reactor applied and fundamental studies. To this end a Fuel Cladding Chemical Interaction Program has been established involving several ERDA laboratories and contractors. Other papers to be presented at this international meeting will describe: FCCI work being carried on out-of-reactor but simulating reactor irradiation conditions; studies using all available data sources aimed at illuminating the mechanism and developing models for FCCI; in-reactor and out-of-reactor tests using various techniques and materials whose objectives are to prevent serious FCCI or to mitigate its effect on fuel pin behavior; and the application of FCCI data to lifetime estimates and design criteria

Investigations of fuel cladding chemical interaction in irradiated LMFBR type oxide fuel pins

Energy Technology Data Exchange (ETDEWEB)

Roake, W E [Westinghouse-Hanford Co., Richland, WA (United States); Adamson, M G [General Electric Company, Vallecitos Nuclear Center, Pleasanton, CA (United States); Hilbert, R F; Langer, S

1977-04-01

subassemblies in EBR-II and selected encapsulated tests irradiated in GETR. Other comparative tests in thermal reactors indicate that fast flux and thermal flux results are similar. An adequate understanding of FCCI requires integration of in reactor tests and out-of-reactor applied and fundamental studies. To this end a Fuel Cladding Chemical Interaction Program has been established involving several ERDA laboratories and contractors. Other papers to be presented at this international meeting will describe: FCCI work being carried on out-of-reactor but simulating reactor irradiation conditions; studies using all available data sources aimed at illuminating the mechanism and developing models for FCCI; in-reactor and out-of-reactor tests using various techniques and materials whose objectives are to prevent serious FCCI or to mitigate its effect on fuel pin behavior; and the application of FCCI data to lifetime estimates and design criteria.

Deployment summary: Fiscal years 1995-2000 [USDOE Office of International Programs

International Nuclear Information System (INIS)

2000-01-01

This publication summarizes the progress made by the Office of International Programs (IP) in deploying innovative technologies for the environmental remediation of the DOE complex and for sites of its international collaborators for fiscal years 1995 through 2000

Deployment summary: Fiscal years 1995-2000 [USDOE Office of International Programs

Energy Technology Data Exchange (ETDEWEB)

None

2000-07-01

This publication summarizes the progress made by the Office of International Programs (IP) in deploying innovative technologies for the environmental remediation of the DOE complex and for sites of its international collaborators for fiscal years 1995 through 2000.

The return of food irradiation

International Nuclear Information System (INIS)

Hammerton, K.

1992-01-01

In discussing the need for food irradiation the author examines the problems that arise in processing foods of different kinds: spices, meat, fruits and vegetables. It is demonstrated that the relatively low dose of radiation required to eliminate the reproductive capacity of the pest can be tolerated by most fruits and vegetables without damage. Moreover the safety of irradiated food is acknowledged by major national and international food organizations and committees. The author agreed that when food irradiation has been approved by a country, consumers should be able to choose between irradiated and non-irradiated food. To enable the choice, clear and unambiguous labelling must be enforced. 13 refs., 1 tab., ills

An overview of food irradiation

International Nuclear Information System (INIS)

Stevenson, M.H.

1991-01-01

This outline survey reviews the subject of food irradiation under the following headings:- brief history, the process (sources, main features of a food processing facility, interaction of radiation with food, main applications of the technology, packaging) consumer concerns (safety, nutritional changes, labelling, detection), international use of food irradiation and legal aspects. (UK)

Summary report of consultants' meeting on IAEA international database on irradiated nuclear graphite properties

International Nuclear Information System (INIS)

Humbert, D.; Wickham, A.J.

2007-06-01

The '9th Meeting of the Technical Steering Committee for the International Database on Irradiated Nuclear Graphite Properties' was held on 26-27 March 2007 at the IAEA Headquarters, Vienna, Austria. All discussions, recommendations and actions of this Consultants' Meeting are recorded in this report. The purposes of the meeting were to review the matters and actions identified in the previous meeting, undertake a review of the current status of the database and make recommendations for actions for the next year. This report contains the current status of the identified actions as well as a summary of the recommendations on enhancements to the database. (author)

Hazard evaluation of The International Fusion Materials Irradiation Facility

Energy Technology Data Exchange (ETDEWEB)

Burgazzi, Luciano [ENEA-Centro Ricerche ' Ezio Clementel' , Advanced Physics Technology Division, Via Martiri di Monte Sole, 4, 40129 Bologna (Italy)]. E-mail: burgazzi@bologna.enea.it

2005-01-15

The International Fusion Materials Irradiation Facility (IFMIF) is aimed to provide an intense neutron source by a high current deuteron linear accelerator and a high-speed lithium flow target, for testing candidate materials for fusion. Liquid lithium is being circulated through a loop and is kept at a temperature above its freezing point. In the frame of the design phase called Key Element technology Phase (KEP), jointly performed by an international team to verify the most important risk factors, safety assessment of the whole plant has been required in order to identify the hazards associated with the plant operation. This paper discusses the safety assessments that were performed and their outcome: Failure Mode and Effect Analysis (FMEA) approach has been adopted in order to accomplish the task. Main conclusions of the study is that, on account of the safety and preventive measures adopted, potential plant related hazards are confined within the IFMIF security boundaries and great care must be exercised to protect workers and site personnel from operating the plant. The analysis has provided as a result a set of Postulated Initiating Events (PIEs), that is off-normal events, that could result in hazardous consequences for the plant, together with the total frequency and the list of component failures which could induce the PIE: this assures the exhaustive list of major initiating events of accident sequences, helpful to the further accident sequence analysis phase. Finally, for each one of the individuated PIEs, the evaluation of the accident evolution, in terms of effects on the plant and relative countermeasures, has allowed to verify that adequate measures are being taken both to prevent the accident occurrence and to cope with the accident consequences, thus assuring the fulfilment of the safety requirements.

34 CFR 658.4 - What definitions apply to the Undergraduate International Studies and Foreign Language Program?

Science.gov (United States)

2010-07-01

... International Studies and Foreign Language Program? 658.4 Section 658.4 Education Regulations of the Offices of... UNDERGRADUATE INTERNATIONAL STUDIES AND FOREIGN LANGUAGE PROGRAM General § 658.4 What definitions apply to the Undergraduate International Studies and Foreign Language Program? The definitions in 34 CFR 655.4 apply to this...

The international framework for safeguarding peaceful nuclear energy programs

International Nuclear Information System (INIS)

Mazer, B.M.

1980-01-01

International law, in response to the need for safeguard assurances, has provided a framework which can be utilized by supplier and recipient states. Multilateral treaties have created the International Atomic Energy Agency which can serve a vital role in the establishment and supervision of safeguard agreements for nuclear energy programs. The Non-Proliferation Treaty has created definite obligations on nuclear-weapon and non-nuclear weapon states to alleviate some possibilities of proliferation and has rejuvenated the function of the IAEA in providing safeguards, especially to non-nuclear-weapon states which are parties to the Non-Proliferation treaty. States which are not parties to the Non-Proliferation Treaty may receive nuclear energy co-operation subject to IAEA safeguards. States like Canada, have insisted through the bilateral nuclear energy co-operation agreements that either individual or joint agreement be reached with the IAEA for the application of safeguards. Trilateral treaties among Canada, the recipient state and the IAEA have been employed and can provide the necessary assurances against the diversion of peaceful nuclear energy programs to military or non-peaceful uses. The advent of the Nuclear Suppliers Group and its guidlines has definitely advanced the cause of ensuring peaceful uses of nuclear energy. The ultimate objective should be the creation of an international structure incorporating the application of the most comprehensive safeguards which will be applied universally to all nuclear energy programs

Consumer acceptance of irradiated poultry

International Nuclear Information System (INIS)

Hashim, I.B.; Resurreccion, A.V.A.; McWatters, K.H.

1995-01-01

A simulated supermarket setting (SSS) test was conducted to determine whether consumers (n = 126) would purchase irradiated poultry products, and the effects of marketing strategies on consumer purchase of irradiated poultry products. Consumer preference for irradiated poultry was likewise determined using a home-use test. A slide program was the most effective educational strategy in changing consumers' purchase behavior. The number of participants who purchased irradiated boneless, skinless breasts and irradiated thighs after the educational program increased significantly from 59.5 and 61.9% to 83.3 and 85.7% for the breasts and thighs, respectively. Using a label or poster did not increase the number of participants who bought irradiated poultry products. About 84% of the participants consider it either 'somewhat necessary' or 'very necessary' to irradiate raw chicken and would like all chicken that was served in restaurants or fast food places to be irradiated. Fifty-eight percent of the participants would always buy irradiated chicken if available, and an additional 27% would buy it sometimes. About 44% of the participants were willing to pay the same price for irradiated chicken as for nonirradiated. About 42% of participants were willing to pay 5% or more than what they were currently paying for nonirradiated chicken. Seventy-three percent or more of consumers who participated in the home-use test (n = 74) gave the color, appearance, and aroma of the raw poultry products a minimum rating of 7 (= like moderately). After consumers participated in a home-use test, 84 and 88% selected irradiated thighs and breasts, respectively, over nonirradiated in a second SSS test

Consumer acceptance of irradiated poultry.

Science.gov (United States)

Hashim, I B; Resurreccion, A V; McWatters, K H

1995-08-01

A simulated supermarket setting (SSS) test was conducted to determine whether consumers (n = 126) would purchase irradiated poultry products, and the effects of marketing strategies on consumer purchase of irradiated poultry products. Consumer preference for irradiated poultry was likewise determined using a home-use test. A slide program was the most effective educational strategy in changing consumers' purchase behavior. The number of participants who purchased irradiated boneless, skinless breasts and irradiated thighs after the educational program increased significantly from 59.5 and 61.9% to 83.3 and 85.7% for the breasts and thighs, respectively. Using a label or poster did not increase the number of participants who bought irradiated poultry products. About 84% of the participants consider it either "somewhat necessary" or "very necessary" to irradiate raw chicken and would like all chicken that was served in restaurants or fast food places to be irradiated. Fifty-eight percent of the participants would always buy irradiated chicken if available, and an additional 27% would buy it sometimes. About 44% of the participants were willing to pay the same price for irradiated chicken as for nonirradiated. About 42% of participants were willing to pay 5% or more than what they were currently paying for nonirradiated chicken. Seventy-three percent or more of consumers who participated in the home-use test (n = 74) gave the color, appearance, and aroma of the raw poultry products a minimum rating of 7 (= like moderately). After consumers participated in a home-use test, 84 and 88% selected irradiated thighs and breasts, respectively, over nonirradiated in a second SSS test.

77 FR 61740 - Call for Applications for the International Buyer Program-Calendar Years 2014 and 2015

Science.gov (United States)

2012-10-11

... should describe in detail the international marketing program to be conducted for the event, and explain... DEPARTMENT OF COMMERCE International Trade Administration [Docket No. 120913451-2451-01] Call for Applications for the International Buyer Program-- Calendar Years 2014 and 2015 AGENCY: International Trade...

Operating plan for the Office of International Health Programs

International Nuclear Information System (INIS)

1996-01-01

In this report unified ideas are presented about what the Office of International Health Programs does, what the individual contributions are, and how the organization connects to the Department of Energy. The planning efforts have focused on the office's three areas of responsibility: Europe, Japan, and the Marshall Islands. Common to each technical program area are issues related to the following: health of populations exposed to radiation incidents and the associated medical aspects of exposure; dose reconstruction; training; and public involvement. Each of the program areas, its customers, and primary customer interests are described

Thermonuclear controlled fusion: international cooperation

International Nuclear Information System (INIS)

Conscience, J.-F.

2001-01-01

This report summarizes the current worldwide status of research in the field of thermonuclear controlled fusion as well as the international research programme planed for the next decades. The two main projects will be the ITER facility (International Thermonuclear Experimental Reactor) that should produce 10 times more energy than the energy injected, and the IFMIF (International Fusion Materials Irradiation Facility) designed to study the reactions of materials under intense neutron fluxes. The future of the pioneering JET facility (Joint European Torus) is also discussed. The engagement of the various countries (USA, Japan, Germany, Russian Federation and Canada) and international organisations (EURATOM and IEA) in terms of investment and research is described. Switzerland is involved in this program through an agreement with EURATOM and is mainly dedicated to experimental studies with the TCV machine in Lausanne and numerical studies of plasma configurations. It will participate to the development of the microwave plasma heating system for the ITER machine

A new model for accreditation of residency programs in internal medicine.

Science.gov (United States)

Goroll, Allan H; Sirio, Carl; Duffy, F Daniel; LeBlond, Richard F; Alguire, Patrick; Blackwell, Thomas A; Rodak, William E; Nasca, Thomas

2004-06-01

A renewed emphasis on clinical competence and its assessment has grown out of public concerns about the safety, efficacy, and accountability of health care in the United States. Medical schools and residency training programs are paying increased attention to teaching and evaluating basic clinical skills, stimulated in part by these concerns and the responding initiatives of accrediting, certifying, and licensing bodies. This paper, from the Residency Review Committee for Internal Medicine of the Accreditation Council for Graduate Medical Education, proposes a new outcomes-based accreditation strategy for residency training programs in internal medicine. It shifts residency program accreditation from external audit of educational process to continuous assessment and improvement of trainee clinical competence.

CERT tribal internship program. Final intern report: Maria Perez, 1994

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-09-01

Historically, American Indian Tribes have lacked sufficient numbers of trained, technical personnel from their communities to serve their communities; tribal expertise in the fields of science, business and engineering being extremely rare and programs to encourage these disciplines almost non-existent. Subsequently, Tribes have made crucial decisions about their land and other facets of Tribal existence based upon outside technical expertise, such as that provided by the United States government and/or private industries. These outside expert opinions rarely took into account the traditional and cultural values of the Tribes being advised. The purpose of this internship was twofold: Create and maintain a working relationship between CERT and Colorado State University (CSU) to plan for the Summit on Tribal human resource development; and Evaluate and engage in current efforts to strengthen the Tribal Resource Institute in Business, Engineering and Science (TRIBES) program. The intern lists the following as the project results: Positive interactions and productive meetings between CERT and CSU; Gathered information from Tribes; CERT database structure modification; Experience as facilitator in participating methods; Preliminary job descriptions for staff of future TRIBES programs; and Additions for the intern`s personal database of professional contacts and resources.

Guidelines and procedures for the International Code Assessment and Applications Program

International Nuclear Information System (INIS)

1987-04-01

This document presents the guidelines and procedures by which the International Code Assessment and Applications Program (ICAP) will be conducted. The document summarizes the management structure of the program and the relationships between and responsibilities of the United States Nuclear Regulatory Commission (USNRC) and the international participants. The procedures for code maintenance and necessary documentation are described. Guidelines for the performance and documentation of code assessment studies are presented. An overview of an effort to quantify code uncertainty, which the ICAP supports, is included

Food irradiation: an emerging opportunity for African countries

International Nuclear Information System (INIS)

Adu-Gyamfi, A.

2004-01-01

Full Text. The paper reviews the use of food irradiation technology and its potential in food processing and international trade for economic development of African countries. Provision of infrastructure along with technical expertise, private sector anticipation, effective collaborative ventures and networking with other countries and international agencies are considered crucial for Africa to harness the potential of food irradiation. (author)

High gamma-rays irradiation tests of critical components for ITER (International Thermonuclear Experimental Reactor) in-vessel remote handling system

International Nuclear Information System (INIS)

Obara, Kenjiro; Kakudate, Satoshi; Oka, Kiyoshi

1999-02-01

In ITER, the in-vessel remote handling is inevitably required to assemble and maintain the activated in-vessel components due to deuterium and tritium operation. Since the in-vessel remote handling system has to be operated under the intense of gamma ray irradiation, the components of the remote handling system are required to have radiation hardness so as to allow maintenance operation for a sufficient length of time under the ITER in-vessel environments. For this, the Japan, European and Russian Home Teams have extensively conducted gamma ray irradiation tests and quality improvements including optimization of material composition through ITER R and D program in order to develop radiation hard components which satisfy the doses from 10 MGy to 100 MGy at a dose rate of 1 x 10 6 R/h (ITER R and D Task: T252). This report describes the latest status of radiation hard component development which has been conducted by the Japan Home Team in the ITER R and D program. The number of remote handling components tested is about seventy and these are categorized into robotics (Subtask 1), viewing system (Subtask 2) and common components (Subtask 3). The irradiation tests, including commercial base products for screening, modified products and newly developed products to improve the radiation hardness, were carried out using the gamma ray irradiation cells in Takasaki Establishment, JAERI. As a result, the development of the radiation hard components which can be tolerable for high temperature and gamma radiation has been well progressed, and many components, such as AC servo motor with ceramics insulated wire, optical periscope and CCD camera, have been newly developed. (author)

High gamma-rays irradiation tests of critical components for ITER (International Thermonuclear Experimental Reactor) in-vessel remote handling system

Energy Technology Data Exchange (ETDEWEB)

Obara, Kenjiro; Kakudate, Satoshi; Oka, Kiyoshi [Department of Fusion Engineering Research, Naka Fusion Research Establishment, Japan Atomic Energy Research Institute, Naka, Ibaraki (Japan)] [and others

1999-02-01

In ITER, the in-vessel remote handling is inevitably required to assemble and maintain the activated in-vessel components due to deuterium and tritium operation. Since the in-vessel remote handling system has to be operated under the intense of gamma ray irradiation, the components of the remote handling system are required to have radiation hardness so as to allow maintenance operation for a sufficient length of time under the ITER in-vessel environments. For this, the Japan, European and Russian Home Teams have extensively conducted gamma ray irradiation tests and quality improvements including optimization of material composition through ITER R and D program in order to develop radiation hard components which satisfy the doses from 10 MGy to 100 MGy at a dose rate of 1 x 10{sup 6} R/h (ITER R and D Task: T252). This report describes the latest status of radiation hard component development which has been conducted by the Japan Home Team in the ITER R and D program. The number of remote handling components tested is about seventy and these are categorized into robotics (Subtask 1), viewing system (Subtask 2) and common components (Subtask 3). The irradiation tests, including commercial base products for screening, modified products and newly developed products to improve the radiation hardness, were carried out using the gamma ray irradiation cells in Takasaki Establishment, JAERI. As a result, the development of the radiation hard components which can be tolerable for high temperature and gamma radiation has been well progressed, and many components, such as AC servo motor with ceramics insulated wire, optical periscope and CCD camera, have been newly developed. (author)

International Border Management Systems (IBMS) Program : visions and strategies.

Energy Technology Data Exchange (ETDEWEB)

McDaniel, Michael; Mohagheghi, Amir Hossein

2011-02-01

Sandia National Laboratories (SNL), International Border Management Systems (IBMS) Program is working to establish a long-term border security strategy with United States Central Command (CENTCOM). Efforts are being made to synthesize border security capabilities and technologies maintained at the Laboratories, and coordinate with subject matter expertise from both the New Mexico and California offices. The vision for SNL is to provide science and technology support for international projects and engagements on border security.

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)

2013 Iowa DOT engineering intern development and management program.

Science.gov (United States)

2013-11-01

The Institute for Transportation (InTrans) at Iowa State University (ISU) developed an internship mentoring program in collaboration : with the Iowa Department of Transportation (DOT) to provide additional mentorship to both student interns and Iowa ...

The post-irradiated examination of CANDU type fuel irradiated in the Institute for Nuclear Research TRIGA reactor

International Nuclear Information System (INIS)

Tuturici, I.L.; Parvan, M.; Dobrin, R.; Popov, M.; Radulescu, R.; Toma, V.

1995-01-01

This post-irradiation examination work has been done under the Research Contract No. 7756/RB, concluded between the International Atomic Energy Agency and the Institute for Nuclear Research. The paper contains a general description of the INR post-irradiation facility and methods and the relevant post-irradiation examination results obtained from an irradiated experimental CANDU type fuel element designed, manufactured and tested by INR in a power ramp test in the 100 kW Pressurised Water Irradiation Loop of the TRIGA 14 MW(th) Reactor. The irradiation experiment consisted in testing an assembly of six fuel elements, designed to reach a bumup of ∼ 200 MWh/kgU, with typical CANDU linear power and ramp rate. (author)

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)

The response of peripheral blood and bone marrow to combined irradiation

International Nuclear Information System (INIS)

Yakovleva, N.G.; Zhorno, L.Ya.

1975-01-01

Biological effects were examined in rats after X irradiation, oral administration of 90 Sr and 144 Ce as well as combined exposure to X radiation and internal contamination with both radionuclides. Morphological changes of the peripheral blood and the frequency of aberrant mitoses in bone marrow cells were used as criteria. In the case of combined radiation exposure three periods were observed with regard to blood changes. The first period was characterized by changes caused by external irradiation, the second one was a short-term period of normalization, and during the last period additive effects of external and internal irradiation were observed. Considering the changes of the frequency of aberrant mitoses only two periods could be detected according to the effects of external and internal irradiation. It is pointed out that in the case of combined irradiation the acute radiation syndrome caused by external irradiation gradually changes into a chronic stage associated with the long-term retention of radionuclides. (author)

Educative campaign about information on irradiated foods

International Nuclear Information System (INIS)

Luna C, P.C.

1991-07-01

The irradiation of foods is accepted by international agencies (FAO, OMS) like a healthy and effective technology at the moment the irradiated foods are marketed easily in many countries, however in other countries exist several factors that affect the practical application of this process. In this work is planned about an educational campaign about the irradiation process directed to the consumers. (Author)

Progress report on the accelerator production of tritium materials irradiation program

International Nuclear Information System (INIS)

Maloy, S.A.; Sommer, W.F.; Brown, R.D.; Roberts, J.E.

1997-01-01

The Accelerator Production of Tritium (APT) project is developing an accelerator and a spoliation neutron source capable of producing tritium through neutron capture on He-3. A high atomic weight target is used to produce neutrons that are then multiplied and moderated in a blanket prior to capture. Materials used in the target and blanket region of an APT facility will be subjected to several different and mixed particle radiation environments; high energy protons (1-2 GeV), protons in the 20 MeV range, high energy neutrons, and low energy neutrons, depending on position in the target and blanket. Flux levels exceed 10 14 /cm 2 s in some areas. The APT project is sponsoring an irradiation damage effects program that will generate the first data-base for materials exposed to high energy particles typical of spallation neutron sources. The program includes a number of candidate materials in small specimen and model component form and uses the Los Alamos Spallation Radiation Effects Facility (LASREF) at the 800 MeV, Los Alamos Neutron Science Center (LANSCE) accelerator

Localizing by autoradiography at -195 deg radioactive areas in rats exposed to a high flux of thermal neutrons, importance of phosphorus 32 in consecutive internal irradiation; Localisation par autoradiographie a -195 deg des zones radioactives chez le rat expose a un haut flux de neutrons thermiques, importance du phosphore 32 dans l'irradiation interne consecutive

Energy Technology Data Exchange (ETDEWEB)

Chanteur, J; Pellerin, P [Commissariat a l' Energie Atomique, Saclay (France).Centre d' Etudes Nucleaires

1961-07-01

Rats weighing 25 g were exposed for 5 mn to a flux of 6.10{sup 12} thermal neutrons/cm{sup 2}/s. Anatomical autoradiography at -195 deg. C has enabled the radioactive organs to be easily localised, to follow in course of time the decrease of radioactivity, and from it to deduce the probable nature of the numerous emitters in question. In particular, the phosphorus 32 has thus appeared to be one of those responsible for internal irradiation, general, on the one hand, by activating cellular phosphorus, local, on the other, by activating bony phosphates. Owing to this, an accidental irradiation by neutrons might have consequences that are both somatic (elective irradiation of the bone marrow) and genetic (activation of nucleic acids). The gamma spectrometry has confirmed the nature of certain other emitters. (author) [French] Des rats de 25 g ont ete exposes pendant 5 mn a un flux de 6.10{sup 12} neutrons thermiques/cm{sup 2}/s. L'autoradiographie anatomique a -195 deg. C a permis de localiser facilement les organes radioactifs, de suivre dans le temps la decroissance de la radioactivite, et d'en deduire la nature probable des nombreux emetteurs en cause. En particulier, le phosphore 32 est ainsi apparu comme l'un des responsables de l'irradiation interne, d'une part generale par activation du phosphore cellulaire, d'autre part locale par activation des phosphates osseux. Une irradiations accidentelle par neutrons aurait, de ce fait, des consequences a la fois somatiques (irradiation elective de la moelle osseuse) et genetiques (activation des acides nucleiques). La spectrometrie gamma a confirme la nature de certains autres emetteurs. (auteur)

Legal, administrative and psychological barriers to the industrial application of food irradiation and the trade in irradiated food

International Nuclear Information System (INIS)

Cornelis, J.C.

1978-01-01

As a result of the recent evaluations of a joint FAO/IAEA/WHO Expert Committee almost all scientific hesitations against the use of irradiation for the preservation of food have been removed. This opens wide perspectives for the augmentation of the quantity of food available for consumption. This also offers great possibilities for less-developed countries with an agricultural economy to export products to the developed countries. Two obstacles to the internationalization of trade in irradiated food remain, however. Only if these last obstacles are removed will food irradiation be able to play an important role. The first obstacle is that no simple test exists to determine whether a food item has been irradiated and with what dose. The second obstacle is the public acceptance of irradiated food, as the public is highly sensitive to imagined or real dangers associated with the word radiation. Ways are suggested for overcoming both obstacles, stressing the importance of international cooperation and international organizations such as the IAEA, FAO and WHO. (author)

Regulations on consume and commercialization of food irradiation in Mexico

International Nuclear Information System (INIS)

Ramirez, M.E.B.; Perez, J.J.

1995-01-01

A Mexican standard for food irradiation is ready for final publication after the authority received and reviewed public comments of the project published in April 1994. The standard establish the radiation doses for different classes of food, based on ICGFI recommendations. Also included are controls for sampling, packaging, labelling, transportation, process inspection and accordance with international regulations. The results of the economical analysis of cost-benefit of the application of the standard show that the net present value is positive. The method of calculation is presented explaining the assumptions considered for the estimation of the total annual savings and surveillance costs. A final version of the research program report on radiation quarantine treatment of Mexican mangoes will be used for the petition to APHIS for the amendment of quarantine procedures to permit importation into the USA of irradiated products. (Author)