Back end of the fuel cycle

International Nuclear Information System (INIS)

Wolfe, B.; Lambert, R.W.

1975-01-01

At present, that portion of the nuclear fuel cycle involving reprocessing, waste management, and mixed-oxide fuel fabrication is in an unsettled state. Government regulatory requirements with respect to all aspects of the back end of the fuel cycle are still being formulated, and there is little positive experience on the operation of commercial reprocessing or mixed-oxide fabrication plants. In view of this unsettled situation, it will be difficult to meet the reprocessing and mixed-oxide fabrication needs of the next decade in the pattern previously anticipated. The costs in the back end of the fuel cycle are much higher than had been anticipated several years ago, a situation similar to that of almost all large endeavors in this country. On the other hand, the added costs are small relative to total power costs and do not affect the economic advantage of nuclear power as compared to other power sources. A rough economic analysis indicates that the question for the back end of the fuel cycle has changed from one of optimizing profitability to one of determining the most economic disposition of spent fuel. Long-term spent fuel storage is a practical and economically acceptable way to provide time for determining a sound course of action for the back end of the fuel cycle. Indeed, if one could count on a breeder economy before the end of the century, one possible course of action is to store light-water fuel until the plutonium can be used in breeders. However, for philosophical as well as practical reasons, it is important that the uncertainties in the course of action should be resolved as quickly as possible. Long-term storage should not be an excuse to delay resolution of the basic questions. (U.S.)

Treatment of the off-gas stream from the HTR reprocessing head-end

International Nuclear Information System (INIS)

Barnert-Wiemer, H.; Juergens, B.; Vijgen, H.

1985-01-01

The AKUT II-facility (nominal throughput 10 m 3 /h, STP) for the clean-up of the burner off-gas has been operated for 20 cold runs in parallel to the JUPITER reprocessing head-end. Two of these runs were continuous operation tests with a duration of 50 and 80 hours, respectively. The facility met or exceeded all design specifications. In a further test series the distillation column alone was run with pure CO 2 and two- and three-component gas mixtures to determine the flooding curves and the stage height (HETP)

Materials reliability in the back end of the nuclear fuel cycle

International Nuclear Information System (INIS)

1987-05-01

Operating experience of nuclear fuel cycle facilities has proved that the performance and availability of key equipment largely depend on the reliability of its construction materials. In general, the materials of construction have performed well in accordance with the design criteria of equipment. In some cases, however, materials failure problems have been encountered, the causes of which are related to their corrosion and mechanical degradation. In response to the growing interest in these topics, the IAEA convened the Technical Committee Meeting on ''Materials Reliability in the Back-End of the Nuclear Fuel Cycle'' at its Headquarters from September 2 to 5, 1986. This Technical Document contains the 15 papers presented during the Meeting. Material aspects of the following fields of the back-end of the nuclear fuel cycle are covered: interim and long-term storage of spent fuel; final disposal of spent fuel; storage and vitrification of High Level Liquid Wastes (HLLW); long-term storage of High Level Wastes (HLW); and spent fuel treatment

Plugger guide for aligning an end plug and a fuel rod tube end

International Nuclear Information System (INIS)

Klapper, K.K.; Boatwright, D.A.

1987-01-01

A pin driving tool is described for inserting or removing pins from teeth on a digging means, comprising: fuel rod tube toward an end plug for application of the end plug into the tube end, the apparatus comprising: (a) a guide housing having an elongated central longitudinal bore with one end for receiving the end plug and an opposite end for receiving the fuel rod tube end; (b) sets of rolling elements disposed in the housing at axially spaced positions along and about the bore thereof. The rolling elements in each set are positioned in fixed relation with respect to one another to receive the fuel rod tube end therebetween and align the tube end with the end plug as the tube end is moved through the bore and into engagement with the end plug; and (c) retaining means disposed adjacent to the open end of the housing bore for engaging the end plug so as to maintain it in a stationary seated position at the one end of the housing bore

Mechanical splicing of superelastic Cu–Al–Mn alloy bars with headed ends

Science.gov (United States)

Kise, S.; Mohebbi, A.; Saiidi, M. S.; Omori, T.; Kainuma, R.; Shrestha, K. C.; Araki, Y.

2018-06-01

This paper examines the feasibility of mechanical splicing using a steel coupler to connect headed ends of superelastic Cu–Al–Mn alloy (Camalloy) bars and steel reinforcing bars to be used in concrete structures. Although threading of Camalloy is as easy as that of steel, mechanical splicing using threaded ends requires machining of Camalloy bars into dog-bone shape to avoid brittle fracture at the threaded ends. The machining process requires significant time and cost and wastes substantial amount of the material. This paper attempts to resolve this issue by applying mechanical splicing using steel couplers to connect headed ends of Camalloy and steel reinforcing bars. To study its feasibility, we prepare 3 specimens wherein both ends of each Camalloy bar (13 mm diameter and 300 mm length) are connected to steel reinforcing bars. The specimens are tested under monotonic, single-cycle, and full-cycle tension loading conditions. From these tests, we observed (1) excellent superelasticity with recoverable strain of around 6% and (2) large ductility with fracture strain of over 19%. It should be emphasized here that, in all the specimens, ductile fracture occurred at the locations apart from the headed ends. This is in sharp contrast with brittle fracture of headed superelastic Ni–Ti SMA bars, most of which took place around the headed ends. From the results of the microstructural analysis, we identified the following reasons for avoiding brittle fracture at the headed ends: (1) Precipitation hardening increases the strength around the boundary between the straight and headed (tapered) portions, where stress concentration takes place. (2) The strength of the straight portion does not increase significantly up to the ductile fracture if its grain orientation is close to 〈0 0 1〉.

Apparatus and method for applying an end plug to a fuel rod tube end

International Nuclear Information System (INIS)

Rieben, S.L.; Wylie, M.E.

1987-01-01

An apparatus is described for applying an end plug to a hollow end of a nuclear fuel rod tube, comprising: support means mounted for reciprocal movement between remote and adjacent positions relative to a nuclear fuel rod tube end to which an end plug is to be applied; guide means supported on the support means for movement; and drive means coupled to the support means and being actuatable for movement between retracted and extended positions for reciprocally moving the support means between its respective remote and adjacent positions. A method for applying an end plug to a hollow end of a nuclear fuel rod tube is also described

Status of the back-end optional advanced research reactor fuel development in Korea

International Nuclear Information System (INIS)

Kim, Chang-Kyu; Lee, Yoon-Sang; Lee, Don-Bae; Oh, Seuk-Jin; Kim, Ki-Hwan; Chae, Hee-Taek; Park, Jong-Man; Sohn Dong-Seong

2003-01-01

U-Mo fuel development has been carried out for a reactor upgrade of HANARO and the back-end option in Korea. The 2nd irradiation test of the U-Mo dispersion rod fuels is underway in HANARO in order to find the optimum uranium loading density and to investigate the applicability of the monolithic U-Mo ring fuel as well as other parameters such as particle size and cladding surface-treatment. The optical observation using an immersion camera showed that the cladding surfaces of the two U 3 Si and U-Mo fuels with a high power rate changed in to the darker color, which is not as severe as those of the driving fuels in HANARO. Presumably it would be acceptable. The other fuels were observed as maintaining their initial good conditions. In connection with monolithic U-Mo fuel development, some achievements such as preliminary U-Mo tube production by a continuous casting process and a successful U-Mo foil production using a roll casting process have been obtained. In addition, some investigation on the surface-treatment of multilayer coating and Zr sputtering coating has showed the possibility of eliminating the problem of a temperature rise due to the corrosion layer formation having quite a low conductivity. The next irradiation test will aim mainly at the qualification of the U-Mo dispersion fuel for HANARO around the end of next year. In the 3rd irradiation fuel bundle, some fuels related to the basic investigation tests for the monolithic U-Mo fuel and surface-treatment for anticorrosion will be loaded. (author)

An anthropomorphic multimodality (CT/MRI) head phantom prototype for end-to-end tests in ion radiotherapy

Energy Technology Data Exchange (ETDEWEB)

Gallas, Raya R.; Huenemohr, Nora; Runz, Armin; Niebuhr, Nina I.; Greilich, Steffen [German Cancer Research Center (DKFZ), Heidelberg (Germany). Div. of Medical Physics in Radiation Oncology; National Center for Radiation Research in Oncology, Heidelberg (Germany). Heidelberg Institute of Radiation Oncology (HIRO); Jaekel, Oliver [German Cancer Research Center (DKFZ), Heidelberg (Germany). Div. of Medical Physics in Radiation Oncology; National Center for Radiation Research in Oncology, Heidelberg (Germany). Heidelberg Institute of Radiation Oncology (HIRO); Heidelberg University Hospital (Germany). Dept. of Radiation Oncology; Heidelberg Ion-Beam Therapy Center (HIT), Heidelberg (Germany)

2015-07-01

With the increasing complexity of external beam therapy ''end-to-end'' tests are intended to cover every step from therapy planning through to follow-up in order to fulfill the higher demands on quality assurance. As magnetic resonance imaging (MRI) has become an important part of the treatment process, established phantoms such as the Alderson head cannot fully be used for those tests and novel phantoms have to be developed. Here, we present a feasibility study of a customizable multimodality head phantom. It is initially intended for ion radiotherapy but may also be used in photon therapy. As basis for the anthropomorphic head shape we have used a set of patient computed tomography (CT) images. The phantom recipient consisting of epoxy resin was produced by using a 3D printer. It includes a nasal air cavity, a cranial bone surrogate (based on dipotassium phosphate), a brain surrogate (based on agarose gel), and a surrogate for cerebrospinal fluid (based on distilled water). Furthermore, a volume filled with normoxic dosimetric gel mimicked a tumor. The entire workflow of a proton therapy could be successfully applied to the phantom. CT measurements revealed CT numbers agreeing with reference values for all surrogates in the range from 2 HU to 978 HU (120 kV). MRI showed the desired contrasts between the different phantom materials especially in T2-weighted images (except for the bone surrogate). T2-weighted readout of the polymerization gel dosimeter allowed approximate range verification.

An anthropomorphic multimodality (CT/MRI) head phantom prototype for end-to-end tests in ion radiotherapy

International Nuclear Information System (INIS)

Gallas, Raya R.; Huenemohr, Nora; Runz, Armin; Niebuhr, Nina I.; Greilich, Steffen; Jaekel, Oliver

2015-01-01

With the increasing complexity of external beam therapy ''end-to-end'' tests are intended to cover every step from therapy planning through to follow-up in order to fulfill the higher demands on quality assurance. As magnetic resonance imaging (MRI) has become an important part of the treatment process, established phantoms such as the Alderson head cannot fully be used for those tests and novel phantoms have to be developed. Here, we present a feasibility study of a customizable multimodality head phantom. It is initially intended for ion radiotherapy but may also be used in photon therapy. As basis for the anthropomorphic head shape we have used a set of patient computed tomography (CT) images. The phantom recipient consisting of epoxy resin was produced by using a 3D printer. It includes a nasal air cavity, a cranial bone surrogate (based on dipotassium phosphate), a brain surrogate (based on agarose gel), and a surrogate for cerebrospinal fluid (based on distilled water). Furthermore, a volume filled with normoxic dosimetric gel mimicked a tumor. The entire workflow of a proton therapy could be successfully applied to the phantom. CT measurements revealed CT numbers agreeing with reference values for all surrogates in the range from 2 HU to 978 HU (120 kV). MRI showed the desired contrasts between the different phantom materials especially in T2-weighted images (except for the bone surrogate). T2-weighted readout of the polymerization gel dosimeter allowed approximate range verification.

An anthropomorphic multimodality (CT/MRI) head phantom prototype for end-to-end tests in ion radiotherapy.

Science.gov (United States)

Gallas, Raya R; Hünemohr, Nora; Runz, Armin; Niebuhr, Nina I; Jäkel, Oliver; Greilich, Steffen

2015-12-01

With the increasing complexity of external beam therapy "end-to-end" tests are intended to cover every step from therapy planning through to follow-up in order to fulfill the higher demands on quality assurance. As magnetic resonance imaging (MRI) has become an important part of the treatment process, established phantoms such as the Alderson head cannot fully be used for those tests and novel phantoms have to be developed. Here, we present a feasibility study of a customizable multimodality head phantom. It is initially intended for ion radiotherapy but may also be used in photon therapy. As basis for the anthropomorphic head shape we have used a set of patient computed tomography (CT) images. The phantom recipient consisting of epoxy resin was produced by using a 3D printer. It includes a nasal air cavity, a cranial bone surrogate (based on dipotassium phosphate), a brain surrogate (based on agarose gel), and a surrogate for cerebrospinal fluid (based on distilled water). Furthermore, a volume filled with normoxic dosimetric gel mimicked a tumor. The entire workflow of a proton therapy could be successfully applied to the phantom. CT measurements revealed CT numbers agreeing with reference values for all surrogates in the range from 2 HU to 978 HU (120 kV). MRI showed the desired contrasts between the different phantom materials especially in T2-weighted images (except for the bone surrogate). T2-weighted readout of the polymerization gel dosimeter allowed approximate range verification. Copyright © 2015. Published by Elsevier GmbH.

TRISO-coated spent fuel processing using a Grind-Leach head-end

International Nuclear Information System (INIS)

Spencer, Barry B.; Del Cul, Guillermo D.; Mattus, Catherine H.; Collins, Emory D.

2005-01-01

Processing of TRISO-coated HTGR fuels with the grind-leach process requires that the fuel be finely pulverized for efficient and effective acid dissolution of the fuel components. Mechanical size reduction of the fuel is being investigated with jet mill technology as the final milling step. Laboratory experiments were performed with surrogates of crushed fuel compacts that indicate that milling to very small particle sizes is feasible. The size distribution of the milled product is sensitive to the solids feed rate, and the distribution may be bimodal which could support an effective solid-solid separation. (author)

Low hydrostatic head electrolyte addition to fuel cell stacks

International Nuclear Information System (INIS)

Kothmann, R.E.

1983-01-01

A fuel cell and system for supply electrolyte, as well as fuel and an oxidant to a fuel cell stack having at least two fuel cells, each of the cells having a pair of spaced electrodes and a matrix sandwiched therebetween, fuel and oxidant paths associated with a bipolar plate separating each pair of adjacent fuel cells and an electrolyte fill path for adding electrolyte to the cells and wetting said matrices. Electrolyte is flowed through the fuel cell stack in a back and forth fashion in a path in each cell substantially parallel to one face of opposite faces of the bipolar plate exposed to one of the electrodes and the matrices to produce an overall head uniformly between cells due to frictional pressure drop in the path for each cell free of a large hydrostatic head to thereby avoid flooding of the electrodes. The bipolar plate is provided with channels forming paths for the flow of the fuel and oxidant on opposite faces thereof, and the fuel and the oxidant are flowed along a first side of the bipolar plate and a second side of the bipolar plate through channels formed into the opposite faces of the bipolar plate, the fuel flowing through channels formed into one of the opposite faces and the oxidant flowing through channels formed into the other of the opposite faces

Development of remote fuel pushing system in Reprocessing Plant, Tarapur

International Nuclear Information System (INIS)

Chandra, Munish; Coelho, G.; Kodilkar, S.S.; Mishra, A.K.; Bajpai, D.D.; Nair, M.K.T.

1990-01-01

Power Reactor Fuel Reprocessing Plant (PREFRE), Tarapur has been processing spent fuel arising from Pressurized Heavy Water Reactors for quite some time. The process adopted in the plant is purex process with chopleach head end treatment. The head end treatment involves loading of ten spent fuel bundles in the charging cask at a time in the fuel bay and aligning the cask with the transfer port and subsequently pushing all the ten bundles together into the fuel magazine. At present the fuel is pushed into the magazine manually. Since the ten bundles weigh approximately 200 Kg. and involves pushing of 9.4 meters length, the operation is carried out using stainless steel screwed pipes, in steps of five lengths. The entire operation requires a large number of trained skilled workers and is found to be tedious. To solve this problem a hydraulic cum pneumatic fuel pushing system has been designed, fabricated, tested and is in the process of installation in the fuel handling area. This paper describes various requirements, constraints and dimensional details arising in the incorporation of such a system to be back fitted in an existing plant, though many of these constraints can be avoided in future plants. Further, complete sequence of operations, technical specifications regarding the telescopic hydraulic power pack and associated controls incorporated in the system are highlighted. (author). 2 figs

Nuclear fuel rod end plug weld inspection

International Nuclear Information System (INIS)

Parker, M. A.; Patrick, S. S.; Rice, G. F.

1985-01-01

Apparatus and method for testing TIG (tungsten inert gas) welds of end plugs on a sealed nuclear reactor fuel rod. An X-ray fluorescent spectrograph testing unit detects tungsten inclusion weld defects in the top end plug's seal weld. Separate ultrasonic weld inspection system testing units test the top end plug's seal and girth welds and test the bottom end plug's girth weld for penetration, porosity and wall thinning defects. The nuclear fuel rod is automatically moved into and out from each testing unit and is automatically transported between the testing units by rod handling devices. A controller supervises the operation of the testing units and the rod handling devices

Research and development of FBR fuel reprocessing in PNC

International Nuclear Information System (INIS)

Hoshino, T.

1976-05-01

The research program of the PNC for FBR fuel reprocessing in Japan is discussed. The general characteristics of FBR fuel reprocessing are pointed out and a comparison with LWR fuel is made. The R and D program is based on reprocessing using the aqueous Purex process. So far, some preliminary steps of the research program have been carried out, these include solvent extraction test, off-gas treatment test, voloxidation process study, solidification test of high-level liquid waste, and study of the dissolution behaviour of irradiated mixed oxide fuel. By the end of the 1980s, a pilot plant for FBR fuel reprocessing will be completed. For the design of the pilot plant, further research will be carried out in the following fields: head-end techniques; voloxidation process; dissolution and extraction techniques; waste treatment techniques. A time schedule for the different steps of the program is included

Head-end process technology for the new reprocessing plants in France and Japan

International Nuclear Information System (INIS)

Saudray, D.; Hugelmann, D.; Cho, A.

1991-01-01

Major technological innovations brought to the new UP3 and UP2-800 reprocessing plants of COGEMA LA HAGUE and also to the JNFS ROKKASHO plant concern the head-end process. The continuous process designed allows for high throughputs whilst meeting stringent safety requirements. The head-end of each plant includes two lines for each operation in order to guarantee availability. This paper presents the T1 head-end facility of the UP3 plant as well as the few adaptations implemented in the ROKKASHO Reprocessing Plant to fulfill the particular design requirements in Japan

Remote handling and automation in back end of fuel cycle

International Nuclear Information System (INIS)

Nair, K.N.S.

2010-01-01

Full text: Indian nuclear programme is readying for a quantum leap and it is essential that technology is available for building advanced fuel recycle plants in the back end and for sustained operation of such plants. Remote technology and automation plays a big role to achieve this goal. With the introduction of advanced fuel cycles in indigenous programme and scenario of international cooperation it is essential to be ready with indigenous technology for meeting all challenges. Work has been progressing to develop locally support technology for remote handling and automation with good success. Essential RH tools such as master slave manipulators, power manipulators and hot cell viewing systems have been developed and commercial production has been established. Customised RH requirements for back end plants have been met and the designs have proven to be worthy for hot operations over the years. In the last few years stress has been on development of equipment and technology to meet the increasing demands of higher throughput plants. Substantial progress has been achieved in the head end and reconversion laboratory systems of reprocessing plants. Similarly successful efforts have also been made for establishing Thoria processing cells and also the RH in the reconversion operations. Custom designed equipment has been developed for decommissioning of ceramic melter, used glove boxes etc. Efforts are on hand to develop automated RH equipment for material handling in underground repositories. This paper aims at bringing out the theme based on some of our own experiences and some reports from plants in operation abroad. (author)

MTR spent fuel back-end - Cogema's long-term commitment

International Nuclear Information System (INIS)

Thomasson, J.

1998-01-01

MTR spent fuel back end has been subject to many reversal and uncertainties in the past 10 years. Until the end of 1988, US obligated materials were subject to the Off site Fuels Policy (OFP). Under this policy, spent fuels were returned to USA, and were reprocessed there. This OFP took end the 31th of December 1988, and Research Reactor's operators had to implement others solutions: On site storage or Reprocessing in Europe. Meanwhile the RERTR Program was leading to a new LEU fuel to replace HEU aluminide. This new silicide fuel has one main drawback: it cannot be reprocessed in working plants without some process main line modifications. Fortunately, a new Research Reactors spent fuels return policy has been set up by the US in the early 1996. This new policy applies to all reactors converted or that have agreed to convert to LEU, and reactors operating with HEU for which no suitable LEU is available. It covers all the spent fuels discharged until 2006/05/12. But after that period of time, each reactor will be fully responsible for its spent fuels. Since the end of 1996, COGEMA is proposing reprocessing services for Aluminides spent fuels, based on the La Hague capability. This COGEMA answer is for the long term, as the La Hague plant has a good load for the coming years, including the first decade of the next century. Further, this activity benefits from a strong R and D support, that allowed fulfilling the evolutive needs of our customers, and gives us the ability to adapt the plant to the future market. Taking advantage of this flexibility, COGEMA offers Research Reactors' operators a long-term commitment. Already two reactors' operators have chosen to contract with COGEMA for the whole life of their reactors. The contracts execution is under progress and the first transportation will take place soon. Beside today's services, COGEMA is involved in R and D activities to support new fuels development enhancing present LEU performances and having the ability to

Back-end of the nuclear fuel cycle

International Nuclear Information System (INIS)

Choi, J.S.

2002-01-01

Current strategies of the back-end nuclear fuel cycles are: (1) direct-disposal of spent fuel (Open Cycle), and (2) reprocessing of the spent fuel and recycling of the recovered nuclear materials (Closed Cycle). The selection of these strategies is country-specific, and factors affecting selection of strategy are identified and discussed in this paper. (author)

Fuel handling system of nuclear reactor plants

International Nuclear Information System (INIS)

Faulstich, D.L.

1991-01-01

This patent describes a fuel handing system for nuclear reactor plants comprising a reactor vessel having an openable top and removable cover for refueling and containing therein, submerged in coolant water substantially filling the reactor vessel, a fuel core including a multiplicity of fuel bundles formed of groups of sealed tube elements enclosing fissionable fuel assembled into units. It comprises a fuel bundle handing platform moveable over the open top of the reactor vessel; a fuel bundle handing mast extendable downward from the platform with a lower end projecting into the open top reactor vessel to the fuel core submerged in water; a grapple head mounted on the lower end of the mast provided with grappling hook means for attaching to and transporting fuel bundles into and out from the fuel core; and a camera with a prismatic viewing head surrounded by a radioactive resisting quartz cylinder and enclosed within the grapple head which is provided with at least three windows with at least two windows provided with an angled surface for aiming the camera prismatic viewing head in different directions and thereby viewing the fuel bundles of the fuel core from different perspectives, and having a cable connecting the camera with a viewing monitor located above the reactor vessel for observing the fuel bundles of the fuel core and for enabling aiming of the camera prismatic viewing head through the windows by an operator

Fuel cell end plate structure

Science.gov (United States)

Guthrie, Robin J.; Katz, Murray; Schroll, Craig R.

1991-04-23

The end plates (16) of a fuel cell stack (12) are formed of a thin membrane. Pressure plates (20) exert compressive load through insulation layers (22, 26) to the membrane. Electrical contact between the end plates (16) and electrodes (50, 58) is maintained without deleterious making and breaking of electrical contacts during thermal transients. The thin end plate (16) under compressive load will not distort with a temperature difference across its thickness. Pressure plate (20) experiences a low thermal transient because it is insulated from the cell. The impact on the end plate of any slight deflection created in the pressure plate by temperature difference is minimized by the resilient pressure pad, in the form of insulation, therebetween.

End-stage head and neck cancer coping mechanisms

Directory of Open Access Journals (Sweden)

Bogdan Popescu

2017-10-01

Full Text Available Coping mechanisms are patients’ means of adapting to stressful situations and involve psychological and physical changes in behavior. Patients adapt to head and neck cancer in a variety of ways. Head and neck cancers are extremely debilitating, especially in advanced stages of the disease or in end-of-life situations. While an oncology team needs to address the needs of all oncology patients, the advanced terminal patients require special attention. Most of these patients do not cope well with their situation and have a tendency to cease social interactions. Pain is the most frequentlyexperienced medical disability in patients having an end-stage illness experience, and thus an important medical endeavor is to afford dignity to the dying patient facingan incurable disease. In such cases, the medical community should never refuse therapy or to assist a dying patient.In some instances, the patient and family may derive benefit from their religious beliefs.

Monolithic fuel injector and related manufacturing method

Science.gov (United States)

Ziminsky, Willy Steve [Greenville, SC; Johnson, Thomas Edward [Greenville, SC; Lacy, Benjamin [Greenville, SC; York, William David [Greenville, SC; Stevenson, Christian Xavier [Greenville, SC

2012-05-22

A monolithic fuel injection head for a fuel nozzle includes a substantially hollow vesicle body formed with an upstream end face, a downstream end face and a peripheral wall extending therebetween, an internal baffle plate extending radially outwardly from a downstream end of the bore, terminating short of the peripheral wall, thereby defining upstream and downstream fuel plenums in the vesicle body, in fluid communication by way of a radial gap between the baffle plate and the peripheral wall. A plurality of integral pre-mix tubes extend axially through the upstream and downstream fuel plenums in the vesicle body and through the baffle plate, with at least one fuel injection hole extending between each of the pre-mix tubes and the upstream fuel plenum, thereby enabling fuel in the upstream plenum to be injected into the plurality of pre-mix tubes. The fuel injection head is formed by direct metal laser sintering.

Back end of the nuclear fuel cycle

International Nuclear Information System (INIS)

Shapar, H.K.

1986-01-01

Most of the nuclear spent fuel that is discharged from the reactors in OECD countries is destined currently for long term interim storage before final processing or direct disposal. There are at least three basic considerations affecting the dicision on spent fuel, that is, the capacity of prompt reprocessing is insufficient at present, reprocessing is not urgent for the reason of economy or plutonium availability, and the cooling of spent fuel in controlled storage is economically advantageous. The basic technology of reprocessing has been commercially available for several decades, but political problems and the lack of immediate incentive for reprocessing slowed the buildup of new capacity. To avoid the problems related to plutonium storage, it is reasonable to postpone reprocessing. Some OECD countries plan the direct disposal of spent fuel elements instead of reprocessing. The technology, supply and demand and cost of the storage and transport of spent fuel, reprocessing and waste disposal are discussed. The share of the back end in the total levelized fuel cycle cost is expected to be between 10 and 20 %. The impact of the choice of back end options on the cost of power generation will be only 2 %. (Kako, I.)

End plug welding of nuclear fuel elements-AFFF experience

International Nuclear Information System (INIS)

Bhatt, R.B.; Singh, S.; Aniruddha Kumar; Amit; Arun Kumar; Panakkal, J.P.; Kamath, H.S.

2004-01-01

Advanced Fuel Fabrication Facility is engaged in the fabrication of mixed oxide (U,Pu)O 2 fuel elements of various types of nuclear reactors. Fabrication of fuel elements involves pellet fabrication, stack making, stack loading and end plug welding. The requirement of helium bonding gas inside the fuel elements necessitates the top end plug welding to be carried out with helium as the shielding gas. The severity of the service conditions inside a nuclear reactor imposes strict quality control criteria, which demands for almost defect free welds. The top end plug welding being the last process step in fuel element fabrication, any rejection at this stage would lead to loss of effort prior to this step. Moreover, the job becomes all the more difficult with mixed oxide (MOX) as the entire fabrication work has to be carried out in glove box trains. In the case of weld rejection, accepted pellets are salvaged by cutting the clad tube. This is a difficult task and recovery of pellets is low (requiring scrap recovery operation) and also leads to active metallic waste generation. This paper discusses the experience gained at AFFF, in the past 12 years in the area of end plug welding for different types of MOX fuel elements

Use of curium neutron flux from head-end pyroprocessing subsystems for the High Reliability Safeguards methodology

Energy Technology Data Exchange (ETDEWEB)

Borrelli, R.A., E-mail: r.angelo.borrelli@gmail.com

2014-10-01

The deployment of nuclear energy systems (NESs) is expanding around the world. Nations are investing in NESs as a means to establish energy independence, grow national economies, and address climate change. Transitioning to the advanced nuclear fuel cycle can meet growing energy demands and ensure resource sustainability. However, nuclear facilities in all phases of the advanced fuel cycle must be ‘safeguardable,’ where safety, safeguards, and security are integrated into a practical design strategy. To this end, the High Reliability Safeguards (HRS) approach is a continually developing safeguardability methodology that applies intrinsic design features and employs a risk-informed approach for systems assessment that is safeguards-motivated. Currently, a commercial pyroprocessing facility is used as the example system. This paper presents a modeling study that investigates the neutron flux associated with processed materials. The intent of these studies is to determine if the neutron flux will affect facility design, and subsequently, safeguardability. The results presented in this paper are for the head-end subsystems in a pyroprocessing facility. The collective results from these studies will then be used to further develop the HRS methodology.

Head and Neck Cancer Treatment

Science.gov (United States)

... Professions Site Index A-Z Head and Neck Cancer Treatment Head and neck cancer overview What are my ... and neck cancer. For updated information on new cancer treatments that are available, you should discuss these issues ...

Reprocessing of ''fast'' fuel in France

International Nuclear Information System (INIS)

Sauteron, J.; Bourgeois, M.; Le Bouhellec, J.; Miquel, P.

1976-05-01

The results of laboratory studies as well as pilot testing (AT-I La Hague, Marcoule, Fontenay-aux-Roses) in reprocessing of fast breeder reactor fuels are described. The paper covers all steps: head end, aqueous and fluoride volatility processes, and waste treatment. In conclusion, it is demonstrated why it is still too early to define a strategy of industrial reprocessing for this reactor type

Verification of the Barnwell Nuclear Fuel Plant (BNFP) mechanical headend design

International Nuclear Information System (INIS)

Townes, G.A.

1978-11-01

Design of the Barnwell Nuclear Fuel Plant mechanical head end includes unique provisions for remote maintenance, minimizes remote handling, and permits high throughput (6 MTU of spent fuel per day). Operability studies have been performed under a contract with the Department of Energy that: (1) assessed its capabilities for possible use in fuel encapsulation with or without compaction as a preparation for spent fuel storage, (2) verified the design of the mechanical head end as remotely maintainable, and (3) provided operator training

Determining plasma-fueling sources with an end-loss ion spectrometer

International Nuclear Information System (INIS)

Grubb, D.P.; Foote, J.H.

1986-01-01

To help identify the major sources of fueling gas in Tandem Mirror Experiment-Upgrade (TMX-U), we mounted a mass-sensitive, E parallel to B, end-loss ion spectrometer (ELIS) near the machine's centerline. We set the electric field in the ELIS to simultaneously measure the axial loss currents of both hydrogen and deuterium. We then initiated plasma discharges, where we injected either hydrogen or deuterium gas into the central cell. We also selected and deselected the central-cell neutral beams that were fueled with hydrogen gas. The end-cell neutral beams were always selected and fueled with deuterium. By taking the ratio of the hydrogen end-loss current to the deuterium end-loss current (with a known deuterium-gas feed rate), we were able to infer the effective fueling rates that were due to wall reflux, central-cell beams, and end-cell beams. The results were the following: wall reflux, 6 Torr.l/s; central-cell beams, 15 Torr.l/s; and end-cell beams 1 Torr.l/s. 3 refs., 3 figs., 1 tab

Nuclear fuel cycle head-end enriched uranium purification and conversion into metal

International Nuclear Information System (INIS)

Bonini, A.; Cabrejas, J.; Lio, L. de; Dell'Occhio, L.; Devida, C.; Dupetit, G.; Falcon, M.; Gauna, A.; Gil, D.; Guzman, G.; Neuringer, P.; Pascale, A.; Stankevicius, A.

1998-01-01

The CNEA (Comision Nacional de Energia Atomica - Argentina) operated two facilities at the Ezeiza Atomic Center which supply purified enriched uranium employed in the production of nuclear fuels. At one of those facilities, the Triple Height Laboratory scraps from the production of MTR type fuel elements (mainly out of specification U 3 O 8 plates or powder) are purified to nuclear grade. The purification is accomplished by a solvent extraction process. The other facility, the Enriched Uranium Laboratory produces 90% enriched uranium metal to be used in Mo 99 production (originally the uranium was used for the manufacture of MTR fuel elements made of aluminium-uranium alloy). This laboratory also provided metallic uranium with a lower enrichment (20%) for a first uranium-silicon testing fuel element, and in the near future it is going to recommence 20% enriched uranium related activities in order to provide the metal for the silicon-based fuel elements production (according to the policy of enrichment reduction for MTR reactors). (author)

Welding nuclear reactor fuel rod end plugs

International Nuclear Information System (INIS)

Yeo, D.

1984-01-01

Apparatus for applying a vacuum to a nuclear fuel rod cladding tube's interior through its open end while girth welding an inserted end plug to its other end. An airtight housing has an orifice with a seal which can hermetically engage the tube's open end. A vacuum hose has one end connected to the housing and the other end connected to a vacuum pump. A mechanized device which moves the housing to engage or disengage its seal with the tube's open end includes at least one arm having one end attached to the housing and the other end pivotally attached to a movable table; an arm rotating device to coaxially align the housing's orifice with the welding-positioned tube; and a table moving device to engage the seal of the coaxially aligned orifice with the tube's open end. (author)

Selective Trapping of Volatile Fission Products with an Off-Gas Treatment System

Energy Technology Data Exchange (ETDEWEB)

B.R. Westphal; J.J. Park; J.M. Shin; G.I. Park; K.J. Bateman; D.L. Wahlquist

2008-07-01

A head-end processing step, termed DEOX for its emphasis on decladding via oxidation, is being developed for the treatment of spent oxide fuel by pyroprocessing techniques. The head-end step employs high temperatures to oxidize UO2 to U3O8 resulting in the separation of fuel from cladding and the removal of volatile fission products. Development of the head-end step is being performed in collaboration with the Korean Atomic Energy Research Institute (KAERI) through an International Nuclear Energy Research Initiative. Following the initial experimentation for the removal of volatile fission products, an off-gas treatment system was designed in conjunction with KAERI to collect specific fission gases. The primary volatile species targeted for trapping were iodine, technetium, and cesium. Each species is intended to be collected in distinct zones of the off-gas system and within those zones, on individual filters. Separation of the volatile off-gases is achieved thermally as well as chemically given the composition of the filter media. A description of the filter media and a basis for its selection will be given along with the collection mechanisms and design considerations. In addition, results from testing with the off-gas treatment system will be presented.

Status of reprocessing technology in the HTGR fuel cycle

International Nuclear Information System (INIS)

Kaiser, G.; Merz, E.; Zimmer, E.

1977-01-01

For more than ten years extensive R and D work has been carried out in the Federal Republic of Germany in order to develop the technology necessary for closing the fuel cycle of high-temperature gas-cooled reactors. The efforts are concentrated primarily on fuel elements having either highly enriched 235 U or recycled 233 U as the fissile and thorium as the fertile material embedded in a graphite matrix. They include the development of processes and equipment for reprocessing and remote preparation of coated microspheres from the recovered uranium. The paper reviews the issues and problems associated with the requirements to deal with high burn-up fuel from HTGR's of different design and composition. It is anticipated that a grind-burn-leach head-end treatment and a modified THOREX-type chemical processing are the optimum choice for the flowsheet. An overview of the present status achieved in construction of a small reprocessing facility, called JUPITER, is presented. It includes a discussion of problems which have already been solved and which have still to be solved like the treatment of feed/breed particle systems and for minimizing environmental impacts envisaged with a HTGR fuel cycle technology. Also discussed is the present status of remote fuel kernel fabrication and coating technology. Additional activities include the design of a mock-up prototype burning head-end facility, called VENUS, with a throughput equivalent to about 6000 MW installed electrical power, as well as a preliminary study for the utilisation of the Karlsruhe LWR prototype reprocessing plant (WAK) to handle HTGR fuel after remodelling of the installations. The paper concludes with an outlook of projects for the future

Fuel assembly

International Nuclear Information System (INIS)

Abe, Hideaki; Sakai, Takao; Ishida, Tomio; Yokota, Norikatsu.

1992-01-01

The lower ends of a plurality of plate-like shape memory alloys are secured at the periphery of the upper inside of the handling head of a fuel assembly. As the shape memory alloy, a Cu-Zn alloy, a Ti-Pd alloy or a Fe-Ni alloy is used. When high temperature coolants flow out to the handling head, the shape memory alloy deforms by warping to the outer side more greatly toward the upper portion thereof with the temperature increase of the coolants. As the result, the shape of the flow channel of the coolants is changed so as to enlarge at the exit of the upper end of the fuel assembly. Then, the pressure loss of the coolants in the fuel assembly is decreased by the enlargement. Accordingly, the flow rate of the coolants in the fuel assembly is increased to lower the temperature of the coolants. Further, high temperature coolants and low temperature coolants are mixed sufficiently just above the fuel assembly. This can suppress the temperature fluctuation of the mixed coolants in the upper portion of the reactor core, thereby enabling to decrease a fatigue and failures of the structural components in the upper portion of the reactor core. (I.N.)

Darlington NGD fuel handling head eight acceptance program

International Nuclear Information System (INIS)

Skelton, P.H.; Sie, T.

1996-01-01

Darlington NGD requires eight fuelling machine heads to fuel the four 932 MW reactors. Six heads are used on the three fuelling machine trolleys for normal fuelling operations. A further two heads are required to allow for maintenance and to provide for such reactor face activities as PIPE and CIGAR. Seven heads were successfully delivered to site from the head supplier. During acceptance testing, stalls on the charge tube screw assembly of the eighth and final head prevented its delivery to site. Replacement of the charge tube screw with a spare screw did not alleviate the problem. An in depth series of tests were undertaken at site, at the supplier and at the screw sub-supplier to determine the root cause of the problem. These tests included taking torque measurements under different operating conditions and using different components to assess the effects of the changes on torque levels. An assessment of the effects of changing chemical conditions (particularly crud levels) was also made. To ensure that the results of the testing were well understood, additional torque testing was also completed on a head and screw assembly at site that was known to work well. Based on all of the above series of tests, a recommendation was made to re-machine the charge tube screw(s). The original charge tube screw from Head eight was subsequently returned to the sub-supplier for re-work. Follow-up torque measurements and acceptance testing showed that the screw rework was effective and that Head eight could be successfully delivered to site. This paper focuses on the results of the head/screw test program. Results of the acceptance testing are also discussed. (author). 2 refs., 4 figs

Darlington NGD fuel handling head eight acceptance program

Energy Technology Data Exchange (ETDEWEB)

Skelton, P H; Sie, T [Ontario Hydro, Bowmanville (Canada). Darlington Nuclear Generating Station; Pilgrim, J [Canadian General Electric Co. Ltd., Toronto, ON (Canada)

1997-12-31

Darlington NGD requires eight fuelling machine heads to fuel the four 932 MW reactors. Six heads are used on the three fuelling machine trolleys for normal fuelling operations. A further two heads are required to allow for maintenance and to provide for such reactor face activities as PIPE and CIGAR. Seven heads were successfully delivered to site from the head supplier. During acceptance testing, stalls on the charge tube screw assembly of the eighth and final head prevented its delivery to site. Replacement of the charge tube screw with a spare screw did not alleviate the problem. An in depth series of tests were undertaken at site, at the supplier and at the screw sub-supplier to determine the root cause of the problem. These tests included taking torque measurements under different operating conditions and using different components to assess the effects of the changes on torque levels. An assessment of the effects of changing chemical conditions (particularly crud levels) was also made. To ensure that the results of the testing were well understood, additional torque testing was also completed on a head and screw assembly at site that was known to work well. Based on all of the above series of tests, a recommendation was made to re-machine the charge tube screw(s). The original charge tube screw from Head eight was subsequently returned to the sub-supplier for re-work. Follow-up torque measurements and acceptance testing showed that the screw rework was effective and that Head eight could be successfully delivered to site. This paper focuses on the results of the head/screw test program. Results of the acceptance testing are also discussed. (author). 2 refs., 4 figs.

MOX fuel use as a back-end option: Trends, main issues and impacts on fuel cycle management

International Nuclear Information System (INIS)

Fukuda, K.; Choi, J.-S.; Shani, R.; Durpel, L. van den; Bertel, E.; Sartori, E.

2000-01-01

In the past decades while the FBIULWR fuel cycle concept was zealously being developed, MOX-fuel use in thermal reactors was taken as an alternative back-end policy option. However, the plutonium recycling with LWRs has evolved to industrial level, gaining high maturity through the incubative period while FBR deployment was envisaged. Today, MOX-fuel use in LWRs makes integral part of the fuel cycle for those countries relying on the recycling policy. Developments to improve the fuel cycle performance, including the minimisation of remaining wastes, and the reactor engineering aspects owing to MOX-fuel use, are continued. This paper jointly presented by IAEA and OECD/NEA brings an integrated overview on MOX use as a back-end policy, covering MOX fuel utilisation, fuel performance and technology, economics, licensing, MOX fuel trends in the coming decades. (author)

SU-E-J-25: End-To-End (E2E) Testing On TomoHDA System Using a Real Pig Head for Intracranial Radiosurgery

Energy Technology Data Exchange (ETDEWEB)

Corradini, N; Leick, M; Bonetti, M; Negretti, L [Clinica Luganese, Radiotherapy Center, Lugano (Switzerland)

2015-06-15

Purpose: To determine the MVCT imaging uncertainty on the TomoHDA system for intracranial radiosurgery treatments. To determine the end-to-end (E2E) overall accuracy of the TomoHDA system for intracranial radiosurgery. Methods: A pig head was obtained from the butcher, cut coronally through the brain, and preserved in formaldehyde. The base of the head was fixed to a positioning plate allowing precise movement, i.e. translation and rotation, in all 6 axes. A repeatability test was performed on the pig head to determine uncertainty in the image bone registration algorithm. Furthermore, the test studied images with MVCT slice thicknesses of 1 and 3 mm in unison with differing scan lengths. A sensitivity test was performed to determine the registration algorithm’s ability to find the absolute position of known translations/rotations of the pig head. The algorithm’s ability to determine absolute position was compared against that of manual operators, i.e. a radiation therapist and radiation oncologist. Finally, E2E tests for intracranial radiosurgery were performed by measuring the delivered dose distributions within the pig head using Gafchromic films. Results: The repeatability test uncertainty was lowest for the MVCTs of 1-mm slice thickness, which measured less than 0.10 mm and 0.12 deg for all axes. For the sensitivity tests, the bone registration algorithm performed better than human eyes and a maximum difference of 0.3 mm and 0.4 deg was observed for the axes. E2E test results in absolute position difference measured 0.03 ± 0.21 mm in x-axis and 0.28 ± 0.18 mm in y-axis. A maximum difference of 0.32 and 0.66 mm was observed in x and y, respectively. The average peak dose difference between measured and calculated dose was 2.7 cGy or 0.4%. Conclusion: Our tests using a pig head phantom estimate the TomoHDA system to have a submillimeter overall accuracy for intracranial radiosurgery.

SU-E-J-25: End-To-End (E2E) Testing On TomoHDA System Using a Real Pig Head for Intracranial Radiosurgery

International Nuclear Information System (INIS)

Corradini, N; Leick, M; Bonetti, M; Negretti, L

2015-01-01

Purpose: To determine the MVCT imaging uncertainty on the TomoHDA system for intracranial radiosurgery treatments. To determine the end-to-end (E2E) overall accuracy of the TomoHDA system for intracranial radiosurgery. Methods: A pig head was obtained from the butcher, cut coronally through the brain, and preserved in formaldehyde. The base of the head was fixed to a positioning plate allowing precise movement, i.e. translation and rotation, in all 6 axes. A repeatability test was performed on the pig head to determine uncertainty in the image bone registration algorithm. Furthermore, the test studied images with MVCT slice thicknesses of 1 and 3 mm in unison with differing scan lengths. A sensitivity test was performed to determine the registration algorithm’s ability to find the absolute position of known translations/rotations of the pig head. The algorithm’s ability to determine absolute position was compared against that of manual operators, i.e. a radiation therapist and radiation oncologist. Finally, E2E tests for intracranial radiosurgery were performed by measuring the delivered dose distributions within the pig head using Gafchromic films. Results: The repeatability test uncertainty was lowest for the MVCTs of 1-mm slice thickness, which measured less than 0.10 mm and 0.12 deg for all axes. For the sensitivity tests, the bone registration algorithm performed better than human eyes and a maximum difference of 0.3 mm and 0.4 deg was observed for the axes. E2E test results in absolute position difference measured 0.03 ± 0.21 mm in x-axis and 0.28 ± 0.18 mm in y-axis. A maximum difference of 0.32 and 0.66 mm was observed in x and y, respectively. The average peak dose difference between measured and calculated dose was 2.7 cGy or 0.4%. Conclusion: Our tests using a pig head phantom estimate the TomoHDA system to have a submillimeter overall accuracy for intracranial radiosurgery

Adaptation and validation of a commercial head phantom for cranial radiosurgery dosimetry end-to-end audit.

Science.gov (United States)

Dimitriadis, Alexis; Palmer, Antony L; Thomas, Russell A S; Nisbet, Andrew; Clark, Catharine H

2017-06-01

To adapt and validate an anthropomorphic head phantom for use in a cranial radiosurgery audit. Two bespoke inserts were produced for the phantom: one for providing the target and organ at risk for delineation and the other for performing dose measurements. The inserts were tested to assess their positional accuracy. A basic treatment plan dose verification with an ionization chamber was performed to establish a baseline accuracy for the phantom and beam model. The phantom and inserts were then used to perform dose verification measurements of a radiosurgery plan. The dose was measured with alanine pellets, EBT extended dose film and a plastic scintillation detector (PSD). Both inserts showed reproducible positioning (±0.5 mm) and good positional agreement between them (±0.6 mm). The basic treatment plan measurements showed agreement to the treatment planning system (TPS) within 0.5%. Repeated film measurements showed consistent gamma passing rates with good agreement to the TPS. For 2%-2 mm global gamma, the mean passing rate was 96.7% and the variation in passing rates did not exceed 2.1%. The alanine pellets and PSD showed good agreement with the TPS (-0.1% and 0.3% dose difference in the target) and good agreement with each other (within 1%). The adaptations to the phantom showed acceptable accuracies. The presence of alanine and PSD do not affect film measurements significantly, enabling simultaneous measurements by all three detectors. Advances in knowledge: A novel method for thorough end-to-end test of radiosurgery, with capability to incorporate all steps of the clinical pathway in a time-efficient and reproducible manner, suitable for a national audit.

Back end of an enduring fuel cycle

International Nuclear Information System (INIS)

Pillay, K.K.S.

1998-03-01

An enduring nuclear fuel cycle is an essential part of sustainable consumption, the process whereby world's riches are consumed in a responsible manner so that future generations can continue to enjoy at least some of them. In many countries, the goal of sustainable development has focused attention on the benefits of nuclear technologies. However, sustenance of the nuclear fuel cycle is dependent on sensible management of all the resources of the fuel cycle, including energy, spent fuels, and all of its side streams. The nuclear fuel cycle for energy production has suffered many traumas since the mid seventies. The common basis of technologies producing nuclear explosives and consumable nuclear energy has been a preoccupation for some, predicament for others, and a perception problem for many. It is essential to reestablish a reliable back end of the nuclear fuel cycle that can sustain the resource requirements of an enduring full cycle. This paper identifies some pragmatic steps necessary to reverse the trend and to maintain a necessary fuel cycle option for the future

End-of-season heating fuel report

International Nuclear Information System (INIS)

1992-01-01

The year-end report notes that the 1991-92 heating season had lower average oil prices (retail home heating fuel) than the past two winters and prices remained relatively stable throughout the season. This year, the heating season average was $.87 per gallon, $1.05 for kerosene, and $1.33 for propane

Radiological and environmental safety in front-end fuel cycle facilities

International Nuclear Information System (INIS)

Puranik, V.D.

2011-01-01

The front end nuclear fuel cycle comprises of mining and processing of beach mineral sands along the southern coast of Kerala, Tamilnadu and Orissa, mining and processing of uranium ore in Singhbhum-East in Jharkhand and refining and fuel fabrication at Hyderabad. The Health Physics Units (HPUs)/Environmental Survey Laboratories (ESLs) set up at each site from inception of operation to carry out regular in-plant, personnel monitoring and environmental surveillance to ensure safe working conditions, evaluate radiation exposure of workers, ensure compliance with statutory norms, help in keeping the environmental releases well within the limits and advise appropriate control measures. This paper describes the occupational and environmental radiological safety measures associated with the operations of front end of nuclear fuel cycle. Radiological monitoring in these facilities is important to ensure safe working environment, protection of workers against exposure to radiation and comply with regulatory limits of exposure. The radiation exposure of workers in different units of the front end nuclear fuels cycle facilities operated by IREL, UCIL and NFC and environmental monitoring results are summarised in this paper

Radiological and environmental surveillance in front-end fuel cycle facilities

International Nuclear Information System (INIS)

Khan, A.H.; Sahoo, S.K.; Tripathi, R.M.

2004-01-01

This paper describes the occupational and environmental radiological safety measures associated with the operations of front end nuclear fuel cycle. Radiological monitoring in the facilities is important to ensure safe working environment, protection of workers against exposure to radiation and comply with regulatory limits of exposure. The radiation exposure of workers in different units of the front end nuclear fuels cycle facilities operated by IREL, UCIL and NFC and environmental monitoring results are summarised

The refurbishment of the D1206 fuel reprocessing plant

International Nuclear Information System (INIS)

Bailey, G.

1988-01-01

The term decommissioning can be applied not only to reactors but to any nuclear plant, laboratory, building or part of a building that may have been associated with radioactive material and needs to be restored to clean conditions. In this case the decommissioning and reconstruction of the Dounreay Fast Reactor fuel reprocessing plant, so that plutonium oxide could be reprocessed as well as enriched uranium fuel, is described. The work included improving containment and shielding, building a new head-end treatment cave for the more complex and larger fuel elements, improving the ventilation and constructing a new dissolver. In this paper the breakdown cave and dissolver cell are described and compared and the work done explained. (U.K.)

Grapples for manipulating end fittings for nuclear reactor fuel assemblies

International Nuclear Information System (INIS)

Jabsen, F.S.

1982-01-01

A nuclear fuel assembly includes control rod guide tubes the upper ends of which protrude beyond a spider and are locked in place by means of a cellular lattice seated in grooves in the outer surfaces of the sleeves. A grapple is provided for disengaging the structure comprising lattice, spider, springs and a grill from the end of the fuel assembly to enable these components to be removed in an assembly state and subsequently replaced after inspection and repair. (author)

Dissolution process for advanced-PWR-type fuels

International Nuclear Information System (INIS)

Black, D.E.; Decker, L.A.; Pearson, L.G.

1979-01-01

The new Fluorinel Dissolution Process and Fuel Storage (FAST) Facility at ICPP will provide underwater storage of spent PWR fuel and a new head-end process for fuel dissolution. The dissolution will be two-stage, using HF and HNO 3 , with an intermittent H 2 SO 4 dissolution for removing stainless steel components. Equipment operation is described

Cost-Effective Fuel Treatment Planning

Science.gov (United States)

Kreitler, J.; Thompson, M.; Vaillant, N.

2014-12-01

The cost of fighting large wildland fires in the western United States has grown dramatically over the past decade. This trend will likely continue with growth of the WUI into fire prone ecosystems, dangerous fuel conditions from decades of fire suppression, and a potentially increasing effect from prolonged drought and climate change. Fuel treatments are often considered the primary pre-fire mechanism to reduce the exposure of values at risk to wildland fire, and a growing suite of fire models and tools are employed to prioritize where treatments could mitigate wildland fire damages. Assessments using the likelihood and consequence of fire are critical because funds are insufficient to reduce risk on all lands needing treatment, therefore prioritization is required to maximize the effectiveness of fuel treatment budgets. Cost-effectiveness, doing the most good per dollar, would seem to be an important fuel treatment metric, yet studies or plans that prioritize fuel treatments using costs or cost-effectiveness measures are absent from the literature. Therefore, to explore the effect of using costs in fuel treatment planning we test four prioritization algorithms designed to reduce risk in a case study examining fuel treatments on the Sisters Ranger District of central Oregon. For benefits we model sediment retention and standing biomass, and measure the effectiveness of each algorithm by comparing the differences among treatment and no treat alternative scenarios. Our objective is to maximize the averted loss of net benefits subject to a representative fuel treatment budget. We model costs across the study landscape using the My Fuel Treatment Planner software, tree list data, local mill prices, and GIS-measured site characteristics. We use fire simulations to generate burn probabilities, and estimate fire intensity as conditional flame length at each pixel. Two prioritization algorithms target treatments based on cost-effectiveness and show improvements over those

Scientific research on the back-end of the fuel cycle for the 21. century

International Nuclear Information System (INIS)

2000-01-01

The aim of the Atalante-2000 conference is to present the major research axis concerning the nuclear fuel cycle back-end. The different topics are: - Present options concerning fuel cycle back-end; - Reprocessing of spent fuel; - Advanced separation for transmutation; - Processing and packaging of radioactive wastes; - Design and fabrication of targets for transmutation; and - Conversion of military plutonium into MOX fuels

IAEA activities in the back-end area of nuclear fuel cycle

International Nuclear Information System (INIS)

Fukuda, Kosaku

1999-01-01

This paper concerns recent outcomes from the IAEA's activities in the area of the nuclear fuel cycle, particularly focusing on the back-end of the fuel cycle. It includes spent fuel management, plutonium utilization and burnup credit. In the area of spent fuel management, worldwide prospects and status of the spent fuel arising, storage and reprocessing are presented. In the area of plutonium utilization worldwide, only MOX fuel fabrication is described. Finally, the worldwide status of the burnup credit implementation is described. (author)

Modified ADS molten salt processes for back-end fuel cycle of PWR spent fuel

International Nuclear Information System (INIS)

Choi, In-Kyu; Yeon, Jei-Won; Kim, Won-Ho

2002-01-01

The back-end fuel cycle concept for PWR spent fuel is explained. This concept is adequate for Korea, which has operated both PWR and CANDU reactors. Molten salt processes for accelerator driven system (ADS) were modified both for the transmutation of long-lived radioisotopes and for the utilisation of the remained fissile uranium in PWR spent fuels. Prior to applying molten salt processes to PWR fuel, hydrofluorination and fluorination processes are applied to obtain uranium hexafluoride from the spent fuel pellet. It is converted to uranium dioxide and fabricated into CANDU fuel. From the remained fluoride compounds, transuranium elements can be separated by the molten salt technology such as electrowinning and reductive extraction processes for transmutation purpose without weakening the proliferation resistance of molten salt technology. The proposed fuel cycle concept using fluorination processes is thought to be adequate for our nuclear program and can replace DUPIC (Direct Use of spent PWR fuel in CANDU reactor) fuel cycle. Each process for the proposed fuel cycle concept was evaluated in detail

End plug for fuel rod and welding method therefor

International Nuclear Information System (INIS)

Yoneda, Hiroshi; Murakami, Kazuo; Oyama, Jun-ichi.

1996-01-01

An end plug of a fuel rod comprises a pressure-insertion portion having a diameter somewhat greater than the inner diameter of a fuel cladding tube and a welding portion having a diameter substantially the same as the outer diameter of the cladding tube. A V-shaped recess having an outer diameter smaller than the greatest outer diameter of the pressure-insertion portion is formed over the entire circumferential surface of the outer circumference of the connection portion of the pressure-insertion portion and the welding portion. The pressure-insertion portion of the end plug is inserted to the end of the cladding tube till the end of the cladding tube abuts against the inclined surface of the V-shaped recess. The abutting surfaces of the end plug and the cladding tube are subjected to resistance welding in this state. The inner portion bulged from the inclined surface of the V-shaped recess is filled in the recess in a molten state. Lowering of temperature of the cladding tube in the vicinity of the welded portion is decreased by γ heat during reactor operation. Accordingly, lowering of ductility of the cladding tube and degradation of material of the welded region due to segregation of hydrogen in the cladding tube can be suppressed. (I.N.)

The back-end of the nuclear fuel cycle: The Argentine view

International Nuclear Information System (INIS)

Stevens, C.E.

2002-01-01

The strategy of the back-end nuclear fuel cycle for Argentina is presented in this paper. Although one may consider Argentina's current policy on spent fuel management as 'wait and see', Argentina is continuously directing her efforts towards the development of technology and human resources for the future demand of the closure of the nuclear fuel cycle. (author)

1981 Annual Status Report. Plutonium fuels and actinide programme

International Nuclear Information System (INIS)

1981-01-01

In this 1981 report the work carried out by the European Institute for Transuranium elements is reviewed. Main topics are: operation limits of plutonium fuels: swelling of advanced fuels, oxide fuel transients, equation of state of nuclear materials; actinide cycle safety: formation of actinides (FACT), safe handling of plutonium fuel (SHAPE), aspects of the head-end processing of carbide fuel (RECARB); actinide research: crystal chemistry, solid state studies, applied actinide research

The development of automated fuel dismantling equipment for a future head-end plant

International Nuclear Information System (INIS)

Haberlin, M.M.

1987-01-01

For future reprocessing plants, practicable methods for dismantling fuel elements are being examined at Springfields Nuclear Power Development Laboratories which would meet the requirements of a high throughput facility. This paper contains the initial results of an experimental programme undertaken to develop and evaluate an automated high speed single/multiple pin extraction unit. Concomitant parts of the programme include the design and evaluation of single and multi-pin extraction chucks. Dummy fuel elements, a 325 pin gridded LMFBR assembly and a 17 x 17 pin gridded LWR assembly were used to assess process efficacy

Burning of MOX fuels in LWRs; fuel history effects on thermal properties of hull and end piece wastes and the repository performance

International Nuclear Information System (INIS)

Hirano, Fumio; Sato, Seichi; Kozaki, Tamotsu

2012-01-01

The thermal impacts of hull and end piece wastes from the reprocessing of MOX spent fuels burned in LWRs on repository performance were investigated. The heat generation rates in MOX spent fuels and the resulting heat generation rates in hull and end piece wastes change depending on the history of MOX fuels. This history includes the burn-up of UO 2 spent fuels from which the Pu is obtained, the cooling period before reprocessing, the storage period of fresh MOX fuels before being loaded into an LWR, as well as the burn-up of the MOX fuels. The heat generation rates in hull and end piece wastes from the reprocessing of MOX spent fuels with any of those histories are significantly larger than those from UO 2 spent fuels with burn-ups of 45 GWd/THM. If a temperature below 80degC is specified for cement-based materials used in waste packages after disposal, the allowable number of canisters containing compacted hull and end pieces in a package for 45 and 70 GWd-MOX needs to be limited to a value of 0.4-1.6, which is significantly lower than 4.0 for 45 GWd-UO 2 . (author)

RTR spent fuel treatment and final waste storage

International Nuclear Information System (INIS)

Thomasson, J.

2000-01-01

A number of RTR operators have chosen in the past to send their spent fuel to the US in the framework of the US take back program. However, this possibility ends as of May 12th, 2006. 3 different strategies are left for managing RTR spent fuel: extended storage, direct disposal and treatment-conditioning through reprocessing. Whilst former strategies raise a number of uncertainties, the latter already offers a management solution. It features two advantages. It benefits from the long experience of existing flexible industrial facilities from countries like France. Secondly, it offers a dramatic volume reduction of the ultimate waste to be stored under well-characterized, stable and durable forms. RTR spent fuel management through reprocessing-conditioning offers a durable management solution that can be fully integrated in whatever global radioactive waste management policy, including ultimate disposal

Storage of thermal reactor fuels - Implications for the back end of the fuel cycle in the UK

International Nuclear Information System (INIS)

Hambley, D.

2016-01-01

Fuel from UK's Advanced Gas-Cooled Reactors (AGRs) is being reprocessed, however reprocessing will cease in 2018 and the strategy for fuel that has not been reprocessed is for it to be placed into wet storage until it can be consigned to a geological disposal facility in around 2080. Although reprocessing of LWR fuel has been undertaken in the UK, and this option is not precluded for current and future LWRs, all utilities planning to operate LWRs are intending to use At-Reactor storage pending geological disposal. This strategy will result in a substantial change in the management of spent fuel that could affect the back end of the fuel cycle for over a century. This paper presents potential fuel storage scenarios for two options: the current nuclear power replacement strategy, which will see 16 GWe of new capacity installed by 2030 and a median strategy, intended to ensure implementation of the UK's carbon reduction target, involving 48 GWe of nuclear capacity installed by 2040. The potential scale, distribution and timing of fuel storage and disposal operations have been assessed and changes to the current industrial activity are highlighted to indicate potential effects on public acceptance of back end activities. (authors)

Determination of mixing factors for VVER-440 fuel assembly head

Energy Technology Data Exchange (ETDEWEB)

Tóth, S., E-mail: toth@reak.bme.hu [Institute of Nuclear Techniques, Budapest University of Technology and Economics, Műegyetem rkp. 9, H-1111 Budapest (Hungary); Aszódi, A. [Institute of Nuclear Techniques, Budapest University of Technology and Economics, Műegyetem rkp. 9, H-1111 Budapest (Hungary)

2013-11-15

CFD models have been developed for the heads of the old, the present and the new type VVER-440 fuel assemblies using the experience of a former validation process. With these models temperature distributions are investigated in the heads of some typical assemblies and the in-core thermocouple signals are calculated. The analyses show that the coolant mixing is intensive but not-perfect in the assembly heads. The difference between the thermocouple signal and the cross-sectional average temperature at the measurement level depends on the assembly type. Using the results of these CFD calculations the weight factors of the rod bundle regions for the in-core thermocouple have been determined. With these factors the thermocouple signals are estimated and the results are statistically tested using the registered data of the Hungarian nuclear power plant. This test shows that the deviations between the measured and the calculated temperatures can be significantly decreased and consequently monitoring uncertainties can be reduced with using the weight factors.

Online ICPMS detection of the thermal release of fission products from nuclear fuel samples

International Nuclear Information System (INIS)

Guenther-Leopold, I.; Svedkauskaite-Le Gore, J.; Kivel, N.

2009-01-01

Full text: The release of volatile and semi-volatile fission products (like Cs, Tc, Mo etc.) from spent nuclear fuel by thermal and thermochemical treatment (oxidative or reductive conditions) as a head-end step for advanced reprocessing scenarios is studied in the Hot Laboratory of the Paul Scherrer Institut. For this purpose, a heated sampling cell online connected to an ICPMS (Element 2, Thermo Fisher Scientific) was designed and tested on simulated fuel samples up to 650 o C. The results of this study as well as technical perspectives for heating experiments up to 2000 o C will be presented. (author)

Development of spent fuel remote handling technology

International Nuclear Information System (INIS)

Yoon, J. S.; Hong, H. D.; Kim, Y. H.

2001-03-01

Since the amount of the spent fuel rapidly increases, the current R and D activities are focused on the technology development related with the storage and utilization of the spent fuel. In this research, to provide such a technology, the mechanical head-end process has been developed. In detail, the swing and shock-free crane and the RCGLUD(Remote Cask Grappling and Lid Unbolting Device) were developed for the safe transportation of the spent fuel assembly, the LLW drum and the transportation cask. Also, the disassembly devices required for the head-end process were developed. This process consists of an assembly downender, a rod extractor, a rod cutter, a fuel decladding device, a skeleton compactor, a force-rectifiable manipulator for the abnormal spent fuel disassembly, and the gantry type telescopic transporter, etc. To provide reliability and safety of these devices, the 3 dimensional graphic design system is developed. In this system, the mechanical devices are modelled and their operation is simulated in the virtual environment using the graphic simulation tools. So that the performance and the operational mal-function can be investigated prior to the fabrication of the devices. All the devices are tested and verified by using the fuel prototype at the mockup facility

Mechanical Performance Evaluation of a Top End Piece for Dual Cooled Fuels

International Nuclear Information System (INIS)

Kim, Jae Yong; Yoon, Kyung Ho; Kim, Hyung Kyu; Choi, Woo Seok

2011-01-01

A fuel assembly consists of five major components, i.e., a top end piece (TEP), a bottom end piece (BEP), spacer grids (SGs), guide tubes (GTs) and an instrumentation tube (IT): in addition, it also includes fuel rods (FRs). The TEP/BEP should satisfy stress intensity limits according to the conditions A and B of ASME, Section III, Division 1.Subsection NB. In a dual-cooled fuel assembly, the array and position of fuel rods are different from those in a conventional PWR fuel assembly; these changes are necessary for achieving power uprating. The flow plates of the TEP and BEP have to be modified accordingly. The pattern and shape of the flow holes were newly designed. To verify the strength compatibility, the Tresca stress limit according to the ASME code was investigated in the case of an axial load of 22.241 kN. In this paper, the stress linearization procedure for strength evaluation of a newly designed TEP is presented

The economics of the back end of the nuclear fuel cycle

International Nuclear Information System (INIS)

Cameron, Ron; Urso, Maria Elena; Lokhov, Alexey

2014-01-01

Spent nuclear fuel and high-level waste from the fuel cycle of commercial nuclear power plants represent a small proportion of the radioactive waste produced globally by various industries (including medicine, agriculture and research), but they account for the greatest radioactivity content and longevity. While technologies are well developed and widely employed for the treatment and disposal of the much larger volumes of less radioactive low-level and short-lived intermediate-level waste, no final disposal facilities have yet been fully implemented for spent nuclear fuel (SNF) and high-level waste (HLW). A lack of experience in the construction and operation of deep geological repositories, combined with the extensive periods required for the implementation of back-end solutions, have thus contributed to growing uncertainties about the costs associated with managing SNF and HLW. The issue has become a central challenge for the nuclear industry and a matter of public concern and debate. Using official data supplied by national authorities, a descriptive overview [1] was developed of general principles and frameworks for the long-term management of SNF, current national policies and practices, as well as available and prospective technology options, including: - Direct disposal, where the fuel is used once and then regarded as waste for disposal. - Partial recycling, where the spent fuel is reprocessed to recover unused uranium and plutonium for recycling in light water reactors (LWRs). Once irradiated, the recycled fuel bundles can be either stored (with the perspective of their reprocessing and recycling in future fast reactors - FRs) or disposed of after encapsulation. - Advanced systems and fuel cycle concepts for the longer-term future, studied theoretically or on a pilot scale, with the dual objective of reducing the mass and radioactivity of waste destined to final disposal and optimising the use of natural resources. In addition, a cost analysis of these

The nuclear fuel cycle desperately in need of front end alignment

International Nuclear Information System (INIS)

White, G.; Reaves, J.

1983-01-01

The front end of the nuclear fuel cycle which includes uranium supply, conversion of U308 to UF6 and enrichment of UF6, is characterized by excess capacity, excess production, growing inventories and price weakness. Excess capacity resulted from uncritical acceptance by suppliers of overly optimistic utility plans for nuclear growth. Cancellation and deferrals of nuclear plans led to reductions in forecast demand just as the new production capacity was coming on line to meet the high levels of demand forecast earlier. The unique and conservative nature of the utilities as business entities and the unique, sole-end-use character of uranium and its related fuel cycle services suggest that the markets for these materials and services will differ from those of other fuels. An international market is foreseen, marked by continuing boom-bust cycles

Inactive end cell assembly for fuel cells for improved electrolyte management and electrical contact

Science.gov (United States)

Yuh, Chao-Yi [New Milford, CT; Farooque, Mohammad [Danbury, CT; Johnsen, Richard [New Fairfield, CT

2007-04-10

An assembly for storing electrolyte in a carbonate fuel cell is provided. The combination of a soft, compliant and resilient cathode current collector and an inactive anode part including a foam anode in each assembly mitigates electrical contact loss during operation of the fuel cell stack. In addition, an electrode reservoir in the positive end assembly and an electrode sink in the negative end assembly are provided, by which ribbed and flat cathode members inhibit electrolyte migration in the fuel cell stack.

Analysis of factors affecting the implementation of back-end nuclear fuel cycle policy in Korea

International Nuclear Information System (INIS)

Choi, Yung Myung; Yang, Maeng Ho; Kim, Hyun Joon; Chung, Hwan Sam; Oh, Keun Bae; Lee, Byung OoK; Ko, Han Suk; Song, Ki Dong; Lee, Man Ki; Moon, Ki Hwan; Lee, Han Myung

1994-01-01

In this study, the back-end nuclear fuel cycle acceptability is surveyed and analyzed in the following three aspects. To begin with, the future political situation and energy-environmental issues are analyzed as part of the socio-economic aspect. Secondly, the domestic situation of nuclear industries and the fuel cycle policy of foreign countries are surveyed as the technical aspect. Finally, NPT, IAEA safeguards and nuclear export control regimes are analyzed as the institutional aspect. The unification period of South and North Korea also will greatly affect the implementation of back-end fuel cycle policy, and public attitudes will affect the acquisition of site, construction, and operation of nuclear facilities. An effort to release international restrictions on the back-end fuel cycle is also required to accelerate the implementation of the policy. In this regard, the back-end fuel cycle policy should be clear-cut to avoid misunderstanding with respect to nuclear proliferation. Importantly, agreements with foreign countries should be amended at a mutual equivalent level. (Author) 30 refs., 5 figs., 25 tabs

Analysis of factors affecting the implementation of back-end nuclear fuel cycle policy in Korea

Energy Technology Data Exchange (ETDEWEB)

Choi, Yung Myung; Yang, Maeng Ho; Kim, Hyun Joon; Chung, Hwan Sam; Oh, Keun Bae; Lee, Byung OoK; Ko, Han Suk; Song, Ki Dong; Lee, Man Ki; Moon, Ki Hwan; Lee, Han Myung [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

1994-01-01

In this study, the back-end nuclear fuel cycle acceptability is surveyed and analyzed in the following three aspects. To begin with, the future political situation and energy-environmental issues are analyzed as part of the socio-economic aspect. Secondly, the domestic situation of nuclear industries and the fuel cycle policy of foreign countries are surveyed as the technical aspect. Finally, NPT, IAEA safeguards and nuclear export control regimes are analyzed as the institutional aspect. The unification period of South and North Korea also will greatly affect the implementation of back-end fuel cycle policy, and public attitudes will affect the acquisition of site, construction, and operation of nuclear facilities. An effort to release international restrictions on the back-end fuel cycle is also required to accelerate the implementation of the policy. In this regard, the back-end fuel cycle policy should be clear-cut to avoid misunderstanding with respect to nuclear proliferation. Importantly, agreements with foreign countries should be amended at a mutual equivalent level. (Author) 30 refs., 5 figs., 25 tabs.

Dosimetric assessment of the field abutment region in head and neck treatments using a multileaf collimator

Energy Technology Data Exchange (ETDEWEB)

Abdel-Hakim, K.; Nishimura, T.; Sakahara, H. [Dept. of Radiology, Hamamatsu Univ. School of Medicine, Hamamatsu (Japan); Takaih, M.; Suzuki, S. [Dept. of Informatics, Hamamatsu Univ. School of Medicine, Hamamatsu (Japan)

2003-05-01

overdose could be smoothed out by overlaps of both leaf ends by 0.8 mm from both lateral and anterior portals. The ideal jaw position was found to be at 1 mm away from the beam central axis in any combination. Conclusion: The use of MLCs for photon field junction matching is appropriate and represents an alternative approach to the problem of field matching using the asymmetric jaws in head and neck treatments. asymmetric jaws in head and neck treatments. (orig.)

Dosimetric assessment of the field abutment region in head and neck treatments using a multileaf collimator

International Nuclear Information System (INIS)

Abdel-Hakim, K.; Nishimura, T.; Sakahara, H.; Takaih, M.; Suzuki, S.

2003-01-01

out by overlaps of both leaf ends by 0.8 mm from both lateral and anterior portals. The ideal jaw position was found to be at 1 mm away from the beam central axis in any combination. Conclusion: The use of MLCs for photon field junction matching is appropriate and represents an alternative approach to the problem of field matching using the asymmetric jaws in head and neck treatments. asymmetric jaws in head and neck treatments. (orig.)

Nuclear reactor fuel assemblies and end fitting grid structures therefor

International Nuclear Information System (INIS)

Jabsen, F.S.

1978-01-01

An improved end fitting grid structure is described for nuclear fuel assemblies which overcomes the need for load-bearing control rod guide tubes and the expensive special fittings that these tubes required. (UK)

Advanced biological treatment of aqueous effluent from the nuclear fuel cycle

International Nuclear Information System (INIS)

Pitt, W.W. Jr.; Hancher, C.W.; Patton, B.D.; Shumate, S.E. II.

1979-01-01

Many of the processing steps in the nuclear fuel cycle generate aqueous effluent streams bearing contaminants that can, because of their chemical or radiological properties, pose an environmental hazard. Concentration of such contaminants must be reduced to acceptable levels before the streams can be discharged to the environment. Two classes of contaminants, nitrates and heavy metals, are addressed in this study. Specific techniques aimed at the removal of nitrates and radioactive heavy metals by biological processes are being developed, tested, and demonstrated. Although cost comparisons between biological processes and current treatment methods are presented, these comparisons may be misleading because biological processes yield environmentally better end results which are difficult to price. However, a strong case is made for the use of biological processes for removing nitrates and heavy metals fron nuclear fuel cycle effluents. The estimated costs for these methods are as low as, or lower than, those for alternate processes. In addition, the resulting disposal products - nitrogen gas, CO 2 , and heavy metals incorporated into microorganisms - are much more ecologically desirable than the end products of other waste treatment methods

Fuel element

International Nuclear Information System (INIS)

1974-01-01

A new fuel can with a loose bottom and head is described. The fuel bar is attached to the loose bottom and head with two grid poles keeping the distance between bottom and head. A bow-shaped handle is attached to the head so that the fuel bar can be lifted from the can

Review of the patents of Top and Bottom End Piece and fuel materials issued by overseas fuel vendors

International Nuclear Information System (INIS)

Yoon, Kyung Ho; Song, Kee Nam; Kim Hyung Kyu; Kang, Heung Seok; Bang, Je Geon.

1997-06-01

In order to develop new type nuclear fuel which can be loaded in the domestic PWRs without serious design changes, it is very important to understand the developing status of fuel components being conducted by overseas fuel vendors prior to commence the full-scale campaign. In this report, patents recorded in US patent lists have been inquired to understand the object, the background and the peculiarity of the invented components for top/bottom end piece and fuel materials. In addition, the important things which must be considered in development of new type fuel were described. (author). 18 tabs., 63 figs., 24 refs

Quantitative Analysis of the Civilian Bilateral Cooperation in Front-End of the Nuclear Fuel Cycle

Energy Technology Data Exchange (ETDEWEB)

Nguyen, Viet Phuong; Yim, Man-Sung [Korea Advanced Institute of Science and Technology, Daejeon (Korea, Republic of)

2015-05-15

A substantial part of such cooperation is related to the front-end of the nuclear fuel cycle, which encompasses the processes that help manufacturing nuclear fuel, including mining and milling of natural uranium, refining and chemical conversion, enrichment (in case of fuels for Pressurized Water Reactor PWR), and fuel fabrication. Traditionally, the supply of natural uranium was dominated by Canada and Australia, whereas enrichment services have been mostly provided by companies from Western states or Russia, which are also the main customers of such services. However, Kazakhstan and African countries like Niger, Namibia, and Malawi have emerged as important suppliers in the international uranium market and recent forecasts show that China will soon become a major player in the front-end market as both consumer and service provider. In this paper, the correlation between bilateral civil nuclear cooperation in front-end of the nuclear fuel cycle and the political and economic relationship among countries was examined through a dataset of bilateral nuclear cooperation in the post-Cold War era, from 1990 to 2011. Such finding has implication on not only the nonproliferation research but also the necessary reinforcement of export control regimes like such as the Nuclear Suppliers Group. Further improvement of this dataset and the regression method are also needed in order to increase the robustness of the findings as well as to cover the whole scope of the nuclear fuel cycle, including both front-end and back-end activities.

Quantitative Analysis of the Civilian Bilateral Cooperation in Front-End of the Nuclear Fuel Cycle

International Nuclear Information System (INIS)

Nguyen, Viet Phuong; Yim, Man-Sung

2015-01-01

A substantial part of such cooperation is related to the front-end of the nuclear fuel cycle, which encompasses the processes that help manufacturing nuclear fuel, including mining and milling of natural uranium, refining and chemical conversion, enrichment (in case of fuels for Pressurized Water Reactor PWR), and fuel fabrication. Traditionally, the supply of natural uranium was dominated by Canada and Australia, whereas enrichment services have been mostly provided by companies from Western states or Russia, which are also the main customers of such services. However, Kazakhstan and African countries like Niger, Namibia, and Malawi have emerged as important suppliers in the international uranium market and recent forecasts show that China will soon become a major player in the front-end market as both consumer and service provider. In this paper, the correlation between bilateral civil nuclear cooperation in front-end of the nuclear fuel cycle and the political and economic relationship among countries was examined through a dataset of bilateral nuclear cooperation in the post-Cold War era, from 1990 to 2011. Such finding has implication on not only the nonproliferation research but also the necessary reinforcement of export control regimes like such as the Nuclear Suppliers Group. Further improvement of this dataset and the regression method are also needed in order to increase the robustness of the findings as well as to cover the whole scope of the nuclear fuel cycle, including both front-end and back-end activities

Electro-optical fuel pin identification system

International Nuclear Information System (INIS)

Kirchner, T.L.

1978-09-01

A prototype Electro-Optical Fuel Pin Identification System referred to as the Fuel Pin Identification System (FPIS) has been developed by the Hanford Engineering Development Laboratory (HEDL) in support of the Fast Flux Test Facility (FFTF) presently under construction at HEDL. The system is designed to remotely read an alpha-numeric identification number that is roll stamped on the top of the fuel pin end cap. The prototype FPIS consists of four major subassemblies: optical read head, digital compression electronics, video display, and line printer

Apparatus for inspecting the quality of nuclear fuel rod ends

International Nuclear Information System (INIS)

Brashier, R.W.; Pfau, E.D.

1990-01-01

This patent describes an apparatus for inspecting the quality of both ends of nuclear fuel rods. It comprises: a housing including a pair of longitudinally separated slots for receiving X-ray downwardly therethrough from an external source and so as to define first and second longitudinally spaced apart operating positions, means for serially guiding nuclear fuel rods longitudinally through the housing and to a first rod position wherein the forward ends of the rods are aligned below the first operating position and to a second rod position wherein the rear ends of the rods are aligned below the second operating position, belt conveyor assembly means for serially advancing X-ray film cartridges longitudinally through the housing and below the rods, and so that each cartridge may be selectively aligned below the first and second operating positions; and table means supported by the conveyor frame for selectively lifting the film cartridges supported by the belts and so that the conveyor belts may be advanced while the film cartridges are held stationary

Development of Head-end Pyrochemical Reduction Process for Advanced Oxide Fuels

International Nuclear Information System (INIS)

Park, B. H.; Seo, C. S.; Hur, J. M.; Jeong, S. M.; Hong, S. S.; Choi, I. K.; Choung, W. M.; Kwon, K. C.; Lee, I. W.

2008-12-01

The development of an electrolytic reduction technology for spent fuels in the form of oxide is of essence to introduce LWR SFs to a pyroprocessing. In this research, the technology was investigated to scale a reactor up, the electrochemical behaviors of FPs were studied to understand the process and a reaction rate data by using U 3 O 8 was obtained with a bench scale reactor. In a scale of 20 kgHM/batch reactor, U 3 O 8 and Simfuel were successfully reduced into metals. Electrochemical characteristics of LiBr, LiI and Li 2 Se were measured in a bench scale reactor and an electrolytic reduction cell was modeled by a computational tool

Economists and the end of fossil fuels (1865-1931)

International Nuclear Information System (INIS)

Missemer, Antoine

2017-01-01

From the 1860's to the 1930's, economists' views about the end of fossil fuels changed. Technological as well as theoretical developments were behind this. The challenge here is to disentangle this web in order to understand how economists (even today) deal with environmental topics

Factors determining the UK's back-end nuclear fuel cycle strategy and future nuclear systems

International Nuclear Information System (INIS)

Dunn, M.J.; Ainsworth, Z.E.

2002-01-01

Nuclear generating capacity in the UK is static with no units currently under construction. The AGRs and the UK's only PWR, Sizewell B, are operated by British Energy Generation Ltd (BEGL) and British Energy Generation (UK) Ltd (BEG(UK)L), who are subsidiaries of British Energy plc (BE) which was privatised in July 1996. Ownership of the Magnox stations, which were excluded from this privatisation, has now been transferred to BNFL.Government policy on spent fuel management in the UK is that it is for the owners of the spent fuel to decide on the appropriate spent fuel management options, based on their own commercial judgement, subject to meeting the necessary regulatory requirements. The main factors which have predominantly determined UK utility decisions on spent fuel management, to date, have been based on the technical considerations of the spent fuel characteristics, economic attractiveness of the options and at reactor site spent fuel storage capacities. To date, reprocessing has been the dominant form of spent fuel treatment in the UK. Spent fuel storage facilities consist of a mixture of at-reactor stores and large, centralised ponds associated with the reprocessing activities which take place at the Sellafield site. BEGL and BEG(UK)L have contracts for the lifetime arisings of AGR fuel which allow for all AGR spent fuel to be sent to Sellafield for reprocessing or long-term storage. The prompt reprocessing of all Magnox fuel will continue, and spent PWR fuel will continue to be stored at the reactor site in the short to medium term. It is likely that a combination of factors, which are discussed later in this paper, will continue to affect back-end nuclear fuel cycle strategy and future nuclear systems. (author)

PWR fuel assembly

International Nuclear Information System (INIS)

Yamada, Yuji.

1995-01-01

A lower end plug is secured to a lower end of a thimble tube. A bolt-like thimble screw is screw-coupled and fastened to a female screw disposed to the end plug by way of a bushing screw-coupled to a lower nozzle. Then, the thimble screw and the lower nozzle are welded to secure the thimble tube and the lower nozzle. The lower portion of the bushing extends near the lower surface of the lower nozzle. The extended portion is provided with a recess to which a bolt head of the thimble screw is tightly inserted and a seating-face portion against which a seating-face of the bolt head abuts. Then, the extended portion of the bushing and the lower nozzle are spot-welded on the side of the lower surface of the nozzle, to prevent rotation of the bushing. This can easily prevent the rotation of the bushing after adjustment, to simplify the assembling of the fuel assembly. (I.N.)

Fuel Chemistry Division: progress report for 1987

International Nuclear Information System (INIS)

1990-01-01

The progress of research and development activities of the Fuel Chemistry Division of the Bhabha Atomic Research Centre, Bombay, during 1987 is reported in the form of summaries which are arranged under the headings: Fuel Development Chemistry, Chemistry of Actinides, Chemical Quality Control of Fuel, and Studies related to Nuclear Material Accounting. A list of publications by the members of the Division during the report period is given at the end of the report. (M.G.B.). refs., 15 figs., 85 tabs

Detailed analysis of coolant mixing in WWER-440 fuel assembly heads

International Nuclear Information System (INIS)

Toth, S.; Aszodi, A.

2008-01-01

Based on experiences of former validation and sensitivity studies, a CFD model for head part of real working fuel assemblies with pitch of 12.3 mm has been developed with the code ANSYS CFX. Calculations were performed for typical fuel assemblies used in the Paks NPP. Differences between the outlet average temperatures and thermocouple signals were determined. Effect of the mixing grid position on thermocouple signal was investigated also. Mixing was analyzed in details with using so-called mixing scalars and weight factors of the central tube and rod bundle regions for in-core thermocouple signal were determined. Sensitivity of the weight factors for pin power distribution and mixing grid position were investigated. (Authors)

Evaluation of self-water-removal in a dead-ended proton exchange membrane fuel cell

International Nuclear Information System (INIS)

Wan, Zhongmin; Liu, Jing; Luo, Zhiping; Tu, Zhengkai; Liu, Zhichun; Liu, Wei

2013-01-01

Highlights: ► Operation characteristics in a dead-ended PEM fuel cell were addressed. ► Modified flow channel was used to realize water removal. ► A novel method by condensing the moisture in the stack end was introduced. - Abstract: In this paper, the operation characteristic of a dead-ended proton exchange membrane fuel cell (PEMFC) placed with vertical orientation is investigated. The relationship between the channel geometry and the wettability of the gas diffusion layer (GDL) surface is theoretically analyzed. Based on the theoretical analysis, straight flow channels with 2.0 mm width and 1.0 mm depth are used for the experimental investigation and the moisture is condensed at the stack end to improve water removal. The results show that the designed fuel cell can operate for about 1 h at 800 mA cm −2 and the performance of the cell decreases with the increase in the operation temperature. Moreover, the recovered liquid water is corresponded closely to the theoretical values

Development of Head-end Pyrochemical Reduction Process for Advanced Oxide Fuels

Energy Technology Data Exchange (ETDEWEB)

Park, B. H.; Seo, C. S.; Hur, J. M.; Jeong, S. M.; Hong, S. S.; Choi, I. K.; Choung, W. M.; Kwon, K. C.; Lee, I. W. [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2008-12-15

The development of an electrolytic reduction technology for spent fuels in the form of oxide is of essence to introduce LWR SFs to a pyroprocessing. In this research, the technology was investigated to scale a reactor up, the electrochemical behaviors of FPs were studied to understand the process and a reaction rate data by using U{sub 3}O{sub 8} was obtained with a bench scale reactor. In a scale of 20 kgHM/batch reactor, U{sub 3}O{sub 8} and Simfuel were successfully reduced into metals. Electrochemical characteristics of LiBr, LiI and Li{sub 2}Se were measured in a bench scale reactor and an electrolytic reduction cell was modeled by a computational tool.

Measures of the Environmental Footprint of the Front End of the Nuclear Fuel Cycle

Energy Technology Data Exchange (ETDEWEB)

Brett Carlsen; Emily Tavrides; Erich Schneider

2010-08-01

Previous estimates of environmental impacts associated with the front end of the nuclear fuel cycle have focused primarily on energy consumption and CO2 emissions. Results have varied widely. Section 2 of this report provides a summary of historical estimates. This study revises existing empirical correlations and their underlying assumptions to fit to a more complete set of existing data. This study also addresses land transformation, water withdrawals, and occupational and public health impacts associated with the processes of the front end of the once-through nuclear fuel cycle. These processes include uranium mining, milling, refining, conversion, enrichment, and fuel fabrication. Metrics are developed to allow environmental impacts to be summed across the full set of front end processes, including transportation and disposition of the resulting depleted uranium.

Measures of the Environmental Footprint of the Front End of the Nuclear Fuel Cycle

International Nuclear Information System (INIS)

Carlsen, Brett; Tavrides, Emily; Schneider, Erich

2010-01-01

Previous estimates of environmental impacts associated with the front end of the nuclear fuel cycle have focused primarily on energy consumption and CO2 emissions. Results have varied widely. Section 2 of this report provides a summary of historical estimates. This study revises existing empirical correlations and their underlying assumptions to fit to a more complete set of existing data. This study also addresses land transformation, water withdrawals, and occupational and public health impacts associated with the processes of the front end of the once-through nuclear fuel cycle. These processes include uranium mining, milling, refining, conversion, enrichment, and fuel fabrication. Metrics are developed to allow environmental impacts to be summed across the full set of front end processes, including transportation and disposition of the resulting depleted uranium.

Fuel Chemistry Division annual progress report for 1990

International Nuclear Information System (INIS)

Vaidyanathan, R.

1993-01-01

The progress report gives brief descriptions of the various activities of the Fuel Chemistry Division of Bhabha Atomic Research Centre, Bombay for the year 1990. The descriptions of activities are arranged under the headings: Fuel Development Chemistry, Chemistry of Actinides, Quality Control of Nuclear Fuels, and studies related to Nuclear Materials Accounting. At the end of the report, a list of papers published in journals and presented at various conferences/symposia is also given. (author). 7 figs., 52 tabs

Fuel Chemistry Division: annual progress report for 1988

International Nuclear Information System (INIS)

Vaidyanathan, S.

1991-01-01

The progress report gives the brief descriptions of various activites of the Fuel Chemistry Division of Bhabha Atomic Research Centre, Bombay for the year 1988. The descriptions of activities are arranged under the headings: Fuel Development Chemistry of Actinides, Quality Control of Fuel, and Studies related to Nuclear Material Accounting. At the end of report, a list of publications published in journals and papers presented at various conferences/symposia during 1988 is given. (author). 13 figs., 61 tabs

Study on the Efficient Disintegration of HTGR Fuel Elements by Electrochemical Method

International Nuclear Information System (INIS)

Piao Nan; Chen Ji; Xiao Cuiping; We Mingfen; Che Jing

2014-01-01

The spent fuel elements in High- temperature gas-cooled reactor (HTGR) have a special structure, so the head-end process of the spent fuel reprocessing is different from the process of water reactor spent fuel. The first step of head-end process of the HTGR spent fuel reprocessing process is disintegration of the graphite matrix and separation of the coated fuel particles. Electrochemical method with nitrate solution as an electrolyte for fuel element disintegration has been conducted by the Institute of Nuclear and New Energy Technology in Tsinghua University. This method allows a total disintegration of graphite matrix, while still preserving the integrity of TRISO particles. The influences of the pretreatment methods such as heating oxidation of graphite, hydrothermal and oxidants oxidation were investigated in the present work. The experimental results showed that there were no significant effects on increasing the disintegration rate when pretreatment methods were used ahead of electrochemical disintegration. This phenomenon indicated that the fuel elements which were calcined at 1073 K and pressed under 300 MPa are too compact to be broken by these pretreatment methods. And the electrochemical disintegration is an effective but slow method in breaking the graphite matrix. (author)

Resource intensities of the front end of the nuclear fuel cycle

International Nuclear Information System (INIS)

Schneider, E.; Phathanapirom, U.; Eggert, R.; Collins, J.

2013-01-01

This paper presents resource intensities, including direct and embodied energy consumption, land and water use, associated with the processes comprising the front end of the nuclear fuel cycle. These processes include uranium extraction, conversion, enrichment, fuel fabrication and depleted uranium de-conversion. To the extent feasible, these impacts are calculated based on data reported by operating facilities, with preference given to more recent data based on current technologies and regulations. All impacts are normalized per GWh of electricity produced. Uranium extraction is seen to be the most resource intensive front end process. Combined, the energy consumed by all front end processes is equal to less than 1% of the electricity produced by the uranium in a nuclear reactor. Land transformation and water withdrawals are calculated at 8.07 m 2 /GWh(e) and 1.37x10 5 l/GWh(e), respectively. Both are dominated by the requirements of uranium extraction, which accounts for over 70% of land use and nearly 90% of water use

Correlation of radioactive waste treatment costs and the environmental impact of waste effluents in the nuclear fuel cycle: reprocessing of high-temperature gas-cooled reactor fuel containing U-233 and thorium

International Nuclear Information System (INIS)

Davis, W. Jr.; Blanco, R.E.; Finney, B.C.; Hill, G.S.; Moore, R.E.; Witherspoon, J.P.

1976-05-01

A cost/benefit study was made to determine the cost and effectiveness of various radioactive waste (radwaste) treatment systems for decreasing the release of radioactive materials from a model high-temperature gas-cooled reactor (HTGR) fuel reprocessing plant and to determine the radiological impact (dose commitment) of the released materials on the environment. The study is designed to assist the U. S. Nuclear Regulatory Commission in defining the term as low as reasonably achievable as it applies to this nuclear facility. The base case is representative of conceptual, developing technology of head-end graphite-burning operations and of extensions of solvent-extraction technology of current designs for light-water-reactor (LWR) fuel reprocessing plants. The model plant has an annual capacity of 450 metric tons of heavy metal (MTHM, where heavy metal is uranium plus thorium), as charged to about fifty 1000-MW(e) HTGRs. Additional radwaste treatment systems are added to the base-case plant in a series of case studies to decrease the amounts of radioactive materials released and to reduce the radiological dose commitment to the population in the surrounding area. The capital and annual costs for the added waste treatment operations and the corresponding reductions in dose commitments are calculated for each case. In the final analysis, the cost/benefit of each case, calculated as additional cost of radwaste system divided by the reduction in dose commitment, is tabulated or the dose commitment is plotted with cost as the variable. The status of each of the radwaste treatment methods used in the case studies is discussed

Evaluation of strategies for end storage of high-level reactor fuel

International Nuclear Information System (INIS)

2001-01-01

This report evaluates a national strategy for end-storage of used high-level reactor fuel from the research reactors at Kjeller and in Halden. This strategy presupposes that all the important phases in handling the high-level material, including temporary storage and deposition, are covered. The quantity of spent fuel from Norwegian reactors is quite small. In addition to the technological issues, ethical, environmental, safety and economical requirements are emphasized

Cause of defect in the end plug welding of the JOYO fuel pin

International Nuclear Information System (INIS)

Ouchi, Masaru; Otani, Seiji; Onisi, Koichi; Tateisi, Yoshinori; Ikawa, Yukio.

1976-01-01

About twelve thousand fuel pins for the JOYO core fuel were fabricated, and their end plug welding was inspected by X-ray radiography. The defect fractions were 0.2 percent for the lower end plugs and 1.8 percent for the upper, respectively. It had been known that the defect was due to ''line porosity''. In this study, the cause of the ''line porosity defect'' was investigated by the welding experiment performed on some dummy specimens of three different types; open end; closed end; and closed end with dummy pellets and a spring. The position of electrodes was varied for changing the arc gap from 0.3 mm to 1.2 mm. The experimental results are summarized in tables. The results showed that no defect was found in the open end type specimens even with the arc gap of 1.2 mm. Whereas in the other two types of specimens, the defect fraction of 60 to 75 percent was observed with the same arc gap. As for the effect of the arc gap, it was shown that 0.3 mm is the best among 0.3 mm, 0.5 mm and 1.2 mm. No defect was observed in the third type of specimens with the arc gap of 0.3 mm. In summary, it was found that the line porosity defect did not depend on the shape of the end plugs. It is considered to be dependent on both the structure of dummy fuel pins and the position of electrodes. (Aoki, K.)

Spent fuel reprocessing system availability definition by process simulation

International Nuclear Information System (INIS)

Holder, N.; Haldy, B.B.; Jonzen, M.

1978-05-01

To examine nuclear fuel reprocessing plant operating parameters such as maintainability, reliability, availability, equipment redundancy, and surge storage requirements and their effect on plant throughput, a computer simulation model of integrated HTGR fuel reprocessing plant operations is being developed at General Atomic Company (GA). The simulation methodology and the status of the computer programming completed on reprocessing head end systems is reported

Automatic planning of head and neck treatment plans

DEFF Research Database (Denmark)

Hazell, Irene; Bzdusek, Karl; Kumar, Prashant

2016-01-01

radiation dose planning (dosimetrist) and potentially improve the overall plan quality. This study evaluates the performance of the Auto-Planning module that has recently become clinically available in the Pinnacle3 radiation therapy treatment planning system. Twenty-six clinically delivered head and neck...... as the previously delivered clinical plans. For all patients, the Auto-Planning tool produced clinically acceptable head and neck treatment plans without any manual intervention, except for the initial target and OAR delineations. The main benefit of the method is the likely improvement in the overall treatment......Treatment planning is time-consuming and the outcome depends on the person performing the optimization. A system that automates treatment planning could potentially reduce the manual time required for optimization and could also pro-vide a method to reduce the variation between persons performing...

End plate for e.g. solid oxide fuel cell stack, sets thermal expansion coefficient of material to predetermined value

DEFF Research Database (Denmark)

2011-01-01

.05-0.3 mm. USE - End plate for solid oxide fuel cell stack (claimed). Can also be used in polymer electrolyte fuel cell stack and direct methanol fuel cell stack. ADVANTAGE - The robustness of the end plate is improved. The structure of the end plate is simplified. The risk of delamination of the stack...

Connection between end plates and rods in a BWR fuel element

International Nuclear Information System (INIS)

Cali', G.P.

1975-01-01

The problem of the connection between the end plates and the rods of a BWR fuel element is analytically formulated. The behaviour of the springs coupling the rods with the upper plate is analyzed with particular detail since the deformation of these springs affects the forces at the interface of the fuel element structure components. A tool is given to design the springs according to some considerations regarding the mechanical strength of the interacting components as well as the influence of the possible geometrical unevennes of the system that can arise during the fuel element lifetime. (Cali', G.P.)

Mitigation of end flux peaking in CANDU fuel bundles using neutron absorbers

Energy Technology Data Exchange (ETDEWEB)

Pierce, D.; Chan, P.K., E-mail: dylan.pierce@rmc.ca [Royal Military College of Canada, Kingston ON, (Canada); Shen, W. [Canadian Nuclear Safety Commission, Ottawa ON, (Canada)

2015-07-01

End flux peaking (EFP) is a phenomenon where a region of elevated neutron flux occurs between two adjoining fuel bundles. These peaks lead to an increase in fission rate and therefore greater heat generation. It is known that addition of neutron absorbers into fuel bundles can help mitigate EFP, yet implementation in Canada Deuterium Uranium (CANDU) type reactors using natural uranium fuel has not been pursued. Monte Carlo N-Particle code (MCNP) 6.1 was used to simulate the addition of a small amount of neutron absorbers strategically within the fuel pellets. This paper will present some preliminary results collected thus far. (author)

Electrometallurgical treatment of aluminum-matrix fuels

International Nuclear Information System (INIS)

Willit, J.L.; Gay, E.C.; Miller, W.E.; McPheeters, C.C.; Laidler, J.J.

1996-01-01

The electrometallurgical treatment process described in this paper builds on our experience in treating spent fuel from the Experimental Breeder Reactor (EBR-II). The work is also to some degree, a spin-off from applying electrometallurgical treatment to spent fuel from the Hanford single pass reactors (SPRs) and fuel and flush salt from the Molten Salt Reactor Experiment (MSRE) in treating EBR-II fuel, we recover the actinides from a uranium-zirconium fuel by electrorefining the uranium out of the chopped fuel. With SPR fuel, uranium is electrorefined out of the aluminum cladding. Both of these processes are conducted in a LiCl-KCl molten-salt electrolyte. In the case of the MSRE, which used a fluoride salt-based fuel, uranium in this salt is recovered through a series of electrochemical reductions. Recovering high-purity uranium from an aluminum-matrix fuel is more challenging than treating SPR or EBR-II fuel because the aluminum- matrix fuel is typically -90% (volume basis) aluminum

End points and assessments in esthetic dental treatment.

Science.gov (United States)

Ishida, Yuichi; Fujimoto, Keiko; Higaki, Nobuaki; Goto, Takaharu; Ichikawa, Tetsuo

2015-10-01

There are two key considerations for successful esthetic dental treatments. This article systematically describes the two key considerations: the end points of esthetic dental treatments and assessments of esthetic outcomes, which are also important for acquiring clinical skill in esthetic dental treatments. The end point and assessment of esthetic dental treatment were discussed through literature reviews and clinical practices. Before designing a treatment plan, the end point of dental treatment should be established. The section entitled "End point of esthetic dental treatment" discusses treatments for maxillary anterior teeth and the restoration of facial profile with prostheses. The process of assessing treatment outcomes entitled "Assessments of esthetic dental treatment" discusses objective and subjective evaluation methods. Practitioners should reach an agreement regarding desired end points with patients through medical interviews, and continuing improvements and developments of esthetic assessments are required to raise the therapeutic level of esthetic dental treatments. Copyright © 2015 Japan Prosthodontic Society. Published by Elsevier Ltd. All rights reserved.

MCNP Simulations of End Flux Peaking in ACR-1000, 2.4 wt % {sup 235}U Fuel Bundles

Energy Technology Data Exchange (ETDEWEB)

Hill, Ian; Donnelly, Jim [Atomic Energy of Canada Limited (AECL), 2251 Speakman Drive, Mississauga, ON, L5K 1B2 (Canada)

2008-07-01

This paper examines the end flux peaking in ACR-1000 fuel bundles. Reactor physics simulations are performed with MCNP to assess the steady state end-flux peaking in an infinite lattice of ACR fuel, as well as to quantify the peaking that occurs during refuelling. 3-dimensional MCNP models are created based on the detailed geometry of the fuel bundle. Detailed position-dependent fuel compositions are obtained from MONTEBURNS which couples MCNP and ORIGIN2.2. Axial and radial power profiles are obtained for both fresh and mid-burnup fuel bundles in an infinite lattice. Subsequently an assessment of the impact of a refuelling transient on the power profiles is performed. The refuelling transient is found to increase the end flux peaking in the region adjacent to light water. (authors)

Lower end fitting debris collector and end cap spacer grid

International Nuclear Information System (INIS)

Bryan, W.J.

1990-01-01

This patent describes a nuclear reactor having fuel assemblies including an upper end fitting and spaced nuclear fuel rod spacer grids for supporting and spacing a plurality of elongated nuclear fuel rods. Each includes a hollow active portion of nuclear fuel filled cladding intermediate the rod ends and tapering end cap of solid material with a circumferential groove on the rod end which first encounters reactor coolant flow, a lower end filtering debris collector and end cap spacer grid for capturing and retaining deleterious debris carried by reactor coolant before it enters the active region of a fuel assembly and creates fuel rod cladding damage

Treatment of recurrences in head and neck cancers occurring in irradiated site

International Nuclear Information System (INIS)

Pernot, M.

1994-01-01

We'll consider as recurrences the elevate relapses occurring at least six months after the first treatment end. The recurrences however frequent it is, is bad codified and everybody does what he can in the presence of a relapse. The number of retreated lesions should be in inverse proportion of the efficiency of the initial treatment. The surgery made large progresses during these last 15 years. The external radiotherapy is seldom a very good treatment indication of head and neck cancer recurrences in previously irradiated site. Iridium 192 wires may be used as implantations with low dose rate. For the cavity proper of mouth, we have counted 159 relapses at the level of the sole primary tumour. The tonsil neoplasms are often treated by a sole external irradiation or in association with curietherapy. For a larynx neoplasm the ideal starting treatment is that one which allows to cure the tumour while protecting the speaking and the swallowing. 83 refs

Dimpled/grooved face on a fuel injection nozzle body for flame stabilization and related method

Science.gov (United States)

Uhm, Jong Ho; Johnson, Thomas Edward; Kim, Kwanwoo; Zuo, Baifang

2013-08-20

A fuel injection head for a fuel nozzle used in a gas turbine combustor includes a substantially hollow body formed with an upstream end face, a downstream end face and a peripheral wall extending therebetween. A plurality of pre-mix tubes or passages extend axially through the hollow body with inlets at the upstream end face and outlets at the downstream end face. An exterior surface of the downstream end face is formed with three-dimensional surface features that increase a total surface area of the exterior surface as compared to a substantially flat, planar downstream end face.

My fuel treatment planner: a user guide.

Science.gov (United States)

Robin L. Biesecker; Roger D. Fight

2006-01-01

My Fuel Treatment Planner (MyFTP) is a tool for calculating and displaying the financial costs and potential revenues associated with forest fuel reduction treatments. It was designed for fuel treatment planners including those with little or no background in economics, forest management, or timber sales. This guide provides the information needed to acquire, load, and...

Fuel handling grapple for nuclear reactor plants

International Nuclear Information System (INIS)

Rousar, D.L.

1992-01-01

This patent describes a fuel handling system for nuclear reactor plants. It comprises: a reactor vessel having an openable top and removable cover and containing therein, submerged in water substantially filling the reactor vessel, a fuel core including a multiplicity of fuel bundles formed of groups of sealed tube elements enclosing fissionable fuel assembled into units, the fuel handling system consisting essentially of the combination of: a fuel bundle handling platform movable over the open top of the reactor vessel; a fuel bundle handling mast extendable downward from the platform with a lower end projecting into the open top reactor vessel to the fuel core submerged in water; a grapple head mounted on the lower end of the mast provided with grapple means comprising complementary hooks which pivot inward toward each other to securely grasp a bail handle of a nuclear reactor fuel bundle and pivot backward away from each other to release a bail handle; the grapple means having a hollow cylindrical support shaft fixed within the grapple head with hollow cylindrical sleeves rotatably mounted and fixed in longitudinal axial position on the support shaft and each sleeve having complementary hooks secured thereto whereby each hook pivots with the rotation of the sleeve secured thereto; and the hollow cylindrical support shaft being provided with complementary orifices on opposite sides of its hollow cylindrical and intermediate to the sleeves mounted thereon whereby the orifices on both sides of the hollow cylindrical support shaft are vertically aligned providing a direct in-line optical viewing path downward there-through and a remote operator positioned above the grapple means can observe from overhead the area immediately below the grapple hooks

Spent fuel treatment at ANL-West

International Nuclear Information System (INIS)

Goff, K.M.; Benedict, R.W.; Levinskas, D.

1994-01-01

At Argonne National Laboratory-West (ANL-West) there are several thousand kilograms of metallic spent nuclear fuel containing bond sodium. This fuel will be treated in the Fuel Cycle Facility at ANL-West to produce stable waste forms for storage and disposal. The treatment operations will employ a pyrochemical process that also has applications for treating most of the fuel types within the Department of Energy complex. The treatment equipment is in its last stage of readiness, and operations will begin in the Fall of 1994

Survey of post-irradiation examinations made of mixed carbide fuels

International Nuclear Information System (INIS)

Coquerelle, M.

1997-01-01

Post-irradiation examinations on mixed carbide, nitride and carbonitride fuels irradiated in fast flux reactors Rapsodie and DFR were carried out during the seventies and early eighties. In this report, emphasis was put on the fission gas release, cladding carburization and head-end gaseous oxidation process of these fuels, in particular, of mixed carbides. (author). 8 refs, 16 figs, 3 tabs

Fuel cell integral bundle assembly including ceramic open end seal and vertical and horizontal thermal expansion control

Science.gov (United States)

Zafred, Paolo R [Murrysville, PA; Gillett, James E [Greensburg, PA

2012-04-24

A plurality of integral bundle assemblies contain a top portion with an inlet fuel plenum and a bottom portion containing a base support, the base supports a dense, ceramic air exhaust manifold having four supporting legs, the manifold is below and connects to air feed tubes located in a recuperator zone, the air feed tubes passing into the center of inverted, tubular, elongated, hollow electrically connected solid oxide fuel cells having an open end above a combustion zone into which the air feed tubes pass and a closed end near the inlet fuel plenum, where the open end of the fuel cells rest upon and within a separate combination ceramic seal and bundle support contained in a ceramic support casting, where at least one flexible cushion ceramic band seal located between the recuperator and fuel cells protects and controls horizontal thermal expansion, and where the fuel cells operate in the fuel cell mode and where the base support and bottom ceramic air exhaust manifolds carry from 85% to all of the weight of the generator.

Device for refueling a nuclear reactor having a core comprising a plurality of fuel assemblies

International Nuclear Information System (INIS)

Van Santen, A.; Elofsson, K.

1975-01-01

A nuclear reactor formed of fuel assemblies each including a plurality of parallel fuel rods arranged in a predetermined fuel rod lattice, which rods are freely extractable and insertable at one end of the fuel assembly, is refueled by extracting from one of the fuel assemblies a number of fuel rods substantially less than the total number of fuel rods and replacing these by inserting new fuel rods into the vacated positions. The removal and return of the rods is produced by a tool having a plurality of gripping members capable of engaging shoulders beneath heads formed on the upper ends of the fuel rods. This may be accomplished by providing a tool having a number of gripping members attached to the tool body corresponding to the lattice positions of the fuel rods to be extracted, having gripping members which can be pushed together to grip beneath shoulders on the upper ends of the fuel rods. (Official Gazette)

The strategy of the long-term back-end nuclear fuel cycle in the Czech Republic

International Nuclear Information System (INIS)

Palagyi, S.; Fajman, V.

2002-01-01

The present status of the strategy of the long-term back-end nuclear fuel cycle in the Czech Republic is briefly outlined in this paper. This strategy is based on the once-through option in the use of the nuclear fuel with subsequent interim storage of the spent fuel and its final disposal as a declared high level waste. However, other technologies for the management of the back-end of the nuclear fuel cycle are not excluded at all. Besides the first already existing and the second interim spent fuel storage facility being sited at Dukovany Nuclear Power Plant, an interim spent fuel storage facility at Temelin Nuclear Power Plant is also under the siting process. To cover the total storing needs a central spent nuclear fuel interim storage facility at Skalka in the Czech-Moravian Highlands is also under consideration. These facilities are or will be equipped with dry-storage containers of cask-type placed in the concrete building and cooled by natural air ventilation. Since 1993 there is a joint effort of several governmental organisations and institutions and private companies to study the scientific, technical and economical possibilities of the construction of the deep geological repository for spent nuclear fuel disposal. A horizontal repository facility with vertical access was selected and a reference project has been accepted. A time horizon for construction in about the year of 2035 was scheduled. The necessary legal and administrative basis of the spent fuel and radioactive waste management was laid down by the law No. 18/1997 (Atomic Act) passed in 1997. This basic law with its implementing regulations fully reflects the internationally accepted principles of the provision of nuclear safety and radiation protection in this respect and it also strongly supports the policy and strategy of the back-end of the nuclear fuel cycle. (author)

The nuclear fuel cycle

International Nuclear Information System (INIS)

Jones, P.M.S.

1987-01-01

This chapter explains the distinction between fissile and fertile materials, examines briefly the processes involved in fuel manufacture and management, describes the alternative nuclear fuel cycles and considers their advantages and disadvantages. Fuel management is usually divided into three stages; the front end stage of production and fabrication, the back end stage which deals with the fuel after it is removed from the reactor (including reprocessing and waste treatment) and the stage in between when the fuel is actually in the reactor. These stages are illustrated and explained in detail. The plutonium fuel cycle and thorium-uranium-233 fuel cycle are explained. The differences between fuels for thermal reactors and fast reactors are explained. (U.K.)

SMART instruments for radiological surveillance at the back end of nuclear fuel cycle

International Nuclear Information System (INIS)

Pendharkar, K.A.; Jauhri, G.S.; Ganesh, G.; Kulkarni, V.V.

2001-01-01

The back end of Nuclear Fuel Cycle mainly consists of Fuel Reprocessing Plant and Waste Management Plant for treatment of different types of wastes generated during processing of spent fuel. A fuel reprocessing plant handles annually several million curies of fission product activity and few hundred kg of plutonium. A Waste Management Facility associated with a reprocessing plant also handles several million curies of fission product activity. In both the plants several types of radiological measurements have to be carried out to ensure that the individual doses are well below regulatory limits and release of radioactivity to environment (through stack and through liquid effluent) is below the limit stipulated in technical specifications of the plant. The measurements comprise individual external dose, measurement of radiation level in different areas of the plant, assessment of air-borne activity due to plutonium and fission products in different areas of the plant, radioactivity release to environment through liquid effluents and through stack. In order to carry out the above mentioned measurements large number of different types of instruments are required. The existing instruments are analog instruments. These instruments have served well. However they have certain limitations with respect to flexibility and extra functionality. In this respect the 'SMART' instruments have distinct advantages. The advantages, that are offered by the 'SMART' instrument in making the radiological surveillance programme more effective, are brought out in the paper. (author)

Policy in France regarding the back-end of the fuel cycle reprocessing/recycling route

International Nuclear Information System (INIS)

Gloaguen, A.; Lenail, B.

1991-01-01

The decision taken in early 1970s to base the French power policy on the use of pressurized water reactors also included the strategy for the back end of the nuclear fuel cycle based on reprocessing, waste conditioning for the final disposal in the most suitable form in terms of safety and plutonium recycling to fast breeder reactors. Twenty years have elapsed, and substantial development and investment have been made. New evidences have emerged especially regarding breeder development, and the initial choice has been proved to be sound. EDF and COGEMA, the French utility and fuel cycle companies, respectively, are working together in order to take the best advantage of past efforts. The good behavior of MOX fuel in EDF reactors and the excellent start of the UP3 reprocessing plant of La Hague, which was completed and commissioned in August, 1990, made EDF and COGEMA extremely confident for future decision. The French choice made in favor of fuel reprocessing the history of fuel reprocessing in France, the policy concerning the back end of nuclear fuel cycle of EDF, and the present consideration and circumstances on this matter are reported. (K.I.)

[Diagnosis and treatment characteristics of head-wind sha in She medicine].

Science.gov (United States)

Zou, Guangyi; Xu, Xiangdong; Zheng, Songming; Yan, Lianhe; Lei, Houxing; Zhang, Qiao-ling; Xiang, Yingmei; Ye, Yiping; Song, Liwei

2015-03-01

The diagnosis and treatment characteristics of head-wind sha in She medicine were analyzed and summarized. By visiting She-nationality villages and towns in Zhejiang province and Fujian province and interviewing hundreds of doctors of She medicine, the sha diagnosis, sha differentiation, experience and theory of treatment were arranged, and a comprehensive summary on theory and application of head-wind sha in She medicine such as pathogeny, name of disease, mechanism, diagnosis, differential diagnosis and treatment was made. It is believed that the methods of diagnosis and treatment in She medicine for head-wind sha could effectively enhance curative effect, safety and patients' quality of life, and the further research should be carried out.

Development of end plug welding method in the fabrication of FBR fuel pins

International Nuclear Information System (INIS)

Ohtani, Seiji; Sawayama, Takeo; Tateishi, Yoshinori

1977-01-01

As a part of the development of the automatic and remote controlled fabrication of FBR fuel pins, welding of fuel pin end plugs has been examined. Cladding tubes and end plugs used for this experiment are made of SUS 316, and they are the components of fuel pins for the prototype fast breeder reactor (Monju) or the second core of Joyo (Joyo MK-II). The welding tests of cladding tubes and four kinds of end plugs were carried out by means of two techniques; tungsten inert gas welding and laser welding. It can be said that no considerable difference was observed in weld penetration, occurrence rate of weld defects and breaking strength between the tight fit and the loose fit plugs. The face-to-face fit welding requires the least welding heat input, but involves much difficulty in the control of weld penetration and bead zone diameter. The good concentrative property and high energy density of laser beam make the face of weld hollow due to the vaporization of weld metal. However, this problem can be easily solved by changing the shape of end plugs. Good results in the other characteristics of the weld also were obtained by this laser welding. Further experiment is needed in connection with the compatibility of weld metal with sodium and neutron irradiation before final judgement is made on the laser welding technique. (Nakai, Y.)

The back end of the nuclear fuel cycle: technical and economic analysis-Part 1

International Nuclear Information System (INIS)

Roglans-Ribas, J.; Spinrad, B.I.

1990-01-01

The back end of the nuclear fuel cycle has been analyzed under current conditions in the United States, taking into consideration the framework defined by the Nuclear Waste Policy Act of 1982 and its amendments. The different steps of the back end of the fuel cycle are studied and different alternatives are compared under technical and economic criteria. Several technical issues have been analyzed for their impact on the economics of the fuel cycle. The bases for the analysis are explained, and the results for a once-through cycle are presented. The results show that a repository in tuff represents the minimum cost situation. The economic model appears very sensitive to several parameters, in particular the period of retrievability and the storage costs

Winter fuels report. Week ending, January 26, 1996

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-01-23

The Winter Fuels Report is intended to provide concise, timely information to the industry, the press, policymakers, consumers analysts, and State and local governments on the following topics: (1) distillate fuel oil net production, imports and stocks on a U.S. level and for all Petroleum Administration for Defense Districts (PADD) and product supplied on a U.S. level; (2) propane net production, imports and stocks on a U.S. level and for PADD`s I, II, and III; (3) natural gas supply and disposition and underground storage for the U.S. and consumption for all PADD`s; as well as selected National average prices; (4) residential and wholesale pricing data for heating oil and propane for those States participating in the joint Energy Information Administration (EIA)/State Heating Oil and Propane Program; (5) crude oil and petroleum price comparisons for the U.S. and selected cities; and (6) a 6-10 Day and 30-Day outlook for temperature and precipitation and U.S. total heating degree-days by city. The distillate fuel oil and propane supply data are collected and published weekly. The data are based on company submissions for the week ending 7:00 a.m. for the preceding Friday. Weekly data for distillate fuel oil are also published in the Weekly Petroleum Status Report. Monthly data for distillate fuel oil and propane are published in the Petroleum Supply Monthly. The residential pricing information is collected by the EIA and the State Energy Offices on a semimonthly basis for the EIA/State Heating Oil and Propane Program. The wholesale price comparison data are collected daily and are published weekly. Residential heating fuel prices are derived from price quotes for home delivery of No. 2 fuel oil and propane. As such, they reflect prices in effect on the dates shown. Wholesale heating oil and propane prices are estimates using a sample of terminal quotes to represent average State prices on the dates given.

Electrometallurgical treatment of oxide spent fuels

International Nuclear Information System (INIS)

Karell, E. J.

1999-01-01

The Department of Energy (DOE) inventory of spent nuclear fuel contains a wide variety of oxide fuel types that may be unsuitable for direct repository disposal in their current form. The molten-salt electrometallurgical treatment technique developed by Argonne National Laboratory (ANL) has the potential to simplify preparing and qualifying these fuels for disposal by converting them into three uniform product streams: uranium metal, a metal waste form, and a ceramic waste form. This paper describes the major steps in the electrometallurgical treatment process for oxide fuels and provides the results of recent experiments performed to develop and scale up the process

Cetuximab in the treatment of head and neck cancer: preliminary results outside clinical trials

Science.gov (United States)

Dequanter, Didier; Shahla, Mohammad; Paulus, Pascal; Lothaire, Phillippe

2010-01-01

Introduction: The purpose of this study was to evaluate the clinical efficacy in our daily practice, outside clinical trials, of cetuximab plus radiotherapy in a majority of treatment-naive patients with locoregionally advanced head and neck squamous cell carcinomas. Methods: A retrospective study was performed to evaluate outcomes in patients who were treated definitively with cetuximab and radiotherapy (ExRT). Patients with stage III or IV, nonmetastatic, measurable squamous cell carcinoma of the head and neck (SCCHN) were eligible. Results: There were 18 males and two females. The median age was 61 years (range from 49 to 87 years old). Concurrent radiotherapy and cetuximab was used, in first line, in 17 patients with locally advanced disease; two patients with recurrent SCCHN, who were intolerant of Cisplatin-based regimens, were treated with radiotherapy combined with weekly cetuximab; and 1 patient received cetuximab and radiotherapy postoperatively. The median time of response was 10 months (range from 2 to 24 months). A partial response was observed in 11 cases; a complete response in nine cases. The occurrence of grade 2–3 skin toxicity was observed in 11 cases. Skin toxicity was clearly correlated with a better response and the duration of the response to the treatment. The use of cetuximab in combination with radiotherapy does not increase the side effects of radiotherapy. At the end of the follow-up, 17 patients died. Conclusion: Cetuximab, with its highly targeted mechanism of action and synergistic activity with current treatment modalities, is a valuable treatment option in head and neck patients. The effect of the epidermal growth factor receptor antagonist occurs without any change in the pattern and the severity of toxicity usually associated with head and neck radiation. Cetuximab seems not to provide the most benefit for patients with oropharyngeal cancers but will in patients with T4 tumors. However, the median duration of local control was

Cetuximab in the treatment of head and neck cancer: preliminary results outside clinical trials

International Nuclear Information System (INIS)

Dequanter, Didier; Shahla, Mohammad; Paulus, Pascal; Lothaire, Phillippe

2010-01-01

The purpose of this study was to evaluate the clinical efficacy in our daily practice, outside clinical trials, of cetuximab plus radiotherapy in a majority of treatment-naive patients with locoregionally advanced head and neck squamous cell carcinomas. A retrospective study was performed to evaluate outcomes in patients who were treated definitively with cetuximab and radiotherapy (ExRT). Patients with stage III or IV, nonmetastatic, measurable squamous cell carcinoma of the head and neck (SCCHN) were eligible. There were 18 males and two females. The median age was 61 years (range from 49 to 87 years old). Concurrent radiotherapy and cetuximab was used, in first line, in 17 patients with locally advanced disease; two patients with recurrent SCCHN, who were intolerant of Cisplatin-based regimens, were treated with radiotherapy combined with weekly cetuximab; and 1 patient received cetuximab and radiotherapy postoperatively. The median time of response was 10 months (range from 2 to 24 months). A partial response was observed in 11 cases; a complete response in nine cases. The occurrence of grade 2–3 skin toxicity was observed in 11 cases. Skin toxicity was clearly correlated with a better response and the duration of the response to the treatment. The use of cetuximab in combination with radiotherapy does not increase the side effects of radiotherapy. At the end of the follow-up, 17 patients died. Cetuximab, with its highly targeted mechanism of action and synergistic activity with current treatment modalities, is a valuable treatment option in head and neck patients. The effect of the epidermal growth factor receptor antagonist occurs without any change in the pattern and the severity of toxicity usually associated with head and neck radiation. Cetuximab seems not to provide the most benefit for patients with oropharyngeal cancers but will in patients with T4 tumors. However, the median duration of local control was less as described in the clinical trials

Spent fuel treatment in Japan

International Nuclear Information System (INIS)

Takahashi, K.

1999-01-01

In Japan, 52 nuclear power reactors are operating with a total power generation capacity of 45 GWe. The cumulative amount of spent fuel arising, as of March 1998, is about 14,700 W. Spent fuel is reprocessed and recovered nuclear materials are to be recycled in LWRs and FBRs. Pu utilization in LWRs will commence in 1999. In January 1997, short-term policy measures were announced by the Atomic Energy Commission, which addressed promotion of the reprocessing programme in Rokkasho, plutonium utilization in LWRs, spent fuel management, back-end measures and FBR development. With regard to the spent fuel management, the policy measures included expansion of spent fuel storage capacity at reactor sites and a study on spent fuel storage away-from-reactor sites, considering the increasing amount of spent fuel arising. Valuable experience was been accumulated at the Tokai Reprocessing Plant (TRP), from the start of hot operation in 1977 up to now. The role of the TRP will be changed from an operation-oriented to a more R and D oriented facility, when PNC is reorganized into the new organization JNC. The Rokkasho reprocessing plant is under construction and is expected to commence operation in 2003. R and D of future recycling technologies is also continued for the establishment of a nuclear fuel cycle based on FBRs and LWRs. (author)

Role of awareness in head-neck acceleration in low velocity rear-end impacts.

Science.gov (United States)

Kumar, S; Narayan, Y; Amell, T

2000-03-01

Fourteen normal healthy seated and restrained young adults were delivered rear-end impacts of four intensities of acceleration. The chair was delivered a regulated and controlled pneumatic blow using a 30 cm cylinder to cause an acceleration of 0.5, 0.9, 1.1 and 1.4g. The accelerated chair was stopped suddenly by impacting the stopper at the other end of the 2 m long friction reduced track. In one set of trials, subjects were informed about the impending impact and in the other they were blindfolded and provided with loud auditory input to eliminate cues of the impact. The accelerations of the chair, shoulder and head of the participating subjects were measured triaxially and compared between levels of acceleration and expectation. The multiple analyses of variance revealed that the peak acceleration was significantly affected by the gender (P < 0.01), intensity of impact (P < 0.001), and expectation (P < 0.0001). The accelerations were significantly different in different axes (P < 0.001). A significant two-way interaction between acceleration and expectation (P < 0.03), and expectation and axes of acceleration (P < 0.02) would imply that awareness of the impending impact serves to significantly reduce the level of accelerations of head and neck.

Mobile Melt-Dilute Treatment for Russian Spent Nuclear Fuel

International Nuclear Information System (INIS)

Peacock, H.

2002-01-01

Treatment of spent Russian fuel using a Melt-Dilute (MD) process is proposed to consolidate fuel assemblies into a form that is proliferation resistant and provides critically safety under storage and disposal configurations. Russian fuel elements contain a variety of fuel meat and cladding materials. The Melt-Dilute treatment process was initially developed for aluminum-based fuels so additional development is needed for several cladding and fuel meat combinations in the Russian fuel inventory (e.g. zirconium-clad, uranium-zirconium alloy fuel). A Mobile Melt-Dilute facility (MMD) is being proposed for treatment of spent fuels at reactor site storage locations in Russia; thereby, avoiding the costs of building separate treatment facilities at each site and avoiding shipment of enriched fuel assemblies over the road. The MMD facility concept is based on laboratory tests conducted at the Savannah River Technology Center (SRTC), and modular pilot-scale facilities constructed at the Savannah River Site for treatment of US spent fuel. SRTC laboratory tests have shown the feasibility of operating a Melt-Dilute treatment process with either a closed system or a filtered off-gas system. The proposed Mobile Melt-Dilute process is presented in this paper

Exergy and environmental comparison of the end use of vehicle fuels: The Brazilian case

International Nuclear Information System (INIS)

Flórez-Orrego, Daniel; Silva, Julio A.M.; Oliveira Jr, Silvio de

2015-01-01

Highlights: • Total and non-renewable exergy costs of Brazilian transportation service are evaluated. • Specific CO 2 emissions of the Brazilian transportation service are determined. • Overall exergy efficiency of the end use of vehicle fuels in transportation sector is calculated. • A comparative extended analysis of the production and end use of transportation fuels is presented. - Abstract: In this work, a comparative exergy and environmental analysis of the vehicle fuel end use is presented. This analysis comprises petroleum and natural gas derivatives (including hydrogen), biofuels (ethanol and biodiesel), and their mixtures, besides of the electricity generated in the Brazilian electricity mix, intended to be used in plug in electric vehicles. The renewable and non-renewable unit exergy costs and CO 2 emission cost are proposed as suitable indicators for assessing the renewable exergy consumption intensity and the environmental impact, and for quantifying the thermodynamic performance of the transportation sector. This allows ranking the energy conversion processes along the vehicle fuels production routes and their end use, so that the best options for the transportation sector can be determined and better energy policies may be issued. It is found that if a drastic CO 2 emissions abatement of the sector is pursued, a more intensive utilization of ethanol in the Brazilian transportation sector mix is advisable. However, as the overall exergy conversion efficiency of the sugar cane industry is still very low, which increases the unit exergy cost of ethanol, better production and end use technologies are required. Nonetheless, with the current scenario of a predominantly renewable Brazilian electricity mix, based on more than 80% of renewable sources, this source consolidates as the most promising energy source to reduce the large amount of greenhouse gas emissions which transportation sector is responsible for

R and D for back-end options for irradiated research reactor fuel in Germany

International Nuclear Information System (INIS)

Bruecher, H.; Curtius, H.; Fachinger, J.

2001-01-01

Out of 11.5 t of irradiated fuel arising from German research reactors until the end of this decade, 3.9 t are intended to be returned to the USA, and 2.3 t are expected to be recycled for reuse of uranium. The remaining 5.3 t, as well as the fuel irradiated after the year 2010, will have to follow the domestic back-end option of extended dry interim storage in Castor-type casks, followed by disposal in a deep geological repository. R and D is going on in the Research Centre Juelich to investigate the long-term behaviour of U-Al based fuel in a salt repository. First results from leaching experiments show I) a fast dissolution of the fuel with mobilization of its radionuclide inventory, and 2) the following formation of amorphous Al-Mg-hydroxide phases. Long-lived actinides from the fuel were shown to be fixed in these phases and hence immobilized. Future R and D will be to investigate the nature and stability of these phases for long-term safety assessments. Investigations will have to be extended to cover alternative disposal sites (granite clay) as well as different (e.g. silicon based) fuels. (author)

Factors determining the long term back end nuclear fuel cycle strategy and future nuclear systems. Proceedings of a technical committee meeting

International Nuclear Information System (INIS)

2002-05-01

The Technical Committee Meeting (TCM) was held in Vienna on 8-10 November 1999; it was organized by the International Atomic Energy Agency and attended by 26 participants from 16 Member States. The purpose of the meeting was to exchange information among experts on the back end fuel cycle strategies adopted by Member States; to identify key factors determining the long-term back end fuel cycle strategies; and to assess the applicability of these factors to future nuclear systems. Issues associated with the back end fuel cycle supporting a country's nuclear power programme are technical, economic, institutional and political. This TCM provided an opportunity to address these issues and their impacts to the back end fuel cycles, as well as to identify and assess factors affecting the back end fuel cycle strategies. The discussion was organized ib the following topical sessions: the nuclear fuel cycle; spent fuel management; waste management and repository; plutonium management. This document contains a summary of the meeting and 22 individual papers presented by participants. Each of the papers was indexed separately

Factors determining the long term back end nuclear fuel cycle strategy and future nuclear systems. Proceedings of a technical committee meeting

Energy Technology Data Exchange (ETDEWEB)

NONE

2002-05-01

The Technical Committee Meeting (TCM) was held in Vienna on 8-10 November 1999; it was organized by the International Atomic Energy Agency and attended by 26 participants from 16 Member States. The purpose of the meeting was to exchange information among experts on the back end fuel cycle strategies adopted by Member States; to identify key factors determining the long-term back end fuel cycle strategies; and to assess the applicability of these factors to future nuclear systems. Issues associated with the back end fuel cycle supporting a country's nuclear power programme are technical, economic, institutional and political. This TCM provided an opportunity to address these issues and their impacts to the back end fuel cycles, as well as to identify and assess factors affecting the back end fuel cycle strategies. The discussion was organized ib the following topical sessions: the nuclear fuel cycle; spent fuel management; waste management and repository; plutonium management. This document contains a summary of the meeting and 22 individual papers presented by participants. Each of the papers was indexed separately.

An end-to-end assessment of range uncertainty in proton therapy using animal tissues

Science.gov (United States)

Zheng, Yuanshui; Kang, Yixiu; Zeidan, Omar; Schreuder, Niek

2016-11-01

Accurate assessment of range uncertainty is critical in proton therapy. However, there is a lack of data and consensus on how to evaluate the appropriate amount of uncertainty. The purpose of this study is to quantify the range uncertainty in various treatment conditions in proton therapy, using transmission measurements through various animal tissues. Animal tissues, including a pig head, beef steak, and lamb leg, were used in this study. For each tissue, an end-to-end test closely imitating patient treatments was performed. This included CT scan simulation, treatment planning, image-guided alignment, and beam delivery. Radio-chromic films were placed at various depths in the distal dose falloff region to measure depth dose. Comparisons between measured and calculated doses were used to evaluate range differences. The dose difference at the distal falloff between measurement and calculation depends on tissue type and treatment conditions. The estimated range difference was up to 5, 6 and 4 mm for the pig head, beef steak, and lamb leg irradiation, respectively. Our study shows that the TPS was able to calculate proton range within about 1.5% plus 1.5 mm. Accurate assessment of range uncertainty in treatment planning would allow better optimization of proton beam treatment, thus fully achieving proton beams’ superior dose advantage over conventional photon-based radiation therapy.

Post-irradiation examination of Oconee 1 fuel: end-of-cycle 2 nondestructive test phase

International Nuclear Information System (INIS)

1979-11-01

Standard B and W Mark B (15 x 15) pressurized water reactor fuel assemblies were nondestructively examined at the end of the second cycle of Oconee 1 reactor operation. Burnups of the 16 fuel assemblies examined ranged from 13,100 to 20,000 MWd/mtU. The examinations were conducted in the Oconee 1 and 2 spent fuel storage pool using the installed underwater test equipment. Data obtained included fuel rod and fuel assembly dimensions, water channel spacings, holddown spring forces, fuel rod crud characteristics, and fuel column axial gap and stack lengths. Visual examinations revealed no evidence of significant rod bowing, cladding deformation, cocked grids, or rod defects. The results, summarized in this report, indicate that the assemblies performed well through two cycles of reactor operation

Radiotherapy in head and neck: a standard treatment?

International Nuclear Information System (INIS)

Santini Blasco, A; Torres Lopez, M; Apardian Manougian, R

1998-01-01

The present work is an exhaustive revision of the literature regarding the employment of combined treatments of radiochemotherapy in the head and neck neoplasms. The sanitary importance of this group of illnesses starts to become remarkable not only due to their frequency but for the high percentage of patients that present themselves for consultation with an advanced illness where the results of the classic treatments of surgery and radiotherapy are discouraging. These results are poor for the survival as well as in the quality of this. It analyzes the role of the different pharmaceuticals used in patients as well as the fundamentally different associations with radiotherapy: neoadjuvant, adjuvant and concomitant. These results allow to affirm that this treatment form is elected for those patients with advanced tumors of head and neck with a general state that allows to tolerate a bigger toxicity [es

Fuel accumulation and forest structure change following hazardous fuel reduction treatments throughout California

Science.gov (United States)

Nicole M. Vaillant; Erin K. Noonan-Wright; Alicia L. Reiner; Carol M. Ewell; Benjamin M. Rau; Josephine A. Fites-Kaufman; Scott N. Dailey

2015-01-01

Altered fuel conditions coupled with changing climate have disrupted fire regimes of forests historically characterised by high-frequency and low-to-moderate-severity fire. Managers use fuel treatments to abate undesirable fire behaviour and effects. Short-term effectiveness of fuel treatments to alter fire behaviour and effects is well documented; however, long-term...

HTGR fuel reprocessing pilot plant: results of the sequential equipment operation

International Nuclear Information System (INIS)

Strand, J.B.; Fields, D.E.; Kergis, C.A.

1979-05-01

The second sequential operation of the HTGR fuel reprocessing cold-dry head-end pilot plant equipment has been successfully completed. Twenty standard LHGTR fuel elements were crushed to a size suitable for combustion in a fluid bed burner. The graphite was combusted leaving a product of fissile and fertile fuel particles. These particles were separated in a pneumatic classifier. The fissile particles were fractured and reburned in a fluid bed to remove the inner carbon coatings. The remaining products are ready for dissolution and solvent extraction fuel recovery

Consolidated Reprocessing Progam. Quarterly progress report ending February 28, 1979

International Nuclear Information System (INIS)

1979-03-01

This publication continues the quarterly series presenting results of work performed under the Consolidated Reprocessing Program at General Atomic Company. Results of work on this program prior to June 1974 were included in a quarterly series on the HTGR Base Program. The work reported includes the development of unit processes and equipment for reprocessing of High-Temperature Gas-Cooled Reactor (HTGR) fuel, the design and development of an integrated pilot line to demonstrate the head end of HTGR reprocessing using unirradiated fuel materials, and design work in support of Hot Engineering Tests (HET). Work is also described on trade-off studies concerning the required design of facilities and equipment for the large-scale recycle of HTGR fuels in order to guide the development activities for HTGR fuel recycle

Nuclear fuel cycle, nuclear fuel makes the rounds: choosing a closed fuel cycle, nuclear fuel cycle processes, front-end of the fuel cycle: from crude ore to enriched uranium, back-end of the fuel cycle: the second life of nuclear fuel, and tomorrow: multiple recycling while generating increasingly less waste

International Nuclear Information System (INIS)

Philippon, Patrick

2016-01-01

France has opted for a policy of processing and recycling spent fuel. This option has already been deployed commercially since the 1990's, but will reach its full potential with the fourth generation. The CEA developed the processes in use today, and is pursuing research to improve, extend, and adapt these technologies to tomorrow's challenges. France has opted for a 'closed cycle' to recycle the reusable materials in spent fuel (uranium and plutonium) and optimise ultimate waste management. France has opted for a 'closed' nuclear fuel cycle. Spent fuel is processed to recover the reusable materials: uranium and plutonium. The remaining components (fission products and minor actinides) are the ultimate waste. This info-graphic shows the main steps in the fuel cycle currently implemented commercially in France. From the mine to the reactor, a vast industrial system ensures the conversion of uranium contained in the ore to obtain uranium oxide (UOX) fuel pellets. Selective extraction, purification, enrichment - key scientific and technical challenges for the teams in the Nuclear Energy Division (DEN). The back-end stages of the fuel cycle for recycling the reusable materials in spent fuel and conditioning the final waste-forms have reached maturity. CEA teams are pursuing their research in support of industry to optimise these processes. Multi-recycle plutonium, make even better use of uranium resources and, over the longer term, explore the possibility of transmuting the most highly radioactive waste: these are the challenges facing future nuclear systems. (authors)

Engineered safeguards system activities at Sandia Laboratories for back-end fuel cycle facilities

International Nuclear Information System (INIS)

Sellers, T.A.; Fienning, W.C.; Winblad, A.E.

1978-01-01

Sandia Laboratories have been developing concepts for safeguards systems to protect facilities in the back-end of the nuclear fuel cycle against potential threats of sabotage and theft of special nuclear material (SNM). Conceptual designs for Engineered Safeguards Systems (ESSs) have been developed for a Fuel Reprocessing Facility (including chemical separations, plutonium conversion, and waste solidification), a Mixed-Oxide Fuel Fabrication Facility, and a Plutonium Transport Vehicle. Performance criteria for the various elements of these systems and a candidate systematic design approach have been defined. In addition, a conceptual layout for a large-scale Fuel-Cycle Plutonium Storage Facility has been completed. Work is continuing to develop safeguards systems for spent fuel facilities, light-water reactors, alternative fuel cycles, and improved transportation systems. Additional emphasis will be placed on the problems associated with national diversion of special nuclear material. The impact on safeguards element performance criteria for surveillance and containment to protect against national diversion in various alternative fuel cycle complexes is also being investigated

Brachytherapy for head and neck cancer. Treatment results and future prospect

International Nuclear Information System (INIS)

Shibuya, Hitoshi; Yoshimura, Ro-ichi; Miura, Masahiko; Ayukawa, Fumio; Watanabe, Hiroshi

2005-01-01

Following the increasing desire of many patients to keep the form and function of speech and swallowing, interstitial brachytherapy has become the main treatment for head and neck cancer. In addition, aged and physically handicapped patients who are refused general anesthesia have come to be referred to our clinic to receive less invasive and curative treatment. In the field of brachytherapy for head and neck cancers, less complicated and more superior treatment results have been achieved following the introduction of spacers, computer dosimetry and so on. As a result of these efforts, treatment results have come to fulfill the desire of patients and their families. During the past 43 years from 1962 to 2005, we have treated over 2, 100 patients of head and neck cancer including 850 with stage I·II oral tongue carcinoma by brachytherapy and acquired a lot of important and precious data including the treatment results, multiple primary cancers as well as radiation-induced cancers. (author)

Flowsheet for shear/leach processing of N Reactor fuel at PUREX

International Nuclear Information System (INIS)

Enghusen, M.B.

1995-01-01

This document was originally prepared to support the restart of the PUREX plant using a new Shear/Leach head end process. However, the PUREX facility was shutdown and processing of the remaining N Reactor fuel is no longer considered an alternative for fuel disposition. This document is being issued for reference only to document the activities which were investigated to incorporate the shear/leach process in the PUREX plant

Prospect of spent fuel reprocessing and back-end cycling in China in 1990's

International Nuclear Information System (INIS)

Ke Youzhi; Wang Rengtao

1987-01-01

According to the CHinese Program of nuclear energy in 1990's, the amount of spent fuel by the year 2000 is estimated in this paper. Reprocessing is considered as an important link in the back-end fuel cycle. A pilot plant is scheduled for hot start up in 1996. The main goal of the study is LWR spent fuel reprocessing. We will use the experience gained from reprocessing of production reactor fuel and last research results. The advanced foreign technigue and experience will be introduced. The study emphasizes on the test of technology, equipments, instrumentation and automation, development of remote maintenance and decontamination. China will start to demonstrate the way for fuel cycle. (author)

On the problems of the fuel cycles of nuclear fuels

International Nuclear Information System (INIS)

Schmidt-Kuester, W.J.; Wagner, H.F.

1976-01-01

A secured procurement with nuclear energy can be only achieved if a completely closed fuel cycle will be established. In the Federal Republic of Germany efforts are concentrated on the front end as well as on the back end of the fuel cycle. At the front end the main tasks are to secure uranium supply and to establish the necessary enrichment capacity. The German concept for the back end of the fuel cycle will provide for an integrated and co-located system for all necessary facilities including reprocessing, plutonium fuel fabrication, treatment, interim storage and final disposal of the radioactive wastes to be operational in the mid-80's. Responsibilities for establishing this system are shared between government and private industry. Government will provide for final waste disposal, industry will built and operate the other facilities. Another important point for the introduction of nuclear energy is to solve reliably the problems of protection of fissionable material, radioactive waste and nuclear facilities. German government has initiated respective activities and has started appropriate R+D-work. (orig.) [de

Fuel rod end plug

International Nuclear Information System (INIS)

McGeary, R.K.; Bucher, G.D.

1989-01-01

This patent describes an end plug for welded disposition within the end of a tube. It comprises a circumferentially extending, axially oriented land surface, having a radial extent defined by means of a first predetermined dimension, for disposition within the end of the tube; a circumferentially extending, axially oriented land surface, having a radial extent defined by means of a second predetermined dimension which is greater than the first predetermined dimension, for disposition outside of the end of the tube. The second land surface being disposed upstream of the first land surface; an annularly extending, radially oriented shoulder portion, defined at the downstream end of the second land surface and having a radially inward depth which is greater than the difference defined between the first and second radial dimensions of the first and second land surfaces, for engaging the end of the tube in a butt contact fashion; and annular groove means defined between the upstream end of the first land surface and the shoulder portion of the end plug, for eliminating porosity defects normally developed within a weldment defined between the tube end and the end plug when the end plug is welded within the tube end, and including a conical surface which extends radially outwardly from the innermost radial depth extent of the shoulder portion to the upstream end of the first land surface

Applications of liquid phase chromatographies for the analysis of streams arising at the back end of nuclear fuel cycle

International Nuclear Information System (INIS)

Deshingkar, D.S.; Yalmali, Vrunda S.; Wattal, P.K.

2000-06-01

India has opted for a closed fuel cycle comprising of reprocessing and recycling technology. The back end of such nuclear fuel cycle involves the reprocessing of spent nuclear fuels for recovery of plutonium and depleted uranium by Purex technology. Wastes arising from the reprocessing plant are classified as high, intermediate and low level wastes (HLW, ILW, LLW). HLW is mixture of over 50 elements present in different chemical forms. The accurate analyses of dissolver solution and HLW are the most challenging but essential tasks for reprocessing plant operations and also for further development of treatment methods. Inductively coupled plasma - atomic emission spectroscopy and atomic absorption spectroscopy techniques are suitable for analysis of metallic anions. Ion chromatography has proven capability to analyse number of cations or anions at ppm or even ppb level in single run. The report reviews the literature regarding the title subject. To assess the technical feasibility of ion chromatography for waste analysis, a simulated PHWR-HLW analogue was prepared. The PHWR-HLW analogue and ground water samples were analysed on DIONEX-DX 500 and Metrohm IC. Results obtained clearly demonstrated the usefulness of ion chromatography as vital analytical tool. HLW and other process or waste streams arising at the back end of nuclear fuel cycle can be analysed for alkali, alkaline earth, rare earth and transition metal cations and important anions. Use of fraction collector along with ion chromatography can enhance it's sensitivity to few Bq/ml for radioactive samples. (author)

Long head of biceps: from anatomy to treatment

Directory of Open Access Journals (Sweden)

Marco Sarmento

2015-01-01

Full Text Available The long head of the biceps (LHB, tendinous structure of the proximal brachial biceps, has its well-known anatomy, which contrasts with its current functional characterization. Various forms of proximal anchor and intra–articular route, important for the correct interpretation of its contribution to the pathology of the shoulder as well as the treatment methodology, are described. Knowledge of its biomechanics results mainly from cadaveric studies that contradict each other. Already the few studies in vivo indicate a depressant and stabilizing action, anterior, for the humeral head. Its pathology is rarely isolated because it is almost always correlated with rotator cuff or labrum pathology. It can be divided into 3 major groups (inflammatory, instability and traumatic and subdivided according to its location. The anterior shoulder pain is the initial symptom of pathology of LHB Its perfect characterization is dependent on the associated injuries. Clinical tests are multiple and only their combination allows better sensitivity and specificity for LHB pathology. The arthro-MRI and dynamic ultrasound are able to increase proper diagnostic of the pathology of LHB. Treatment ranges from conservative and surgical. The latter includes the repair, tenotomy and tenodesis of LHB which can be performed by open or arthroscopic methodology. The author intends to review existing literature on all aspects related to the long head of the biceps from anatomy to treatment, presenting the latest results.

Fuel Chemistry Division annual progress report for 1989

International Nuclear Information System (INIS)

Singh Mudher, K.D.

1993-01-01

The progress report gives a brief description of the various activities of the Fuel Chemistry Division of Bhabha Atomic Research Centre, Bombay for the year 1989. The descriptions of activities are arranged under the headings: Fuel Development Chemistry, Chemical Quality Control, Chemistry of Actinides, Sol-Gel process for the non Nuclear Ceramics and Studies related to Nuclear Material Accounting.At the end of the report, a list of papers published in journals and presented at various conferences/symposia is also given. (author). 69 tabs., 6 figs

Premixer assembly for mixing air and fuel for combustion

Science.gov (United States)

York, William David; Johnson, Thomas Edward; Keener, Christopher Paul

2016-12-13

A premixer assembly for mixing air and fuel for combustion includes a plurality of tubes disposed at a head end of a combustor assembly. Also included is a tube of the plurality of tubes, the tube including an inlet end and an outlet end. Further included is at least one non-circular portion of the tube extending along a length of the tube, the at least one non-circular portion having a non-circular cross-section, and the tube having a substantially constant cross-sectional area along its length

Polyvalent fuel treatment facility (TCP): shearing and dissolution of used fuel at La Hague facility

Energy Technology Data Exchange (ETDEWEB)

Brueziere, J.; Tribout-Maurizi, A.; Durand, L.; Bertrand, N. [Recycling Business Unit, AREVA, 1 place de la coupole, 92084 Paris La defense Cedex (France)

2013-07-01

Although many used nuclear fuel types have already been recycled, recycling plants are generally optimized for Light Water Reactor (LWR) UO{sub x} fuel. Benefits of used fuel recycling are consequently restricted to those fuels, with only limited capacity for the others like LWR MOX, Fast Reactor (FR) MOX or Research and Test Reactor (RTR) fuel. In order to recycle diverse fuel types, an innovative and polyvalent shearing and dissolving cell is planned to be put in operation in about 10 years at AREVA's La Hague recycling plant. This installation, called TCP (French acronym for polyvalent fuel treatment) will benefit from AREVA's industrial feedback, while taking part in the next steps towards a fast reactor fuel cycle development using innovative treatment solutions. Feasibility studies and R/Development trials on dissolution and shearing are currently ongoing. This new installation will allow AREVA to propose new services to its customers, in particular in term of MOX fuel, Research Test Reactors fuel and Fast Reactor fuel treatment. (authors)

Fuels planning: science synthesis and integration; economic uses fact sheet 04: My Fuel Treatment Planner

Science.gov (United States)

Rocky Mountain Research Station USDA Forest Service

2004-01-01

In the face of rapidly changing public and political attitudes toward fire and fuel planning, one thing remains constant: the fuel planner is ultimately responsible for making decisions on the land. This fact sheet discusses the options for fuel treatments, and the need, development, and use of the MS Excel-based tool, My Fuel Treatment Planner.

Experiments on simulation of coolant mixing in fuel assembly head and core exit channel of WWER-440 reactor

International Nuclear Information System (INIS)

Kobzar, L.L; Oleksyuk, D.A.

2006-01-01

RRC 'Kurchatov Institute' has performed coolant mixing investigation in a head of a full-size simulator of WWER-440 fuel assembly. The experiments were focused on obtaining the data important for investigating the trends in temperature difference between the value registered by a ICIS thermocouple and the value of average temperature. The completed experiments ensure representative of configuration simulation by reproducing every construction peculiar feature of flow part of fuel assembly in the domain between the lower spacing grid and thermocouple location, and also by slightly modified fuel assembly regular elements (or analogues thereof). For the purpose of effectiveness of coolant mixing assessment within the head cross section of FA simulator, we measured coolant temperature distribution both in the place where coolant flow leaves the rod bundle simulator (in 39 data points along the cross section) and in the cross section location of regular ICIS thermocouple simulator (30 data points). The testing was conducted with pressure of (90 - 95) bar, mass coolant flow rates up to 2000 kg/(m 2 .s), temperature of coolant heating in 'hot' parts of the bundle up to 35.. and differences between coolant temperature extremes measured in rod bundle simulator outlet up to 20... Temperature fields were registered in 63 conditions that differ in coolant flow and inlet coolant temperature, electrical heating rate of FA simulator, and radial coolant distribution. In certain registered conditions we simulated coolant leakage to the space between the fuel assemblies. The received test data may be important both for investigation of dependencies between the coolant temperature in regular thermocouple location or average outlet temperature in assembly head, and for validation of CFD codes or subchannel codes (Authors)

Economics of the back-end of fuel cycle: Controversy, uncertainties and the industrial evidence

International Nuclear Information System (INIS)

Guais, J.C.

1987-01-01

This paper underlines the usefulness of the document issued by OECD/NEA on the ''economics of the nuclear fuel cycle,'' as a reference methodology. As regards the technical and costs assumptions, we feel that COGEMA as the most important reprocessor to date has accumulated a large industrial experience allowing a better knowledge of the various costs included in the back-end operations, from spent fuel transportation handling and storage, to reprocessing and wastes conditioning. A comparative analysis of the two main options for the fuel cycle: reprocessing/recycling versus once-through, is performed on these grounds. In the economic conditions prevailing in Western Europe and in Japan, the resulting cost comparison is in favor of the reprocessing/recycling cycle. The authors conclude that economics is important as it is, is not the only criteria to be considered then assessing the back-end options: overall strategy, energy policy, environmental consideration and public acceptance are the other view-points to use to reach a sound decision in this field

Brachytherapy in the treatment of head and neck cancer

International Nuclear Information System (INIS)

Yoo, Seong Yul

1999-01-01

Brachytherapy has been proved to be an effective method for the purpose of increasing radiation dose to the tumor and reducing the dose to the surrounding normal tissue. In head and neck cancer, the rationale of brachytherapy is as follows; Firstly, early small lesion is radiocurative and the major cause of failure is local recurrence. Secondly, it can diminish evidently the dose to the normal tissue especially masseteric muscle and salivary gland. Thirdly, the anatomy of head and neck is suitable to various technique of brachytherapy. On background of accumulated experience of LDR iridium brachytherapy of head and neck cancer for the last 15 years, the author reviewed the history of radioisotope therapy, the characteristics of radionuclides, and some important things in the method, clinical technique and treatment planning. The author analyzed the clinical result of 185 cases of head and neck cancer treated in the Korea Cancer Center Hospital. Finally the future prospect of brachytherapy of head and neck cancer is discussed

European Research on Electrochemotherapy in Head and Neck Cancer (EURECA) project

DEFF Research Database (Denmark)

Plaschke, Christina Caroline; Bertino, Giulia; McCaul, James A.

2017-01-01

Aim Electrochemotherapy is an effective local treatment for cutaneous tumours and metastases. In this prospective trial, six European institutions investigated electrochemotherapy in recurrent, mucosal head and neck tumours. Patient and methods Forty-three patients with recurrent mucosal head....... Primary end-point was local tumour response. Secondary end-points were safety and toxicity, overall and progression free survival, and quality-of-life. Results Thirty-seven patients were evaluable for tumour response, pain score, side-effects and quality of life questionnaires. Six patients were...

Effect of fuel treatments and backfiring on the recovery of an obligate seeder-dominated heathland

Energy Technology Data Exchange (ETDEWEB)

Fernández Filgueira, C.; Vega Hidalgo, J.A.

2016-07-01

Aim of the study: To evaluate how a plant community responded to a backfire that occurred four years after application of different types of fuel-reduction treatments. Area of study: Erica umbellata Loefl. (L.)-dominated heathland in Galicia (NW Spain). Materials and Methods: Shrub cover surveys in 16 experimental plots from 2006 to 2014. Fuel reduction treatments (prescribed burning, clearing and mastication) were applied in the spring of 2006 and the area was burned by a wildfire in the summer of 2010. Main results: Shrub total cover recovered quickly after the backfire in both the treated and untreated areas, and the pre-treatment values were reached four years after the fire. Post-wildfire resprouting species cover recovery was not affected by fuel treatments. As a contrast, Erica umbellata cover reached levels similar to those in the untreated plots only in the areas treated by prescribed burning. After the wildfire, grasses cover recovery was greater in the treated than in the untreated areas and the effect lasted until the end of the study. Research highlights: Prescribed fire and backfire was favourable for Erica umbellata regeneration compared to clearing and mastication. (Author)

Thorium utilization program. Quarterly progress report for the period ending May 31, 1977

Energy Technology Data Exchange (ETDEWEB)

1977-06-01

Results of work performed under the National HTGR Fuel Recycle Program (also known as the Thorium Utilization Program) at General Atomic Company are presented. Results of work on this program prior to June 1974 were included in a quarterly series on the HTGR Base Program. The work reported includes the development of unit processes and equipment for reprocessing of High-Temperature Gas-Cooled Reactor (HTGR) fuel, the design and development of an integrated pilot line to demonstrate the head end of HTGR reprocessing using unirradiated fuel materials, and design work in support of Hot Engineering Tests (HET). Work is also described on trade-off studies concerning the required design of facilities and equipment for the large-scale recycle of HTGR fuels in order to guide the development activities for HTGR fuel recycle.

Gripping means for fuel assemblies of nuclear reactor

International Nuclear Information System (INIS)

Batjukov, V.I.; Fadeev, A.I.; Shkhian, T.G.; Vjugov, O.N.

1980-01-01

The proposed gripping means for fuel assemblies of a nuclear reactor comprises a housing, whereupon there is movably mounted a slider provided with longitudinally extending slots to receive gripping jaws whose tails are pivotably secured to the housing of the gripping means. On one side, the end faces of the longitudinally extending slots are slanted with respect to the longitudinal axis of the gripping means and come in contact with the teeth of the gripping jaws provided on the end which is opposite to the tail, whereby the jaws open as the slider and housing of the gripping means moves relative to each other so that the teeth are received in an internal groove provided in the head of the fuel assembly

Beyond Fuel Treatment Effectiveness: Characterizing Interactions between Fire and Treatments in the US

Directory of Open Access Journals (Sweden)

Kevin Barnett

2016-10-01

Full Text Available In the United States, fuel reduction treatments are a standard land management tool to restore the structure and composition of forests that have been degraded by past management. Although treatments can have multiple purposes, their principal objective is to create landscape conditions where wildland fire can be safely managed to help achieve long-term land management goals. One critique is that fuel treatment benefits are unlikely to transpire due to the low probability that treated areas will be burned by a subsequent fire within a treatment’s lifespan, but little quantitative information exists to corroborate this argument. We summarized the frequency, extent, and geographic variation of fire and fuel treatment interactions on federal lands within the conterminous United States (CONUS. We also assessed how the encounters between fuel treatments and fires varied with treatment size, treatment age, and number of times treated. Overall, 6.8% of treatment units evaluated were encountered by a subsequent fire during the study period, though this rate varied among ecoregions across the CONUS. Larger treatment units were more likely to be encountered by a fire, and treatment units were most frequently burned within one year of the most recent treatment, the latter of which is likely because of ongoing maintenance of existing treatments. Our results highlight the need to identify and prioritize additional opportunities to reduce fuel loading and fire risk on the millions of hectares of federal lands in the CONUS that are in need of restoration.

Safety and regulatory aspects of front end facilities of nuclear fuel cycle

International Nuclear Information System (INIS)

Khan, Kirity Bhushan; Jha, S.K.; Bhasin, Vivek; Behere, P.G.

2017-01-01

Nuclear Fuels Group of BARC consists of various divisions with diverse activities but impeccable safety records. This has been made possible with strict safety culture among trained personnel across all divisions. The major activities of this group encompass the front end fuel fabrication facilities for thermal and fast reactors and post irradiation examination of fuel and structural materials. The group has been responsible for delivering departmental targets, as and when required, fulfilling all safety and security requirements. The present article covers the safety and regulatory aspects of this group with special emphasis on group safety management by the administrative/organizational control, the procedure followed for regulatory review and control which are carried out and the laid down procedures for identifying, classifying and reporting of safety related incidents. (author)

Autologous Platelet Concentrates as Treatment for Avascular Necrosis of Femoral Head in a Dog.

Science.gov (United States)

Parra, Estefanía; Vergara, Andrea; Silva, Raúl F

2017-03-01

Avascular necrosis of the femoral head is a developmental disturbance that generally affects young dogs of small breeds and produces ischemic necrosis of the femoral head resulting in an incongruous and malformed joint. The most common treatment is the excisional arthroplasty of the head and femoral neck. The aim of this study is to describe the treatment of avascular necrosis in a Yorkshire dog using intra-articular injections of autologous platelet concentrate. Evaluations were made at 0, 15, 30, 60, and 120 days of treatment, describing the following parameters: clinical gait analysis, perimetry, goniometry, and radiographic evaluations. The results obtained in this case suggest that the autologous platelet concentrate may be an alternative for the treatment of avascular necrosis of the femoral head in dogs. Copyright © 2017 Elsevier Inc. All rights reserved.

Investigation of economics of back-end nuclear fuel cycle options in the Republic of Korea based on Once-through

Energy Technology Data Exchange (ETDEWEB)

Cho, Seok-Ki; Yim, Man-Sung [Korea Advance Institute of Science and Technology, Daejeon (Korea, Republic of)

2015-05-15

The purpose of this study is to examine these questions and perform economic evaluations of various cases of Once-through back-end fuel cycles in the ROK. Therefore, the study is to support decision making in terms of how the long term spent nuclear fuel (SNF) management strategy should be developed. A spreadsheet model was developed to plan reactor construction, the interim storage and the HLW repository construction within engineered constraints, based on the estimation of the spent fuel flow and the energy supply of the nuclear power program. The model computes the back-end levelized costs for various fuel cycle choices. The scenarios assumed in the model include (1) 0 year/10year/20year of licensed operation period extension; (2) the phase-out of NPP program and the continuous use including the reunification of Korean peninsula; (3) reactor decommissioning and construction lead times - 10 years and 5 years respectively in this study; (4) geological constraints of siting for a new reactor - 38 for without the reunification and 70 for with the reunification; (5) the first initiation of reactor decommissioning and operation of HLW repository - assumed to be 2020 and 2050; and (6) capacity factor of reactor operation and the on-site wet storage pool capacity - 0.85 and 0.498 MTHM per MWe which is equivalent with APR1400. The capacity factor for PHWR reactors was assumed at 0.85 and the plan for PHWR was fixed as phase-out. The spreadsheet model conducts computation for annual expenditures of the back-end fuel cycle and calculates the levelized costs. Licensed operation period extension enhances not only economic efficiency, stable energy supply, but also reduces burden of siting for a new reactor and waste disposal. And regardless the reunification, continuous use of nuclear energy lowers the back-end fuel cycle cost. With projection that a large portion of social cost is included in the current back-end fuel cycle cost, nuclear energy likely has more competency in

Exploring the mechanisms of vehicle front-end shape on pedestrian head injuries caused by ground impact.

Science.gov (United States)

Yin, Sha; Li, Jiani; Xu, Jun

2017-09-01

In pedestrian-vehicle accidents, pedestrians typically suffer from secondary impact with the ground after the primary contact with vehicles. However, information about the fundamental mechanism of pedestrian head injury from ground impact remains minimal, thereby hindering further improvement in pedestrian safety. This study addresses this issue by using multi-body modeling and computation to investigate the influence of vehicle front-end shape on pedestrian safety. Accordingly, a simulation matrix is constructed to vary bonnet leading-edge height, bonnet length, bonnet angle, and windshield angle. Subsequently, a set of 315 pedestrian-vehicle crash simulations are conducted using the multi-body simulation software MADYMO. Three vehicle velocities, i.e., 20, 30, and 40km/h, are set as the scenarios. Results show that the top governing factor is bonnet leading-edge height. The posture and head injury at the instant of head ground impact vary dramatically with increasing height because of the significant rise of the body bending point and the movement of the collision point. The bonnet angle is the second dominant factor that affects head-ground injury, followed by bonnet length and windshield angle. The results may elucidate one of the critical barriers to understanding head injury caused by ground impact and provide a solid theoretical guideline for considering pedestrian safety in vehicle design. Copyright © 2017 Elsevier Ltd. All rights reserved.

Multilateral approach to the back end of the nuclear fuel cycle in Asia-Pacific?

International Nuclear Information System (INIS)

Lim, Eunjung

2016-01-01

In spite of the nearly unprecedented scale of the Fukushima Daiichi Nuclear Accident which caused countries around the world to review their nuclear power systems and to rethink their nuclear power expansion plans, nuclear power capacity continues to grow, spearheaded by the Asia-Pacific region. The Asia-Pacific has become a major emerging market for nuclear energy industry, which indicates that the management of spent nuclear fuel is likely to be a nuisance for the countries in this region in the coming decades. By reviewing the history of discussions on multilateral approaches to the back end of the nuclear fuel cycle and examining relevant empirical cases, this article aims to explore the feasibility of a multilateral approach to the back end of the nuclear fuel cycle in this region and provide some policy suggestions to enhance nuclear governance in the Asia-Pacific. - Highlights: • The Asia-Pacific has become a huge emerging market for nuclear power industry. • Asian-Pacific countries operating reactors lack solution for spent nuclear fuel. • Multilateral approach is attractive, but hard to be realized. • The main obstacle is variations in policies for SNF management among the Asia-Pacific countries. • The country that should take its initiative in this field is the United States.

Experimental investigation of power peak in vicinity of WWER-440 control rod at end of fuel cycle

International Nuclear Information System (INIS)

Mikus, J.

2004-01-01

This paper presents some results of the axial power (fission density) distribution measurements carried out on the light-water, zero-power reactor LR-0 in a WWER-440 type core in vicinity of the WWER-440 control rod model at zero boron concentration in moderator, modelling the conditions at the end of the WWER-440 fuel cycle. Further information concerns the control rod model description, specification of the LR-0 core, fuel assemblies and measurement conditions. The aim of performed experiment is enlargement of the available power peaking database to enable the validation of the calculation codes by means of the measured data that correspond to the end of WWER-440 fuel cycle. (author)

Internationalization of the back end of the nuclear fuel cycle: Problems and prospects

International Nuclear Information System (INIS)

Haeckel, E.

1997-01-01

International cooperation and transnational division of labour is a distinctive feature of the nuclear industry, but it is conspicuously lacking at the back end of the nuclear fuel cycle. Meanwhile, national efforts to close the fuel cycle have remained largely unsuccessful. Governments and the nuclear industry are paralyzed in a gridlock of indecision and obstruction. This pattern has been reinforced at the international level. More recently, however, a number of dynamic challenges to governments and the industry has opened up new prospects for internationalization. (author)

Internationalization of the back end of the nuclear fuel cycle: Problems and prospects

Energy Technology Data Exchange (ETDEWEB)

Haeckel, E [Forschunginstitut der Deutschen Gesellschaft fuer Auswaertige Politik, Bonn (Germany)

1997-12-01

International cooperation and transnational division of labour is a distinctive feature of the nuclear industry, but it is conspicuously lacking at the back end of the nuclear fuel cycle. Meanwhile, national efforts to close the fuel cycle have remained largely unsuccessful. Governments and the nuclear industry are paralyzed in a gridlock of indecision and obstruction. This pattern has been reinforced at the international level. More recently, however, a number of dynamic challenges to governments and the industry has opened up new prospects for internationalization. (author). 3 refs.

Electrochemical reduction of CerMet fuels for transmutation using surrogate CeO2-Mo pellets

Science.gov (United States)

Claux, B.; Souček, P.; Malmbeck, R.; Rodrigues, A.; Glatz, J.-P.

2017-08-01

One of the concepts chosen for the transmutation of minor actinides in Accelerator Driven Systems or fast reactors proposes the use of fuels and targets containing minor actinides oxides embedded in an inert matrix either composed of molybdenum metal (CerMet fuel) or of ceramic magnesium oxide (CerCer fuel). Since the sufficient transmutation cannot be achieved in a single step, it requires multi-recycling of the fuel including recovery of the not transmuted minor actinides. In the present work, a pyrochemical process for treatment of Mo metal inert matrix based CerMet fuels is studied, particularly the electroreduction in molten chloride salt as a head-end step required prior the main separation process. At the initial stage, different inactive pellets simulating the fuel containing CeO2 as minor actinide surrogates were examined. The main studied parameters of the process efficiency were the porosity and composition of the pellets and the process parameters as current density and passed charge. The results indicated the feasibility of the process, gave insight into its limiting parameters and defined the parameters for the future experiment on minor actinide containing material.

Summary of cost projection for regulatory uncertainties in the back end of the fuel cycle

International Nuclear Information System (INIS)

Raudenbush, M.H.; Geller, L.

1977-01-01

Fuel recycle cost deviations resulting from regulatory changes in the back end of the fuel cycle are examined from a number of different data sources, and three potentially large cost uncertainties are identified; HLW disposal, alpha-waste criteria, and in-plant material control/accountability for safeguards. Present and past methods of regulatory cost effectiveness determinations are critiqued and in some cases found wanting

Seasonal fuel consumption, stoves, and end-uses in rural households of the far-western development region of Nepal

Science.gov (United States)

Lam, Nicholas L.; Upadhyay, Basudev; Maharjan, Shovana; Jagoe, Kirstie; Weyant, Cheryl L.; Thompson, Ryan; Uprety, Sital; Johnson, Michael A.; Bond, Tami C.

2017-12-01

Understanding how fuels and stoves are used to meet a diversity of household needs is an important step in addressing the factors leading to continued reliance on polluting devices, and thereby improving household energy programs. In Nepal and many other countries dependent on solid fuel, efforts to mitigate the impacts of residential solid fuel use have emphasized cooking while focusing less on other solid fuel dependent end-uses. We employed a four-season fuel assessment in a cohort of 110 households residing in two elevation regions of the Far-Western Development Region (Province 7) of Nepal. Household interviews and direct fuel weights were used to assess seasonality in fuel consumption and its association with stoves that met cooking and non-cooking needs. Per-capita fuel consumption in winter was twice that of other measured seasons, on average. This winter increase was attributed to greater prevalence of use and fuel consumption by supplemental stoves, not the main cooking stove. End-use profiles showed that fuel was used in supplemental stoves to meet the majority of non-meal needs in the home, notably water heating and preparation of animal food. This emphasis on fuels, stoves, and the satisfaction of energy needs—rather than just stoves or fuels—leads to a better understanding of the factors leading to device and fuel choice within households.

Effect of fuel treatments and backfiring on the recovery of an obligate seeder-dominated heathland

Directory of Open Access Journals (Sweden)

Cristina Fernández Filgueira

2016-12-01

Full Text Available Aim of study: To evaluate how a plant community responded to a backfire that occurred four years after application of different types of fuel-reduction treatments. Area of study: Erica umbellata Loefl. (L.-dominated heathland in Galicia (NW Spain. Materials and Methods: Shrub cover surveys in 16 experimental plots from 2006 to 2014. Fuel reduction treatments (prescribed burning, clearing and mastication were applied in the spring of 2006 and the area was burned by a wildfire in the summer of 2010. Main results: Shrub total cover recovered quickly after the backfire in both the treated and untreated areas, and the pre-treatment values were reached four years after the fire. Post-wildfire resprouting species cover recovery was not affected by fuel treatments. As a contrast,  Erica umbellata cover reached levels similar to those in the untreated plots only in the areas treated by prescribed burning. After the wildfire, grasses cover recovery was greater in the treated than in the untreated areas and the effect lasted until the end of the study. Research highlights: Prescribed fire and backfire was favourable for Erica umbellata regeneration compared to clearing and mastication. Keywords: prescribed burning; clearing; mechanical shredding; Erica; wildfire.

Risk assessment for truck-transport assuming different concepts of the back-end of the fuel cycle

International Nuclear Information System (INIS)

Tully, A.; Sonnenschein, R.; Haeusler, S.

1983-01-01

The different concepts of the back-end of the fuel cycle existing in the Federal Republic of Germany require that various types of radioactive materials will be transported along different pathways, for various distances and at different frequencies, thus resulting in different risks to the public. In one part of the second phase of the R + D program Projekt Sicherheitsstudien Entsorgung (PSE), the risk during normal and accident conditions will be assessed for each of the concepts of the back-end of the fuel cycle. Within this part of the safety analysis, DORNIER SYSTEM will determine the risks resulting from the transport of radioactive materials by truck, using the probabilistic method of fault tree analysis. This part of the investigation will extend until the end of 1983. 4 references, 5 tables

Clinical Value of High Mobility Group Box 1 and the Receptor for Advanced Glycation End-products in Head and Neck Cancer: A Systematic Review

Directory of Open Access Journals (Sweden)

Nguyen, Austin

2016-04-01

Full Text Available Introduction High mobility group box 1 is a versatile protein involved in gene transcription, extracellular signaling, and response to inflammation. Extracellularly, high mobility group box 1 binds to several receptors, notably the receptor for advanced glycation end-products. Expression of high mobility group box 1 and the receptor for advanced glycation end-products has been described in many cancers. Objectives To systematically review the available literature using PubMed and Web of Science to evaluate the clinical value of high mobility group box 1 and the receptor for advanced glycation end-products in head and neck squamous cell carcinomas. Data synthesis A total of eleven studies were included in this review. High mobility group box 1 overexpression is associated with poor prognosis and many clinical and pathological characteristics of head and neck squamous cell carcinomas patients. Additionally, the receptor for advanced glycation end-products demonstrates potential value as a clinical indicator of tumor angiogenesis and advanced staging. In diagnosis, high mobility group box 1 demonstrates low sensitivity. Conclusion High mobility group box 1 and the receptor for advanced glycation end-products are associated with clinical and pathological characteristics of head and neck squamous cell carcinomas. Further investigation of the prognostic and diagnostic value of these molecules is warranted.

Quality evaluation of PHWR fuel element end cap weld joints by ultrasonic testing technique

Energy Technology Data Exchange (ETDEWEB)

Singh, J L; Nair, V R; Ramadasan, E; Majumdar, S; Sahoo, K C [Bhabha Atomic Research Centre, Bombay (India). Radiometallurgy Div.; Kumar, Arun [Atomic Fuel Fabrication Facility, Tarapur (India)

1994-12-31

An ultrasonic testing technique has been developed for effective quality evaluation of Pressurised Heavy Water Reactor (PHWR) fuel end plug welds. A focused high frequency shear wave is directed to the weld zone from half skip distance to detect lack of fusion, porosities and wall cracks in the weld zone. A tentative select/reject level has been evolved to sort out the defective weld by examining more than 700 PHWR fuel pin welds. (author). 5 refs., 5 figs.

Fuels planning: science synthesis and integration; economic uses fact sheet 03: economic impacts of fuel treatments

Science.gov (United States)

Rocky Mountain Research Station USDA Forest Service

2004-01-01

With increased interest in reducing hazardous fuels in dry inland forests of the American West, agencies and the public will want to know the economic impacts of fuel reduction treatments. This fact sheet discusses the economic impact tool, a component of My Fuel Treatment Planner, for evaluating economic impacts.

Effect of mastication and other mechanical treatments on fuel structure in chaparral

Science.gov (United States)

Brennan, Teresa J.; Keeley, Jon E.

2015-01-01

Mechanical fuel treatments are a common pre-fire strategy for reducing wildfire hazard that alters fuel structure by converting live canopy fuels to a compacted layer of dead surface fuels. Current knowledge concerning their effectiveness, however, comes primarily from forest-dominated ecosystems. Our objectives were to quantify and compare changes in shrub-dominated chaparral following crushing, mastication, re-mastication and mastication-plus-burning treatments, and to assess treatment longevity. Results from analysis of variance (ANOVA) identified significant differences in all fuel components by treatment type, vegetation type and time since treatment. Live woody fuel components of height, cover and mass were positively correlated with time since treatment, whereas downed woody fuel components were negatively correlated. Herbaceous fuels, conversely, were not correlated, and exhibited a 5-fold increase in cover across treatment types in comparison to controls. Average live woody fuel recovery was 50% across all treatment and vegetation types. Differences in recovery between time-since-treatment years 1–8 ranged from 32–65% and exhibited significant positive correlations with time since treatment. These results suggest that treatment effectiveness is short term due to the rapid regrowth of shrubs in these systems and is compromised by the substantial increase in herbaceous fuels. Consequences of not having a full understanding of these treatments are serious and leave concern for their widespread use on chaparral-dominated landscapes.

Treatment of Childhood Head and Neck Cancer - Patient Version

Science.gov (United States)

Find diagnosis, staging, and treatment information for these head and neck cancers: hypopharynx, larynx, lip and oral cavity, neck cancer with occult primary, nasopharynx, oropharynx, paranasal sinus and nasal cavity, and salivary gland cancer.

Development of an End-plug Welding Technology for an Instrumented Fuel Irradiation Test

International Nuclear Information System (INIS)

Kim, Soo Sung; Lee, Chul Yong; Shin, Yoon Taek; Choo, Kee Nam

2010-01-01

The irradiation test of end-plug specimens was planned for the evaluation of nuclear fuels performance. To establish the fabrication process, and for satisfying the requirements of the irradiation test, an orbital-GTA weld machine for the specimens of the dual rods was developed, and the preliminary welding experiments for optimizing the process conditions of the specimens of the dual rods were performed. Dual rods with a 9.5mm diameter and a 0.6mm wall thickness of the cladding tubes and end-plugs have been used and the optimum conditions of the pin-hole welding have also been selected. This paper describes the experimental results of the GTA welds of the specimens of the dual rods and the metallography examinations of the GTA welded specimens for various welding conditions for the instrumented fuel irradiation test. These investigations satisfied the requirements of the instrumented irradiation test and the GTA welds for the specimens of the dual rods at the HANARO research reactor

Topical papers on the back end of the fuel cycle

International Nuclear Information System (INIS)

1978-01-01

Contributions of five countries discuss problems connected with the treatment of spent fuel elements and radioactive waste. Emphasis is placed on the necessary capacities and the particularities of servicing contracts. Some examples of existing contracts are discussed

Front end of the nuclear fuel cycle: options to reduce the risks of terrorism and proliferation

International Nuclear Information System (INIS)

Greenberg, E.V.C.; Hoenig, M.M.

1987-01-01

The authors' assessment of the prospects for advanced front end technologies and fuel assurances becoming effective mechanisms for achieving nonproliferation and antiterrorism objectives is relatively pessimistic unless they are integrated with back end accommodations such as the return of spent fuel. They recommend that further examination of front end assurances be linked to that accommodation. To be sure, certain real technological improvements may postpone the day when commercial use of nuclear explosive fuels, with all their attendant terrorism and proliferation risks, is justified. Indeed, improvements in LWRs, using well-understood technology combined with advanced enrichment techniques, could reduce uranium requirements up to 45% at the beginning of the next century and up to 30% a decade earlier, provided the economic and security incentives are present. On the institutional side, existing supply conditions put little pressure on importing countries to seek long-term supply assurances. Moreover, the political obstacles to creating new international institutions or arrangements are exceedingly difficult to overcome, especially without a heightened consciousness of the growing risks of civilian explosive nuclear materials and the political will to make these risks a high priority. 2 tables

The importance for Bulgaria of multilateral approaches to the back-end of the nuclear fuel cycle

International Nuclear Information System (INIS)

Necheva, Ch.; McCombie, Ch.

2005-01-01

Bulgaria has a comparatively small nuclear program, but this provides a significant contribution of about 45% to the total electricity production in the country. There are 4 WWER units in operation at Kozloduy NPP and the national energy policy foresees construction of a further plant, Belene NPP. Further development of the nuclear option is dependent on the assurance of both fresh nuclear fuel supply and long-term management of spent fuel and high level waste. Because of the technical and economic challenges involved, international co-operation (bilateral and multilateral) in the back-end of the nuclear fuel cycle is a strategic issue of prime importance. This approach is very politically and socially sensitive at home and abroad and requires international consensus on the legal framework. For Bulgaria, as a producer of nuclear energy which relies on imported fresh nuclear fuel, an option of major interest is to seek a final solution for dealing with spent fuel in co-operation with the supplier of fresh fuel, i.e. Russia at present. But Bulgaria does not address only this option. In parallel, Kozloduy NPP is an organizational member of the international association ARIUS, established in 2002 in Baden, Switzerland. Thus the country also directly supports the mission of Arius, namely the promotion of concepts for safe, secure, economic and politically and socially acceptable regional and international storage and disposal of spent fuel and HLW. Bulgaria also participates directly in the SAPIERR project that was initiated by Arius under the 6 Framework Programme of the European Commission in order to study the concept of regional repositories to be shared by European partners. The range of Bulgarian waste management activities - including practical issues at the power plants, national studies on waste treatment, and involvement in the bilateral and multinational approaches described above - ensures that the country continues to maintain the necessary technical

Design and simulation of front end power converter for a microgrid with fuel cells and solar power sources

Science.gov (United States)

Jeevargi, Chetankumar; Lodhi, Anuj; Sateeshkumar, Allu; Elangovan, D.; Arunkumar, G.

2017-11-01

The need for Renewable Energy Sources (RES) is increasing due to increased demand for the supply of power and it is also environment friendly.In the recent few years, the cost of generation of the power from the RES has been decreased. This paper aims to design the front end power converter which is required for integrating the fuel cells and solar power sources to the micro grid. The simulation of the designed front end converter is carried out in the PSIM 9.1.1 software. The results show that the designed front end power converter is sufficient for integrating the micro grid with fuel cells and solar power sources.

Post-therapeutic surveillance strategies in head and neck squamous cell carcinoma

NARCIS (Netherlands)

Digonnet, Antoine; Hamoir, Marc; Andry, Guy; Haigentz, Missak; Takes, Robert P.; Silver, Carl E.; Hartl, Dana M.; Strojan, Primoz; Rinaldo, Alessandra; de Bree, Remco; Dietz, Andreas; Gregoire, Vincent; Paleri, Vinidh; Langendijk, Johannes A.; Vander Poorten, Vincent; Hinni, Michael L.; Rodrigo, Juan P.; Suarez, Carlos; Mendenhall, William M.; Werner, Jochen A.; Genden, Eric M.; Ferlito, Alfio

The management of head and neck squamous cell carcinomas does not end with the completion of ablative therapy. The oncologic objectives of post-treatment follow-up are to detect recurrences and second primary tumors; beyond that, follow-up should evaluate acute and chronic treatment-related side

2-22 Study of Oxidation/reduction Volatilization Technology

Institute of Scientific and Technical Information of China (English)

Tan; Cunmin[1; Cao; Shiwei[1; Tian; Yuan[1; Qin; Zhi[1

2015-01-01

As an advanced dry head-end processing of spent fuel reprocessing, the oxidation-reduction volatilization technology will use for pulverizing uranium oxide ceramic pellets, decladding, and removal of most of volatile and semi-volatile fission elements, 3H, 14C, Kr, Xe, I, Cs, Ru and Tc, from fuel prior to main treatment process. The AIROX and ORIOX process, including circulation of oxidation in oxygen atmosphere and reduction in hydrogen atmosphere, researched on international at present, is considered to be the first choice for head-end processing.

Treatment of Pediatric Head and Neck Cancer - Health Professional Version

Science.gov (United States)

Find information about prognosis, staging, and treatment for the following head and neck cancer sites in children: esthesioneuroblastoma, larynx and papillomatosis, nasopharynx, oral cavity, and salivary gland.

Apparatus and process for separating end of nuclear fuel assembly

International Nuclear Information System (INIS)

Beneck, J.A.; Quayre, C.; Moreau, J.R.M.; Vermeille, D.E.A.

1989-01-01

The apparatus for cutting the guide tubes of a nuclear fuel assembly below the bottom nozzle has a framework with removable fixation and centering means on the bottom nozzle. Cutting devices in the form of hollow pins are inserted simultaneously into all the guide tubes. Each pin contains a shaft that is moved axially inside it by the expansion system to deploy or retract a cutting edge near the lower end of the pin. A single motor using a gear wheel system, rotates all the cutting pins simultaneously [fr

Chemical dissolution of spent fuel and cladding using complexed fluoride species

International Nuclear Information System (INIS)

Rance, P.J.W.; Freeman, G.A.; Mishin, V.; Issoupov, V.

2001-01-01

The dissolution of LWR fuel cladding using two fluoride ion donors, HBF 4 and K 2 ZrF 6 , in combination with nitric acid has been investigated as a potential reprocessing head-end process suitable for chemical decladding and fuel dissolution in a single process step. Maximum zirconium concentrations in the order of 0,75 to 1 molar have been achieved and dissolution found to continue to low F:Zr ratios albeit at ever decreasing rates. Dissolution rates of un-oxidised zirconium based fuel claddings are fast, whereas oxidised materials exhibit an induction period prior to dissolution. Data is presented relating to the rates of dissolution of cladding and UO 2 fuels under various conditions. (author)

1982 Annual Status Report Plutonium Fuels and Actinide Programme

International Nuclear Information System (INIS)

Lindner, R.

1983-01-01

The programme of the Transuranium Institute has long included work on advanced fuels for fast breeder reactors. Study of the swelling of carbide and nitride fuels is now nearing completion, the retention of fission gases in bubbles of different sizes in the fuel having been quantified as function of burn-up and temperature. An important step forward has been achieved in the studies of the Equation of State of Nuclear Fuels up to 5000 K. Formation of some of the less abundant isotopes in PWR fuel has been determined experimentally. Aerosol formation during the fabrication of plutonium containing fuels, part of the activity Safe Handling of Plutonium Fuel has been studied. Head-End Processing of carbide fuels has continued experiments with high burn up mixed carbides. In the field of actinide research the preparation and characterisation of pure specimens is carried out. Effect of actinides on the properties of waste glasses is investigated

Fast breeder fuel cycle

International Nuclear Information System (INIS)

1978-07-01

This contribution is prepared for the answer to the questionnaire of working group 5, subgroup B. B.1. is the short review of the fast breeder fuel cycles based on the reference large commercial Japanese LMFBR. The LMFBRs are devided into two types. FBR-A is the reactor to be used before 2000, and its burnup and breeding ratio are relatively low. The reference fuel cycle requirement is calculated based on the FBR-A. FBR-B is the one to be used after 2000, and its burnup and breeding ratio are relatively high. B.2. is basic FBR fuel reprocessing scheme emphasizing the differences with LWR reprocessing. This scheme is based on the conceptual design and research and development work on the small scale LMFBR reprocessing facility of Japan. The facility adopts a conventional PUREX process except head end portions. The report also describes the effects of technical modifications of conventional reprocessing flow sheets, and the problems to be solved before the adoption of these alternatives

[SURGICAL HIP DISLOCATION APPROACH FOR TREATMENT OF FEMORAL HEAD FRACTURE].

Science.gov (United States)

Tang, Yanfeng; Liu, Youwen; Zhu, Yingjie; Li, Jianming; Li, Wuyin; Li, Qiyi; Jia, Yudong

2015-11-01

To discuss the value of surgical hip dislocation approach in the treatment of femoral head fracture. A retrospectively analysis was made on the clinical data of 15 patients with femoral head fractures treated through surgical hip dislocation approach between January 2010 and February 2013. There were 11 men and 4 women with an average age of 30.8 years (range, 15-63 years). The causes included traffic accident injury in 9 cases, falling injury from height in 5 cases, and sports injury in 1 case. According to Pipkin typing, 2 cases were rated as type I, 7 cases as type II, 1 case as type III, and 5 cases as type IV. The interval of injury and operation was 2-10 days (mean, 4.1 days). Reduction was performed in 10 patients within 6 hours after injury, and then bone traction was given for 4-6 weeks except 5 patients who received reduction in the other hospital. Primary healing of incision was obtained in all patients after surgery without complications of dislocation and lower limbs deep venous thrombosis. The mean follow-up time was 29.9 months (range, 25-36 months). During follow-up, there was no infection, breakage of internal fixation, or nonunion of femoral greater trochanter fracture. In 3 patients having necrosis of the femoral head, 2 had no obvious symptoms [staging as IIa and IIb respectively according to Association Research Circulation Osseous (ARCO) staging system], and 1 (stage IIIb) had nonunion of the femoral neck fracture, who underwent total hip arthroplasty (THA). In 4 patients having myositis ossificans (2 cases of grade I, 1 case of grade II, and 1 case of grade III based on Brooker grading), no treatment was given in 3 cases and the focus was removed during THA in 1 case. According to the Thompson-Epstein scale at last follow-up, the results were excellent in 9 cases, good in 3 cases, fair in 1 case, and poor in 2 cases, and the excellent and good rate was 80%. Surgical hip dislocation approach can not only protect the residual vessels of the

Hybrid laser arc welding of a used fuel container

Energy Technology Data Exchange (ETDEWEB)

Boyle, C., E-mail: cboyle@nwmo.ca [Nuclear Waste Management Organization, Toronto, ON (Canada); Martel, P. [Novika Solutions, La Pocatiere, QC (Canada)

2015-07-01

The Nuclear Waste Management Organization (NWMO) has designed a novel Used Fuel Container (UFC) optimized for CANDU used nuclear fuel. The Mark II container is constructed of nuclear grade pipe for the body and capped with hemi-spherical heads. The head-to-shell joint fit-up features an integral backing designed for external pressure, eliminating the need for a full penetration closure weld. The NWMO and Novika Solutions have developed a partial penetration, single pass Hybrid Laser Arc Weld (HLAW) closure welding process requiring no post-weld heat treatment. This paper will discuss the joint design, HLAW process, associated welding equipment, and prototype container fabrication. (author)

Hybrid laser arc welding of a used fuel container

Energy Technology Data Exchange (ETDEWEB)

Boyle, C. [Nuclear Waste Management Organization (NWMO), Toronto, Ontario (Canada); Martel, P. [Novika Solutions, La Pocatiere, Quebec (Canada)

2015-09-15

The Nuclear Waste Management Organization (NWMO) has designed a novel Used Fuel Container (UFC) optimized for CANDU used nuclear fuel. The Mark II container is constructed of nuclear grade pipe for the body and capped with hemi-spherical heads. The head-to-shell joint fit-up features an integral backing designed for external pressure, eliminating the need for a full penetration closure weld. The NWMO and Novika Solutions have developed a partial penetration, single pass Hybrid Laser Axe Weld (HLAW) closure welding process requiring no post-weld heat treatment. This paper will discuss the joint design, HLAW process, associated welding equipment, and prototype container fabrication. (author)

Reference thorium fuel cycle

International Nuclear Information System (INIS)

Driggers, F.E.

1978-08-01

In the reference fuel cycle for the TFCT program, fissile U will be denatured by mixing with 238 U; the plants will be located in secure areas, with Pu being recycled within these secure areas; Th will be recycled with recovered U and Pu; the head end will handle a variety of core and blanket fuel assembly designs for LWRs and HWRs; the fuel may be a homogeneous mixture either of U and Th oxide pellets or sol-gel microspheres; the cladding will be Zircaloy; and MgO may be added to the fuel to improve Th dissolution. Th is being considered as the fertile component of fuel in order to increase proliferation resistance. Spent U recovered from Th-based fuels must be re-enriched before recycle to prevent very rapid buildup of 238 U. Stainless steel will be considered as a backup to Zircaloy cladding in case Zr is incompatible with commercial aqueous dissolution. Storage of recovered irradiated Th will be considered as a backup to its use in the recycle of recovered Pu and U. Estimates are made of the time for introducing the Th fuel cycle into the LWR power industry. Since U fuel exposures in LWRs are likely to increase from 30,000 to 50,000 MWD/MT, the Th reprocessing plant should also be designed for Th fuel with 50,000 MWD/MT exposure

Femoral head injuries: Which treatment strategy can be recommended?

NARCIS (Netherlands)

Henle, Philipp; Kloen, Peter; Siebenrock, Klaus A.

2007-01-01

Despite different operative and non-operative treatment regimens, the outcome after femoral head fractures has changed little over the past decades. The initial trauma itself as well as secondary changes such as posttraumatic osteoarthritis, avascular necrosis or heterotopic ossification is often

Fuel assembly

International Nuclear Information System (INIS)

Sakuyama, Tadashi; Mukai, Hideyuki.

1988-01-01

Purpose: To prevent the bending of a fuel rod caused by the difference in the elongation between a joined fuel rod and a standard fuel rod thereby maintain the fuel rod integrity. Constitution: A joined fuel rod is in a thread engagement at its lower end plug thereof with a lower plate, while passed through at its upper end plug into an upper tie plate and secured with a nut. Further, a standard fuel rod is engaged at its upper end plug and lower end plug with the upper tie plate and the lower tie plate respectively. Expansion springs are mounted to the upper end plugs of these bonded fuel rods and the standard fuel rods for preventing this lifting. Each of the fuel rods comprises a plurality of sintered pellets of nuclear fuel materials laminated in a zircaloy fuel can. The content of the alloy ingredient in the fuel can of the bonded fuel rod is made greater than that of the alloy ingredient of the standard fuel rod. this can increase the elongation for the bonded fuel rod, and the spring of the standard fuel rod is tightly bonded to prevent the bending. (Yoshino, Y.)

Development of Vegetation and Surface Fuels Following Fire Hazard Reduction Treatment

Directory of Open Access Journals (Sweden)

Scott L. Stephens

2012-08-01

Full Text Available In dry western Unites States forests where past resource management has altered the ecological role of fire and stand characteristics alike, mechanical thinning and prescribed burning are commonly applied in wildfire hazard abatement. The reduced surface fuel loads and stand structures resulting from fuels modifications are temporary, yet few studies have assessed the lifespan of treatment effects. We sampled forest fuels and vegetation following fuels reduction in a chronosequence of time since treatment in the northern Sierra Nevada and southern Cascade regions of California. Treatments altered overstory characteristics including stand density, basal area, and species composition. These effects were still present on the oldest treatment sites (8–15 years post-treatment. Other stand characteristics, particularly timelag fuel loads, seedling density, and shrub cover, exhibited substantial variability, and differences between treatment age classes and between treatment and control groups were not statistically significant.

Social science to improve fuels management: a synthesis of research on assessing social acceptability of fuels treatments

Science.gov (United States)

Terry C. Daniel; Michael Valdiserri; Carrie R. Daniel; Pamela Jakes; Pamela Jakes; Susan Barro

2005-01-01

A series of syntheses were commissioned by the USDA Forest Service to aid in fuels mitigation project planning. This synthesis focuses on research for assessing the social acceptability of fuels treatments. The synthesis is structured around six important considerations for any social acceptability assessment: defining the fuels treatments being assessed; representing...

General Atomic HTGR fuel reprocessing pilot plant: results of initial sequential equipment operation

International Nuclear Information System (INIS)

1978-09-01

In September 1977, the processing of 20 large high-temperature gas-cooled reactor (LHTGR) fuel elements was completed sequentially through the head-end cold pilot plant equipment. This report gives a brief description of the equipment and summarizes the results of the sequential operation of the pilot plant. 32 figures, 15 tables

An overview of head and neck treatment at the KNH radiotherapy, Nairobi

International Nuclear Information System (INIS)

Mucheusi, L.

2006-01-01

It is known from several studies that precise radical radiotherapy leads to better local control thus increasing overall survival of patients suffering from Head and Neck malignancies if diagnosed early enough. The wide gap in the techniques and equipment used between the developed and the developing world are a source of concern especially in Sub Saharan africa which hardly boasts of even a single linear accelerator. in this presentation, common Head and Neck condition treatment is examined as it is done at the Kenyatta National Hospital. The treatment techniques used the planning process/innovations improvisations-adopted by radiographers at the institution to achieve the prescribed treatment

Long term assurance of supply of back end of fuel cycle facilities and services

International Nuclear Information System (INIS)

1978-01-01

The paper deals with the long-term assurance of supply of the back end of fuel cycle facilities and services. 11 fundamental questions are posed and commented on by representatives of 7 countries. Non-proliferation aspects are not considered as they will be discussed elsewhere

Treatment of head and neck squamous cell carcinoma in elderly patients

International Nuclear Information System (INIS)

Honda, Keigo; Asato, Ryo; Tsuji, Jun; Kanda, Tomoko; Ushiro, Kohji; Watanabe, Yoshiki; Mori, Yusuke

2010-01-01

The object of this study was to clarify the characteristics of treatment for elderly head and neck squamous cell cancer patients. We conducted a chart review of 177 head and neck squamous cell cancer patients who had been treated at Kyoto Medical Center, from 2005 through 2009. All the collected data were analyzed to compare the clinical features and the treatment outcomes between the younger group ( or =75, EG, n=46). Male to female ratio was lower in EG (5.6:1 vs. 1.7:1, p<0.01). C urative treatment was performed in most of the patients with early disease (stage I-II) in both groups (96.7% vs. 90.5%), while the ratio of curative treatment was significantly lower in EG patients with advanced stage disease (stage III-IV) (92.3% vs. 52.0%, p<0.01). There was no significant difference in the frequency of adopted treatment modality (surgery or radiotherapy) between YG and EG. Adjuvant chemotherapy or postoperative radiotherapy was avoided in most of EG patients. Local complication rates after major surgery for advanced cases were similar in both groups (30.8% vs. 27.3%), while a higher systemic complication rate was observed in EG (0% vs. 27.3%). After curative treatment, there was no difference in disease specific three-year survival rates between YG and EG (100% vs. 100% in early stage disease, 65.2% vs. 60.6% in advanced disease, Kaplan-Meier curve). Although treatment of elderly patients with head and neck cancer can be inhibited by poor performance status and/or concomitant diseases, clinical results after curative treatment are comparable to those of younger patients. (author)

Application of spent fuel treatment technology to plutonium immobilization

International Nuclear Information System (INIS)

McPheeters, C.C.; Ackerman, J.P.; Gay, E.C., Johnson, G.K.

1996-01-01

The purpose of the electrometallurgical treatment technology being developed at Argonne National Laboratory (ANL) is to convert certain spent nuclear fuels into waste forms that are suitable for disposal in a geological repository for nuclear waste. The spent fuels of interest are those that cannot be safely stored for a long time in their current condition, and those that cannot be qualified for repository disposal. This paper explores the possibility of applying this electrometallurgical treatment technology to immobilization of surplus fissile materials, primarily plutonium. Immobilization of surplus fissile materials by electrometallurgical treatment could be done in the same facilities, at the same time. and in the same equipment as the proposed treatment of the present inventory of spent nuclear fuel. The cost and schedule savings of this simultaneous treatment scheme would be significant

The Union view of back end fuel cycle provisions for nuclear power plants

International Nuclear Information System (INIS)

Anon.

1981-01-01

After a long political and technical discussion, the German trade unions united in the German Federation of Labor (DGB) arrived at the finding that back end fuel cycle provisions for nuclear power plants in the Federal Republic of Germany, in addition to the present concept of the Government providing for a reprocessing plant, should also include studies of the alternative possibility to store spent fuel elements over long periods of time, perhaps with a possibility to recover them later. That decision is also based on a report by the Nuclear Technology Working Group of the Metal Workers Union (IG Metall) and the Public Workers Union (OeTV). (orig.) [de

Pilot-scale equipment development for pyrochemical treatment of spent oxide fuel

International Nuclear Information System (INIS)

Herrmann, S. D.

1999-01-01

Fundamental objectives regarding spent nuclear fuel treatment technologies include, first, the effective distribution of spent fuel constituents among product and stable waste forms and, second, the minimization and standardization of waste form types and volumes. Argonne National Laboratory (ANL) has developed and is presently demonstrating the electrometallurgical treatment of sodium-bonded metal fuel from Experimental Breeder Reactor II, resulting in an uranium product and two stable waste forms, i.e. ceramic and metallic. Engineering efforts are underway at ANL to develop pilot-scale equipment which would precondition irradiated oxide fuel via pyrochemical processing and subsequently allow for electrometallurgical treatment of such non-metallic fuels into standard product and waste forms. This paper highlights the integration of proposed spent oxide fuel treatment with existing electrometallurgical processes. System designs and technical bases for development of pilot-scale oxide reduction equipment are also described

Fuel assembly

International Nuclear Information System (INIS)

Gjertsen, R.K.; Bassler, E.A.; Huckestein, E.A.; Salton, R.B.; Tower, S.N.

1988-01-01

A fuel assembly adapted for use with a pressurized water nuclear reactor having capabilities for fluid moderator spectral shift control is described comprising: parallel arranged elongated nuclear fuel elements; means for providing for axial support of the fuel elements and for arranging the fuel elements in a spaced array; thimbles interspersed among the fuel elements adapted for insertion of a rod control cluster therewithin; means for structurally joining the fuel elements and the guide thimbles; fluid moderator control means for providing a volume of low neutron absorbing fluid within the fuel assembly and for removing a substantially equivalent volume of reactor coolant water therefrom, a first flow manifold at one end of the fuel assembly sealingly connected to a first end of the moderator control tubes whereby the first ends are commonly flow connected; and a second flow manifold, having an inlet passage and an outlet passage therein, sealingly connected to a second end of the moderator control tubes at a second end of the fuel assembly

Hazardous fuel treatments, suppression cost impacts, and risk mitigation

Science.gov (United States)

Matthew P. Thompson; Michael S. Hand; Julie W. Gilbertson-Day; Nicole M. Vaillant; Darek J. Nalle

2013-01-01

Land management agencies face uncertain tradeoffs regarding investments in preparedness and fuels management versus future suppression costs and impacts to valued resources and assets. Prospective evaluation of fuel treatments allows for comparison of alternative treatment strategies in terms of socioeconomic and ecological impacts, and can facilitate tradeoff analysis...

Introduction to the study of the treatment of spent nuclear fuel

International Nuclear Information System (INIS)

Floh, B.; Araujo, J.A. de; Matsuda, H.T.

1975-01-01

An introduction is made to the study of the treatment of spent nuclear fuels. Main topics discussed are: basic information, volatilization processes, treatment of thorium based fuels (Thorex process), analytical chemistry of spent nuclear fuel and design of industrial facilities

Outline of a fuel treatment facility in NUCEF

International Nuclear Information System (INIS)

Sugikawa, Susumu; Umeda, Miki; Kokusen, Junya

1997-03-01

This report presents outline of the nuclear fuel treatment facility for the purpose of preparing solution fuel used in Static Experiment Critical Facility (STACY) and Transient Experiment Critical Facility (TRACY) in Nuclear Fuel Cycle Safety Engineering Research Facility (NUCEF), including descriptions of process conditions and dimensions of major process equipments on dissolution system of oxide fuel, chemical adjustment system, purification system, acid recovery system, solution fuel storage system, and descriptions of safety design philosophy such as safety considerations of criticality, solvent fire, explosion of hydrogen and red-oil and so on. (author)

Treatment of Head and Neck Cancer in Adults - Patient Version

Science.gov (United States)

Find diagnosis, staging, and treatment information for these head and neck cancers: hypopharynx, larynx, lip and oral cavity, neck cancer with occult primary, nasopharynx, oropharynx, paranasal sinus and nasal cavity, and salivary gland cancer.

Improving Therapeutic Ratio in Head and Neck Cancer with Adjuvant and Cisplatin-Based Treatments

Directory of Open Access Journals (Sweden)

Loredana G. Marcu

2013-01-01

Full Text Available Advanced head and neck cancers are difficult to manage despite the large treatment arsenal currently available. The multidisciplinary effort to increase disease-free survival and diminish normal tissue toxicity was rewarded with better locoregional control and sometimes fewer side effects. Nevertheless, locoregional recurrence is still one of the main reasons for treatment failure. Today, the standard of care in head and neck cancer management is represented by altered fractionation radiotherapy combined with platinum-based chemotherapy. Targeted therapies as well as chronotherapy were trialled with more or less success. The aim of the current work is to review the available techniques, which could contribute towards a higher therapeutic ratio in the treatment of advanced head and neck cancer patients.

ArcFuels: an ArcMap toolbar for fuel treatment planning and wildfire risk assessment

Science.gov (United States)

Nicole M. Vaillant; Alan A. Ager

2014-01-01

Fire behavior modeling and geospatial analysis can provide tremendous insight to land managers in defining both the benefits and potential impacts of fuel treatments in the context of land management goals and public expectations. ArcFuels is a streamlined fuel management planning and wildfire risk assessment system that creates a trans-scale (stand to large landscape...

Reprocessing in breeder fuel cycles

International Nuclear Information System (INIS)

Burch, W.D.; Groenier, W.S.

1982-01-01

Over the past decade, the United States has developed plans and carried out programs directed toward the demonstration of breeder fuel reprocessing in connection with the first breeder demonstration reactor. A renewed commitment to moving forward with the construction of the Clinch River Breeder Reactor (CRBR) has been made, with startup anticipated near the end of this decade. While plans for the CRBR and its associated fuel cycle are still being firmed up, the basic research and development programs required to carry out the demonstrations have continued. This paper updates the status of the reprocessing plans and programs. Policies call for breeder recycle to begin in the early to mid-1990's. Contents of this paper are: (1) evolving plans for breeder reprocessing (demonstration reprocessing plant, reprocessing head-end colocated at an existing facility); (2) relationship to LWR reprocessing; (3) integrated equipment test (IET) facility and related hardware development activities (mechanical considerations in shearing and dissolving, remote operations and maintenance demonstration phase of IET, integrated process demonstration phase of IET, separate component development activities); and (4) supporting process R and D

Apparatus for assembling and welding end plugs to nuclear fuel cladding tubes and inspecting the end plug welds on an automated basis

International Nuclear Information System (INIS)

Schoenig, F.C. Jr.; Walker, E.S.; Cueman, M.K.; Haughton, R.A.; Zuloaga, J.A. Jr.

1989-01-01

This patent describes an automated apparatus for welding a separate end plug to one open end of each of a succession of nuclear fuel cladding tubes and for inspecting each end plug weld. The apparatus comprising, in combination: a welding station; a cooldown station for cooling each end plug weld in an inert gas atmosphere; a serial number reader station for reading a serial number on each end plug; a first weld inspection station; a second weld inspection station for generating second weld inspection data; a computer system linked with the serial number reader and the first and second weld inspection stations; an input queue for holding a plurality of tubes; a tube transporter for periodically picking individual tubes from the input queque and conveying the tubes in a direction transverse to their tube axis in indexing steps to index positions respectively axially aligned with the welding, serial number reader, and first and second weld inspection stations; and a sorter positioned at an output end of the tube transporter

Initial treatment results using cyberknife for head and neck tumor

International Nuclear Information System (INIS)

Himei, Kengo; Katsui, Kuniaki; Yoshida, Atsushi; Takemoto, Mitsuhiro; Kobayashi, Mitsuru; Kuroda, Masahiro; Hiraki, Yoshio

2002-01-01

The CyberKnife, a medical device for stereotactic radiotherapy, is composed of a combination of a robot manipulator and LINAC. For the treatment of head and neck tumors, this system has been applied. Between June 2000 and January 2001, 18 patients with head and neck tumor were treated with this system because of tumor recurrence, difficulty in surgery or additional increase after external radiotherapy. The median age was 64 years. Primary lesions were skull base (4), nasopharynx (3), paranasal sinus (3), nasal cavity (2), lacrimal gland (1), oropharynx (1), oral floor (1), and buccul mucosa (1), metastatic lymph nodes were found in three. The prescribed dose was 12-38 Gy as for marginal dose. The response rate (CR+PR) was 44.4% and local control rate (CR+PR+NC) was 77.8%. The adverse effects were assessed by the NCI-CTC Version 2.0 and observed grade 3 in two cases. Our early experience indicates that this system could to be feasible for the treatment of locally advanced or recurrent head and neck tumor, and for the reduction of adverse effect and maintenance of useful QOL of patients. (author)

Prevention and treatment of the consequences of head and neck radiotherapy

NARCIS (Netherlands)

Vissink, A; Burlage, FR; Spijkervet, FKL; Jansma, J; Coppes, RP

The location of the primary tumor or lymph node metastases dictates the inclusion of the oral cavity, salivary glands, and jaws in the radiation treatment portals for patients who have head and neck cancer. The clinical sequelae of the radiation treatment include mucositis, hyposalivation, loss of

Detection of treatment setup errors between two CT scans for patients with head and neck cancer

International Nuclear Information System (INIS)

Ezzell, Leah C.; Hansen, Eric K.; Quivey, Jeanne M.; Xia Ping

2007-01-01

Accuracy of treatment setup for head and neck patients undergoing intensity-modulated radiation therapy is of paramount importance. The conventional method using orthogonal portal images can only detect translational setup errors while the most frequent setup errors for head and neck patients could be rotational errors. With the rapid development of image-guided radiotherapy, three-dimensional images are readily acquired and can be used to detect both translational and rotational setup errors. The purpose of this study is to determine the significance of rotational variations between two planning CT scans acquired for each of eight head and neck patients, who experienced substantial weight loss or tumor shrinkage. To this end, using a rigid body assumption, we developed an in-house computer program that utilizes matrix transformations to align point bony landmarks with an incremental best-fit routine. The program returns the quantified translational and rotational shifts needed to align the scans of each patient. The program was tested using a phantom for a set of known translational and rotational shifts. For comparison, a commercial treatment planning system was used to register the two CT scans and estimate the translational errors for these patients. For the eight patients, we found that the average magnitudes and standard deviations of the rotational shifts about the transverse, anterior-posterior, and longitudinal axes were 1.7±2.3 deg., 0.8±0.7 deg., and 1.8±1.1 deg., respectively. The average magnitudes and standard deviations of the translational shifts were 2.5±2.6 mm, 2.9±2.8 mm, 2.7±1.7 mm while the differences detected between our program and the CT-CT fusion method were 1.8±1.3 mm, 3.3±5.4 mm, and 3.0±3.4 mm in the left-right, anterior-posterior, and superior-inferior directions, respectively. A trend of larger rotational errors resulting in larger translational differences between the two methods was observed. In conclusion, conventional

Ecodesign of Liquid Fuel Tanks

Science.gov (United States)

Gicevska, Jana; Bazbauers, Gatis; Repele, Mara

2011-01-01

The subject of the study is a 10 litre liquid fuel tank made of metal and used for fuel storage and transportation. The study dealt with separate life cycle stages of this product, compared environmental impacts of similar fuel tanks made of metal and plastic, as well as analysed the product's end-of-life cycle stage, studying the waste treatment and disposal scenarios. The aim of this study was to find opportunities for improvement and to develop proposals for the ecodesign of 10 litre liquid fuel tank.

Power peak in vicinity of WWER-440 control rod at end of fuel cycle

International Nuclear Information System (INIS)

Mikus, J.

2003-01-01

This paper presents some results of the axial power distribution measurements carried out in a WWER-440 type core on the light-water, zero-power reactor LR-O in the vicinity of the WWER-440 control rod model at zero boron concentration in moderator. Further presented information concern the description of the control rod model, LR-0 core arrangement, specification of the fuel assemblies and measurement conditions. The aim of performed experiment is enlargement of the available 'power peaking database' to enable the calculation codes validation also by means of data that correspond to the end of WWER-440 fuel cycle (Authors)

Design, Fabrication, and Testing of a Laboratory-Scale Voloxidation System for Removal of Tritium and Other Volatile Fission Products from Used Nuclear Fuel

International Nuclear Information System (INIS)

Spencer, Barry B; DelCul, Guillermo D; Bradley, Eric Craig; Jubin, Robert Thomas; Hylton, Tom D; Collins, Emory D

2008-01-01

Advanced nuclear fuel processing methodologies are being demonstrated at the Oak Ridge National Laboratory (ORNL) as part of the Global Nuclear Energy Partnership (GNEP) program. A coupled end-to-end (CETE) research and development (R and D) capability is being installed to provide all primary processing operations, ranging from spent fuel receipt to production of products and waste forms. This R and D capability is designed for small, laboratory-scale throughput and will permit conduct of experiments in the range of 20 kg of spent fuel per year. The head-end processing segment includes single-pin shearing, voloxidation to remove tritium from the fuel before it enters the aqueous based separations systems, cleanup of the cladding hulls for disposition, and transfer of the fuel powder to the dissolution process. This paper describes the voloxidation system design and presents results from the cold checkout of the hardware. Preliminary results of the initial processing campaign with spent fuel is presented as well

Liposomal treatment of xerostomia, odor, and taste abnormalities in patients with head and neck cancer.

Science.gov (United States)

Heiser, Clemens; Hofauer, Benedikt; Scherer, Elias; Schukraft, Johannes; Knopf, Andreas

2016-04-01

Smell and taste disorders, sicca symptoms, can be detected in patients with head and neck cancer. The purpose of this study was to assess the utility of local liposomal application in the treatment of patients with head and neck cancers. Ninety-eight patients with head and neck cancer were included in this study. The groups were defined as: group 1 = only surgery; group 2 = surgery + adjuvant radiochemotherapy; and group 3 = primarily radiochemotherapy. All patients had finished cancer treatment and received liposomal sprays for the nose and mouth for 2 months (LipoNasal, LipoSaliva; Optima Pharmaceutical GmbH, Germany) and suffered from taste and smell disorders. We performed tests with "Sniffin' Sticks," "Taste Strips," and a xerostomia questionnaire before and after treatment. After application of liposomes, patients demonstrated a statistically significant increase in smell and taste, and reduced xerostomia. Our results demonstrate that using nonpharmaceutical liposomal sprays improve smell, taste, and symptoms of xerostomia in patients with head and neck cancer. © 2015 Wiley Periodicals, Inc. Head Neck 38: E1232-E1237, 2016. © 2015 Wiley Periodicals, Inc.

Devoluming and stabilizing method for end piece

International Nuclear Information System (INIS)

Ikeda, Satoshi; Shiotsuki, Msao; Kawamura, Shigeyoshi; Komatsu, Fumiaki.

1991-01-01

As a first method, end pieces and other radioactive metal wastes are filled as a mixture in a vessel, and preliminary compression is conducted. Then, the bulk density of the radioactive metal wastes is reduced and gaps in the end pieces are filled with radioactive metal wastes. If they are applied with heat treatment under high pressure in this state together with the vessel, they are devolumed and stabilized without damaging the vessel. As a second method, metal powders are mixed and filled in the vessel together with the end pieces. The gaps in the end pieces are filled with the metal powders and if they are applied with heat treatment under high pressure in this state together with the vessel, the end pieces are devolumed and stabilized without damaging the vessel in the same manner. This can devolume and stabilize the end pieces separated from nuclear fuel assemblies easily and safely. (T.M.)

Advanced waste forms from spent nuclear fuel

International Nuclear Information System (INIS)

Ackerman, J.P.; McPheeters, C.C.

1995-01-01

More than one hundred spent nuclear fuel types, having an aggregate mass of more than 5000 metric tons (2700 metric tons of heavy metal), are stored by the United States Department of Energy. This paper proposes a method for converting this wide variety of fuel types into two waste forms for geologic disposal. The method is based on a molten salt electrorefining technique that was developed for conditioning the sodium-bonded, metallic fuel from the Experimental Breeder Reactor-II (EBR-II) for geologic disposal. The electrorefining method produces two stable, optionally actinide-free, high-level waste forms: an alloy formed from stainless steel, zirconium, and noble metal fission products, and a ceramic waste form containing the reactive metal fission products. Electrorefining and its accompanying head-end process are briefly described, and methods for isolating fission products and fabricating waste forms are discussed

Scientific research on the back-end of the fuel cycle for the 21. century; Les recherches scientifiques sur l'aval du cycle pour le 21. siecle

Energy Technology Data Exchange (ETDEWEB)

NONE

2000-07-01

The aim of the Atalante-2000 conference is to present the major research axis concerning the nuclear fuel cycle back-end. The different topics are: - Present options concerning fuel cycle back-end; - Reprocessing of spent fuel; - Advanced separation for transmutation; - Processing and packaging of radioactive wastes; - Design and fabrication of targets for transmutation; and - Conversion of military plutonium into MOX fuels.

Basic principles of forest fuel reduction treatments

Science.gov (United States)

James K. Agee; Carl N. Skinner

2005-01-01

Successful fire exclusion in the 20th century has created severe fire problems across the West. Not every forest is at risk of uncharacteristically severe wildfire, but drier forests are in need of active management to mitigate fire hazard. We summarize a set of simple principles important to address in fuel reduction treatments: reduction of surface fuels, increasing...

Studies on the fission products behavior during dissolution process of BWR spent fuel

International Nuclear Information System (INIS)

Sato, K.; Nakai, E.; Kobayashi, Y.

1987-01-01

In order to obtain basic data on fission products behavior in connection with the head end process of fuel reprocessing, especially to obtain better understanding on undissolved residues, small scale dissolution studies were performed by using BWR spent fuel rods which were irradiated as monitoring fuel rods under the monitoring program for LWR fuel assembly performance entitled PROVING TEST ON RELIABILITY OF FUEL ASSEMBLY . The Zircaloy-2 claddings and the fuel pellets were subjected individually to the following studies on 1) release of fission products during dissolution process, 2) characterization of undissolved residues, and 3) analysis of the claddings. This paper presents comprehensive descriptions of the fission products behavior during dissolution process, based on detailed and through PIE conducted by JNFS under the sponsorship of MITI (Ministry of International Trade and Industry)

Chemical engineering in fuel reprocessing. The French experience

International Nuclear Information System (INIS)

Viala, M.; Sombret, C.; Bernard, C.; Miquel, P.; Moulin, J.P.

1992-01-01

Reprocessing is the back-end of the nuclear fuel cycle, designed to recover valuable fissile materials, especially plutonium, and to condition safely all the wastes ready for disposal. For its new commercial reprocessing plants (UP 3 and UP 2 800) COGEMA decided to include many engineering innovations as well as new processes and key-components developed by CEA. UP 3 is a complete new plant with a capacity of 800 t/y which was put in operation in August 1990. UP 2 800 is an extension of the existing UP 2 facility, designed to achieve the same annual capacity of 800 t/y, to be put in operation at the end of 1993 by the commissioning of a new head-end and highly active chemical process facilities

Principles of provision concerning the back-end of the fuel cycle of nuclear power plants find application

International Nuclear Information System (INIS)

1977-01-01

The Ministry of the Interior has asked the Laender on the 14th June 1977, to apply forthwith the 'principles of provision concerning the back-end of the fuel cycle of nuclear power plants' as a minimum pre-condition for waste management in licensing procedures for nuclear power stations. The 'principles' were part of a report, elaborated by a Bund/Laender working group at a undersecretary-of-state level on questions concerning the back-end of the fuel cycle of nuclear power plants. The report was favourably acknowledged during a meeting of the Federal Chancellor and the Minister-Presidents of the Laender on May 6th, 1977. The principles are presented. (orig./HP) [de

Head-end reprocessing equipment remote maintenance demonstration

International Nuclear Information System (INIS)

Evans, J.H.; Metz, C.F. III.

1989-01-01

Prototype equipment for reprocessing breeder reactor nuclear fuel was installed in the Remote Operation and Maintenance Demonstration (ROMD) area of the Consolidated Fuel Reprocessing Program (CFRP) facility at the Oak Ridge National Laboratory (ORNL) in order to evaluate the design of this equipment in a cold mock-up of a remotely maintained hot cell. This equipment included the Remote Disassembly System (RDS) and the Remote Shear System (RSS). These systems were disassembled and reassembled remotely by using the extensive remote handling systems that are installed in this simulated hot-cell environment. 5 refs., 5 figs

Multi-institutional evaluation of end-to-end protocol for IMRT/VMAT treatment chains utilizing conventional linacs.

Science.gov (United States)

Loughery, Brian; Knill, Cory; Silverstein, Evan; Zakjevskii, Viatcheslav; Masi, Kathryn; Covington, Elizabeth; Snyder, Karen; Song, Kwang; Snyder, Michael

2018-03-20

We conducted a multi-institutional assessment of a recently developed end-to-end monthly quality assurance (QA) protocol for external beam radiation therapy treatment chains. This protocol validates the entire treatment chain against a baseline to detect the presence of complex errors not easily found in standard component-based QA methods. Participating physicists from 3 institutions ran the end-to-end protocol on treatment chains that include Imaging and Radiation Oncology Core (IROC)-credentialed linacs. Results were analyzed in the form of American Association of Physicists in Medicine (AAPM) Task Group (TG)-119 so that they may be referenced by future test participants. Optically stimulated luminescent dosimeter (OSLD), EBT3 radiochromic film, and A1SL ion chamber readings were accumulated across 10 test runs. Confidence limits were calculated to determine where 95% of measurements should fall. From calculated confidence limits, 95% of measurements should be within 5% error for OSLDs, 4% error for ionization chambers, and 4% error for (96% relative gamma pass rate) radiochromic film at 3% agreement/3 mm distance to agreement. Data were separated by institution, model of linac, and treatment protocol (intensity-modulated radiation therapy [IMRT] vs volumetric modulated arc therapy [VMAT]). A total of 97% of OSLDs, 98% of ion chambers, and 93% of films were within the confidence limits; measurements were found outside these limits by a maximum of 4%, consistent despite institutional differences in OSLD reading equipment and radiochromic film calibration techniques. Results from this test may be used by clinics for data comparison. Areas of improvement were identified in the end-to-end protocol that can be implemented in an updated version. The consistency of our data demonstrates the reproducibility and ease-of-use of such tests and suggests a potential role for their use in broad end-to-end QA initiatives. Copyright © 2018 American Association of Medical

Kinematics of a Head-Neck Model Simulating Whiplash

Science.gov (United States)

Colicchia, Giuseppe; Zollman, Dean; Wiesner, Hartmut; Sen, Ahmet Ilhan

2008-01-01

A whiplash event is a relative motion between the head and torso that occurs in rear-end automobile collisions. In particular, the large inertia of the head results in a horizontal translation relative to the thorax. This paper describes a simulation of the motion of the head and neck during a rear-end (whiplash) collision. A head-neck model that…

Computed tomography on a defective CANDU fuel pencil end cap

International Nuclear Information System (INIS)

Lupton, L.R.

1985-09-01

Five tomographic slices through a defective end cap from a CANDU fuel pencil have been generated using a Co-60 source and a first generation translate-rotate tomography scanner. An anomaly in the density distribution that is believed to have resulted from the defect has been observed. However, with the 0.30 mm spatial resolution used, it has not been possible to state unequivocally whether the change in density is caused by a defect in the weld or a statistical anomaly in the data. It is concluded that a microtomography system, with a spatial resolution in the range of 0.1 mm, could detect the flaw

Accuracy of self-reported tobacco assessments in a head and neck cancer treatment population

International Nuclear Information System (INIS)

Warren, Graham W.; Arnold, Susanne M.; Valentino, Joseph P.; Gal, Thomas J.; Hyland, Andrew J.; Singh, Anurag K.; Rangnekar, Vivek M.; Cummings, K. Michael; Marshall, James R.; Kudrimoti, Mahesh R.

2012-01-01

Prospective analysis was performed of self-reported and biochemically confirmed tobacco use in 50 head and neck cancer patients during treatment. With 93.5% compliance to complete weekly self-report and biochemical confirmatory tests, 29.4% of smokers required biochemical assessment for identification. Accuracy increased by 14.9% with weekly vs. baseline self-reported assessments. Data confirm that head and neck cancer patients misrepresent true tobacco use during treatment.

Equipment to take up the axial forces occuring on fuel elements in the operation of a nuclear reactor

International Nuclear Information System (INIS)

Sankovich, M.

1977-01-01

A constructive solution for the spring support of fuel elements between a lower and upper grid is given which prevents vibrations from the influence of axial forces due to thermal expansion and/or coolant flow with the least possible resistance to the coolant flow. As plate or screw springs usually allow certain vibrations or even encourage these, and to compensate for the flow resistance thus caused nominal increase of the total cooling power is necessary, i.e. the total efficiency of the plants is lowered; therefore a combined torsion and spring was constructed. 4 each of these springs surround in an approximately horizontal plane the head of a fuel element containing the usual number of fuel rods. Each spring forms a U seen from above and surrounds the fuel element head on one side completely and about half the length of the two adjacent sides. The three sides of the spring are inbedded in the openings of the fuel element end pieces so as not to cause any nominal resistance for the coolant flow rising from the fuel elements. (HP) [de

A review of the environmental impact of mining and milling of radioactive ores, upgrading processes, and fabrication of nuclear fuels

International Nuclear Information System (INIS)

Costello, J.M.; Davy, D.R.; Cattell, F.C.R.; Cook, J.E.

1980-01-01

The subject is discussed under the headings: uranium mining; milling of uranium ores; manufacture of uranium hexafluoride; uranium enrichment; fuel manufacture and fabrication; environmental impact (use of natural resources; effluents from fuel cycle operations; occupational health; public health); alternative fuel cycles; additional waste treatment. (U.K.)

The EBR-II spent fuel treatment program

International Nuclear Information System (INIS)

Lineberry, M.J.; McFarlane, H.F.

1995-01-01

Argonne National Laboratory has refurbished and equipped an existing hot cell facility for demonstrating a high-temperature electrometallurgical process for treating spent nuclear fuel from the Experimental Breeder Reactor-11. Two waste forms will be produced and qualified for geologic disposal of the fission and activation products. Relatively pure uranium will be separated for storage. Following additional development, transuranium elements will be blended into one of the high-level waste streams. The spent fuel treatment program will help assess the viability of electrometallurgical technology as a spent fuel management option

Advances in HTGR spent fuel treatment technology

International Nuclear Information System (INIS)

Holder, N.D.; Lessig, W.S.

1984-08-01

GA Technologies, Inc. has been investigating the burning of spent reactor graphite under Department of Energy sponsorship since 1969. Several deep fluidized bed burners have been used at the GA pilot plant to develop graphite burning techniques for both spent fuel recovery and volume reduction for waste disposal. Since 1982 this technology has been extended to include more efficient circulating bed burners. This paper includes updates on high-temperature gas-cooled reactor fuel cycle options and current results of spent fuel treatment testing for fluidized and advanced circulating bed burners

Mechanical mastication as a fuels treatment in southeastern forests

Science.gov (United States)

Jesse K. Kreye; J. Morgan Varner; Leda N. Kobziar

2016-01-01

Mastication is an increasingly common fuels treatment that redistributes ‘‘ladder’’ fuels to the forest floor to reduce vertical fuel continuity, crown fire potential, and fireline intensity. Despite its widespread adoption, it remains unclear how mastication impacts fuels, fire behavior, or plant communities  across Southeastern forest ecosystems. We evaluated these...

Back-end fuel cycle efficiencies with respect to improved uranium utilization

International Nuclear Information System (INIS)

Kuczera, B.; Hennies, H.H.

1983-01-01

The world-wide nuclear power plant (NPP) capacity is at present 160 GW(e). If one adds the power stations under construction and ordered, a plant capacity of approximately 480 GW(e) is obtained for 1990, with the share of LWRs making up more than 80%. A modern LWR consumes in the open fuel cycle about 4400 metric tonnes of natural uranium per GW(e), assuming a lifetime of 30 years and a load factor of 70%. Considering the natural uranium reserves known at present and exploitable under economic conditions, it can be conveniently estimated that, with the present NPP capacity extension perspective, the natural uranium resources may be exhausted in a few decades. This trend can be counteracted in a flexible manner by various approaches in fuel cycle technology and strategy: (i) by steady further development of the established LWR technology the uranium consumption can be reduced by about 15%; (ii) closing the nuclear fuel cycle on the basis of LWRs (i.e. thermal uranium and plutonium recycling) implies up to 40% savings in natural uranium consumption; (iii) more recent considerations include the advanced pressurized water reactor (APWR). The APWR combines the proven PWR technology with a newly developed tight lattice core with greatly improved conversion characteristics (conversion ratio = 0.90 to 0.95). In terms of uranium utilization, the APWR has an efficiency three to five times higher than a PWR; (iv) Commercial introduction of FBR systems results in an optimal utilization of uranium which, at the same time, guarantees the supply of nuclear fuel well beyond the present century. For a corresponding transition period an energy supply system can be conceived which relies essentially on extended back-end fuel cycle capacities. These would facilitate a symbiosis of PWR, APWR and FBR, characterized by high flexibility with respect to long-term developments on the energy market. (author)

Pressure loss coefficient and flow rate of side hole in a lower end plug for dual-cooled annular nuclear fuel

Energy Technology Data Exchange (ETDEWEB)

Shin, Chang-Hwan, E-mail: shinch@kaeri.re.kr; Park, Ju-Yong, E-mail: juyong@kaeri.re.kr; In, Wang-Kee, E-mail: wkin@kaeri.re.kr

2013-12-15

Highlights: • A lower end plug with side flow holes is suggested to provide alternative flow paths of the inner channel. • The inlet loss coefficient of the lower end plug is estimated from the experiment. • The flow rate through the side holes is estimated in a complete entrance blockage of inner channel. • The consequence in the reactor core condition is evaluated with a subchannel analysis code. - Abstract: Dual-cooled annular nuclear fuel for a pressurized water reactor (PWR) has been introduced for a significant increase in reactor power. KAERI has been developing a dual-cooled annular fuel for a power uprate of 20% in an optimized PWR in Korea, the OPR1000. This annular fuel can help decrease the fuel temperature substantially relative to conventional cylindrical fuel at a power uprate. Annular fuel has dual flow channels around itself; however, the inner flow channel has a weakness in that it is isolated unlike the outer flow channel, which is open to other neighbouring outer channels for a coolant exchange in the reactor core. If the entrance of the inner channel is, as a hypothetical event, completely blocked by debris, the inner channel will then experience a rapid increase in coolant temperature such that a departure from nucleate boiling (DNB) may occur. Therefore, a remedy to avoid such a postulated accident is indispensable for the safety of annular fuel. A lower end plug with side flow holes was suggested to provide alternative flow paths in addition to the central entrance of the inner channel. In this paper, the inlet loss coefficient of the lower end plug and the flow rate through the side holes were estimated from the experimental results even in a complete entrance blockage of the inner channel. An optimization for the side hole was also performed, and the results are applied to a subchannel analysis to evaluate the consequence in the reactor core condition.

The role of EGFR-targeting strategies in the treatment of head and neck cancer

Directory of Open Access Journals (Sweden)

Dequanter D

2012-07-01

Full Text Available Didier Dequanter, Mohammad Shahla, Pascal Paulus, Philippe H LothaireDepartment of Surgery, CHU Charleroi (Hopital Andre Vésale, Montigny le Tilleul, BelgiumAbstract: With its targeted mechanism of action and synergistic activity with current treatment modalities, cetuximab is a potentially valuable treatment option for patients with recurrent and/or metastatic squamous cell cancer of the head and neck who have progressed on cisplatin-based chemotherapy. The use of cetuximab in combination with radiotherapy as definitive treatment for locoregionally advanced squamous cell cancer of the head and neck is generally restricted to patients unfit to receive cisplatin-based chemoradiation, which is still considered the standard of care. The effect of this epidermal growth factor receptor antagonist occurs without any change in the pattern and the severity of toxicity usually associated with head and neck radiation.Keywords: cetuximab, SCCHN, radiotherapy

Stem cell treatment for avascular necrosis of the femoral head: current perspectives

Directory of Open Access Journals (Sweden)

Houdek MT

2014-04-01

Full Text Available Matthew T Houdek,1 Cody C Wyles,2 John R Martin,1 Rafael J Sierra11Department of Orthopedic Surgery, 2School of Medicine, Mayo Clinic, Rochester, MN, USAAbstract: Avascular necrosis (AVN of the femoral head is a progressive disease that predominantly affects younger patients. Although the exact pathophysiology of AVN has yet to be elucidated, the disease is characterized by a vascular insult to the blood supply of the femoral head, which can lead to collapse of the femoral head and subsequent degenerative changes. If AVN is diagnosed in the early stages of the disease, it may be possible to attempt surgical procedures which preserve the hip joint, including decompression of the femoral head augmented with concentrated bone marrow. The use of autologous stem cells has shown promise in halting the progression of AVN of the femoral head, and subsequently preventing young patients from undergoing total hip arthroplasty. The purpose of this study was to review the current use of stem cells for the treatment of AVN of the femoral head.Keywords: avascular necrosis, femoral head, osteonecrosis, stem cells, concentrated bone marrow

Development of remote welding technology for nuclear fuel end capping (A study on the weldability of Zircaloy-4)

Energy Technology Data Exchange (ETDEWEB)

Kho, Jin Hyun; Sung, Ho Hyun; Hyun, Yong Kyu; Suh, Hee Kang [Korea University of Technology and Education, Cheonan (Korea)

1998-03-01

The integrity of nuclear fuel end cap welds is essential to the nuclear fuel performance and safety as well as the usability of power plant. The first aim of this project is to obtain experimental data on the nuclear fuel cladding materials of Zircaloy-4 with welding processes such as plasma arc, gas tungsten arc and laser beam welding. the data obtained in this study will be applicable to the nuclear fuel design, fabrication and nuclear fuel quality control. In addition, the welding processes applicable to the Zircaloy-4 welding were compared and contrasted. The weldability of Zircaloy-4 was evaluated from the metallurgical and mechanical standpoints. 88 refs., 57 figs., 16 tabs. (Author)

Application of the pulsed magnetic welding process to nuclear breeder reactor fuel pin end closures

International Nuclear Information System (INIS)

Brown, W.F.

1984-01-01

The pulsed magnetic welding process is a solid state welding process in which metallurgical bonding is effected by impacting metal or alloy parts against each other at high velocity by use of controlled high frequency, high intensity pulsed magnetic fields. This process is similar to the explosive welding process except that magnetic energy is used for impacting the parts together instead of using explosive energy. The pulsed magnetic welding (PMW) process is readily applied to the welding of cylindrical plugs to small diameter tubes. Although breeder reactor fuel pin design may vary in size, the application described here consisted of cladding tubes approximately 6.4 mm in diameter by 244 cm long with a wall thickness of 0.38 mm. After the cladding tubes are filled with fuel pellets and associated metal hardware, tapered end plugs are inserted into the end of the tubes and welded. A typical setup for PMW is described

Calculation Of Radon Gas Inhaled By A Front End Worker Of The Nuclear Fuel Cycles

International Nuclear Information System (INIS)

Soedardjo

1996-01-01

The calculation of Radon gas inhaled by workers in a front end nuclear fuel cycle has been studied. The cycle of front end nuclear fuel is underground uranium exploration on Remaja tunnel West Kalimantan. The activities of mining consider of drilling, blasting, transporting mineral and tunnel supporting were chosen, It is assumed that in one month, for a worker has four assignments namely in tunnel I, tunnel II, tunnel III and tunnel IV, The activities in the mine are divided into some categories, namely 12 hours of drilling, 2 hours of after blasting, 9 hours of mineral transportation and 8 hours of tunnel support construction. The result of calculation shows that the average Radon gas concentration on each particular location is still less than maximum permissible concentration 300 pCi/l. The prediction of maximum dose inhaled by one uranium miner during a year is 2.3 x 10 2 μCi which is less than BATAN regulation 7.3 x 10 2 μCi

Spent fuel treatment to allow storage in air

International Nuclear Information System (INIS)

Williams, K.L.

1988-01-01

During Fiscal Year 1987 (FY-87), research began at the Idaho National Engineering Laboratory (INEL) to develop a treatment material and process to coat fuel rods in commercial spent fuel assemblies to allow the assemblies to be stored in hot (up to 380 0 C) air without oxidation of the fuel. This research was conducted under a research and development fund provided by the U.S. Department of Energy (DOE) and independently administered by EG and G Idaho, Inc., DOE's prime contractor at the INEL. The objectives of the research were to identify and evaluate possible treatment processes and materials, identify areas of uncertainty, and to recommend the most likely candidate to allow spent fuel dry storage in hot air. The results of the research are described: results were promising and several good candidates were identified, but further research is needed to examine the candidates to the point where comparison is possible

Scientific research on the back-end of the fuel cycle for the 21. century; Les recherches scientifiques sur l'aval du cycle pour le 21. siecle

Energy Technology Data Exchange (ETDEWEB)

NONE

2000-07-01

The aim of the Atalante-2000 conference is to present the major research axis concerning the nuclear fuel cycle back-end. The different topics are: - Present options concerning fuel cycle back-end; - Reprocessing of spent fuel; - Advanced separation for transmutation; - Processing and packaging of radioactive wastes; - Design and fabrication of targets for transmutation; and - Conversion of military plutonium into MOX fuels.

Fuel nozzle assembly

Science.gov (United States)

Johnson, Thomas Edward [Greer, SC; Ziminsky, Willy Steve [Simpsonville, SC; Lacey, Benjamin Paul [Greer, SC; York, William David [Greer, SC; Stevenson, Christian Xavier [Inman, SC

2011-08-30

A fuel nozzle assembly is provided. The assembly includes an outer nozzle body having a first end and a second end and at least one inner nozzle tube having a first end and a second end. One of the nozzle body or nozzle tube includes a fuel plenum and a fuel passage extending therefrom, while the other of the nozzle body or nozzle tube includes a fuel injection hole slidably aligned with the fuel passage to form a fuel flow path therebetween at an interface between the body and the tube. The nozzle body and the nozzle tube are fixed against relative movement at the first ends of the nozzle body and nozzle tube, enabling the fuel flow path to close at the interface due to thermal growth after a flame enters the nozzle tube.

The nuclear fuel cycle is complete

International Nuclear Information System (INIS)

Hildenbrand, G.

1984-01-01

The nuclear fuel cycle in the Federal Republic of Germany has a firm base. Its entry stages, natural uranium, conversion, enrichment, and fuel fabrication, have not only been put on solid grounds in terms of supplies, but have also attained a high degree of technical maturity and a high quality level. Further efforts are being devoted to cost reductions. Especially higher burnups and the recycling of plutonium in the form of MOX fuel assemblies in light water reactors must be mentioned under this heading. In the field of back end fuel cycle steps, the important sector of interim storage has now found a practical solution, which is also fully sufficient with respect to capacity. The project of a German reprocessing plant has now entered its decisive stage with the filling of the licensing applications and the awarding of the planning contracts. The study on alternative waste management techniques entitled ''Direct Final Storage'' is about to be concluded, and a work on the exploration and development of a repository proceeds on schedule. (orig.) [de

Investigation on Nd:YAG laser weldability of zircaloy-4 end cap closure for nuclear fuel elements

International Nuclear Information System (INIS)

Kim, Soo Sung; Lee, Chul Yung; Yang, Myung Seung

2001-01-01

Various welding processes are now available for end cap closure of nuclear fuel element such as TIG(Tungsten Inert Gas) welding, magnetic resistance welding and laser welding. Even though the resistance and TIG welding processes are widely used for manufacturing commercial fuel elements, they can not be recommended for the remote seal welding of a fuel element at a hot cell facility due to the complexity of electrode alignment, difficulty in the replacement of parts in the remote manner and a large heat input for a thin sheath. Therefore, the Nd:YAG laser system using optical fiber transmission was selected for Zircaloy-4 end cap welding inside hot cell. The laser welding apparatus was developed using a pulsed Nd:YAG laser of 500 watt average power with optical fiber transmission. The weldability of laser welding was satisfactory with respect to the microstructures and mechanical properties comparing with TIG and resistance welding. The optimum operation processes of laser welding and the optical fiber transmission system for hot cell operation in a remote manner have been developed. The effects of irradiation on the properties of the laser apparatus were also being studied

Quantifying the potential impacts of fuel treatments on wildfire suppression costs

Science.gov (United States)

Matthew P. Thompson; Nicole M. Vaillant; Jessica R. Haas; Krista M. Gebert; Keith D. Stockmann

2013-01-01

Modeling the impacts and effects of hazardous fuel reduction treatments is a pressing issue within the wildfire management community. Prospective evaluation of fuel treatment effectiveness allows for comparison of alternative treatment strategies in terms of socioeconomic and ecological impacts and facilitates analysis of tradeoffs across land-management objectives....

Fuel cell generator with fuel electrodes that control on-cell fuel reformation

Science.gov (United States)

Ruka, Roswell J [Pittsburgh, PA; Basel, Richard A [Pittsburgh, PA; Zhang, Gong [Murrysville, PA

2011-10-25

A fuel cell for a fuel cell generator including a housing including a gas flow path for receiving a fuel from a fuel source and directing the fuel across the fuel cell. The fuel cell includes an elongate member including opposing first and second ends and defining an interior cathode portion and an exterior anode portion. The interior cathode portion includes an electrode in contact with an oxidant flow path. The exterior anode portion includes an electrode in contact with the fuel in the gas flow path. The anode portion includes a catalyst material for effecting fuel reformation along the fuel cell between the opposing ends. A fuel reformation control layer is applied over the catalyst material for reducing a rate of fuel reformation on the fuel cell. The control layer effects a variable reformation rate along the length of the fuel cell.

Aspects of welding of zircaloy thin tube to end plugin the experimental welding facility of fuel element fabrication laboratory

International Nuclear Information System (INIS)

Shafy, M.; El-Hakim, E.

1997-01-01

The work was achieved within the scope of developing egyptian nuclear fuel fabrication laboratory in inshas. It showed the results of developing a welding facility for performing a qualified zircaloy-2 and 4 thin tubes to end weld joints. The welding chamber design was developed to get qualified weld for both PWR and CANDU fuel rod configurations. Experimental works for optimizing the welding parameters of tungsten inert gas (TIG) welding and electron beam (EB) welding processes were achieved. The ld penetration deeper than the wall tube thickness can be obtained for qualified end plug weld joints. It recommended to use steel compensating block for radiographic inspection of end plug weld joints. The predominate defects that can be expected in end plug weld joints, are lack of penetration and cavity. The microstructure of the fusion zone and heat affected zones are Widmanstaetten structure and its grain size is drastically sensible to the heat generation and removal of arc welding. 16 figs

Deployment evaluation methodology for the electrometallurgical treatment of DOE-EM spent nuclear fuel

International Nuclear Information System (INIS)

Dahl, C.A.; Adams, J.P.; Ramer, R.J.

1998-07-01

Part of the Department of Energy (DOE) spent nuclear fuel (SNF) inventory may require some type of treatment to meet acceptance criteria at various disposition sites. The current focus for much of this spent nuclear fuel is the electrometallurgical treatment process under development at Argonne National Laboratory. Potential flowsheets for this treatment process are presented. Deployment of the process for the treatment of the spent nuclear fuel requires evaluation to determine the spent nuclear fuel program need for treatment and compatibility of the spent nuclear fuel with the process. The evaluation of need includes considerations of cost, technical feasibility, process material disposition, and schedule to treat a proposed fuel. A siting evaluation methodology has been developed to account for these variables. A work breakdown structure is proposed to gather life-cycle cost information to allow evaluation of alternative siting strategies on a similar basis. The evaluation methodology, while created specifically for the electrometallurgical evaluation, has been written such that it could be applied to any potential treatment process that is a disposition option for spent nuclear fuel. Future work to complete the evaluation of the process for electrometallurgical treatment is discussed

Device for facilitating the insertion and withdrawal of fuel assemblies from a nuclear reactor

International Nuclear Information System (INIS)

Andrea, C.; Siegel, E.A.

1976-01-01

A device is provided which is installed in a reactor prior to carrying out refueling operations and which accurately locates and isolates a selected core location to permit rapid withdrawal and insertion of fuel subassemblies at that location. A shielded plug designed to cooperate with the refueling apparatus is inserted into an access port in the reactor head. A structural shroud extends down from the plug and carries at its lower end a radially floating, hexagonal spreader tube with mechanisms to rotate it for angular alignment purposes and a linear drive for inserting it into the core. The upper end of the spreader tube serves as a guide for leading the fuel handling apparatus into alignment with the chosen subassembly

Modeling of a Membrane Based Humidifier for Fuel Cell Applications Subject to End-Of-Life Conditions

DEFF Research Database (Denmark)

Nielsen, Mads Pagh; Olesen, Anders Christian; Menard, Alan

2014-01-01

applications. For instance for automotive applications and various backup power systems substituting batteries. Humidification of the inlet air of PEM fuel cell stacks is essential to obtain optimum proton conductivity. Operational humidities of the anode and cathode streams having dew points close to the fuel......Proton Exchange Membrane (PEM) Fuel Cell Stacks efficiently convert the chemical energy in hydrogen to electricity through electrochemical reactions occurring on either side of a proton conducting electrolyte. This is a promising and very robust energy conversion process which can be used in many...... cell operating temperature are required. These conditions must be met at the Beginning-Of-Life (BOL) as well as at the End-Of-Life (EOL) of the fuel cell system. This paper presents results of a numerical 1D model of the heat- and mass transport phenomena in a membrane humidifier with a Nafion...

Protective head of sensors

International Nuclear Information System (INIS)

Liska, K.; Anton, P.

1987-01-01

The discovery concerns the protective heads of diagnostic assemblies of nuclear power plants for conductors of the sensors from the fuel and control parts of the said assemblies. A detailed description is presented of the design of the protective head which, as compared with the previous design, allows quick and simple assembly with reduced risk of damaging the sensors. The protective head may be used for diagnostic assemblies both in power and in research reactors and it will be used for WWER reactor assemblies. (A.K.). 3 figs

System and method for consolidating spent fuel rods

International Nuclear Information System (INIS)

Baudro, T.O.

1987-01-01

A system is described for consolidating spent fuel rods from spent fuel assemblies, comprising: a consolidation container in which the fuel rods may be packed; a frame capable of holding a fuel assembly and the container during consolidation, the frame permitting each of the fuel assembly and the container to be removed; tool means with gripper means for gripping and releasing a rod, the tool means including means for moving the gripper means upwardly and downwardly; a first indexing head having first guide means for guiding the gripper means while the gripper means moves downwardly; a first rail, the first indexing head being slidably mounted on the first rail; a second indexing head having second guide means for guiding the gripper means while the gripper means moves downwardly; a second rail, the second indexing head being slidably mounted on the second rail; and a third rail, the first rail and the second rail being slidably mounted on the third rail; wherein the first indexing head is slidable on the first and third rails to a first position that is above a preselected rod in the fuel assembly; and wherein the second indexing head is slidable on the second and third rails to a second position that is above a preselected location in the container

Separations in back-end of nuclear fuel cycle: overview of R and D activities

International Nuclear Information System (INIS)

Bansal, N.K.; Chitnis, R.R.

2004-01-01

This article discusses various areas in back-end of nuclear fuel cycle where R and D activities in separation science are actively pursued. Solvent extraction and ion-exchange are the main techniques where maximum developmental activities are underway. In addition to actual techniques, article also discusses the status of the studies especially where the process has been applied on larger scale. (author)

Using fine-scale fuel measurements to assess wildland fuels, potential fire behavior and hazard mitigation treatments in the southeastern USA

International Nuclear Information System (INIS)

Ottmar, Roger D.; Blake, John I.; Crolly, William T.

2012-01-01

The inherent spatial and temporal heterogeneity of fuelbeds in forests of the southeastern United States may require fine scale fuel measurements for providing reliable fire hazard and fuel treatment effectiveness estimates. In a series of five papers, an intensive, fine scale fuel inventory from the Savanna River Site in the southeastern United States is used for building fuelbeds and mapping fire behavior potential, evaluating fuel treatment options for effectiveness, and providing a comparative analysis of landscape modeled fire behavior using three different data sources including the Fuel Characteristic Classification System, LANDFIRE, and the Southern Wildfire Risk Assessment. The research demonstrates that fine scale fuel measurements associated with fuel inventories repeated over time can be used to assess broad scale wildland fire potential and hazard mitigation treatment effectiveness in the southeastern USA and similar fire prone regions. Additional investigations will be needed to modify and improve these processes and capture the true potential of these fine scale data sets for fire and fuel management planning.

In a bad place: Carers of patients with head and neck cancer experiences of travelling for cancer treatment.

Science.gov (United States)

Balfe, Myles; Keohane, Kieran; O' Brien, Katie; Gooberman-Hill, Rachael; Maguire, Rebecca; Hanly, Paul; O' Sullivan, Eleanor; Sharp, Linda

2017-10-01

To explore the effect that treatment-related commuting has on carers of patients with head and neck cancer. Semi-structured interviews, thematically analysed, with 31 carers. Treatment-related commuting had a considerable impact on carers of patients with head and neck cancer, both in practical terms (economic costs, disruption) and also in psychological terms. Many carers of patients with head and neck cancer described becoming distressed by their commute. Some carers from large urban cities appeared to have hidden commuting burdens. Some carers respond to commuting stress by 'zoning out' or becoming 'like zombies'. Treatment-related travel for head and neck cancer can have significant practical and psychological impacts. Health professionals should be aware of the impacts that commuting can have on head and neck caregivers. Health services may be able to take practical steps, such as providing subsidized parking, to address head and neck carergivers' difficulties. Copyright © 2017 Elsevier Ltd. All rights reserved.

Fission product release assessment for end fitting failure in Candu reactor loaded with CANFLEX-NU fuel bundles

Energy Technology Data Exchange (ETDEWEB)

Oh, Dirk Joo; Jeong, Chang Joon; Lee, Kang Moon; Suk, Ho Chun [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

1998-12-31

Fission product release (FPR) assessment for End Fitting Failure (EFF) in CANDU reactor loaded with CANFLEX-natural uranium (NU) fuel bundles has been performed. The predicted results are compared with those for the reactor loaded with standard 37-element bundles. The total channel I-131 release at the end of transient for EFF accident is calculated to be 380.8 TBq and 602.9 TBq for the CANFLEX bundle and standard bundle channel cases, respectively. They are 4.9% and 7.9% of total inventory, respectively. The lower total releases of the CANFLEX bundle O6 channel are attributed to the lower initial fuel temperatures caused by the lower linear element power of the CANFLEX bundle compared with the standard bundle. 4 refs., 1 fig., 4 tabs. (Author)

Fission product release assessment for end fitting failure in Candu reactor loaded with CANFLEX-NU fuel bundles

Energy Technology Data Exchange (ETDEWEB)

Oh, Dirk Joo; Jeong, Chang Joon; Lee, Kang Moon; Suk, Ho Chun [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

1997-12-31

Fission product release (FPR) assessment for End Fitting Failure (EFF) in CANDU reactor loaded with CANFLEX-natural uranium (NU) fuel bundles has been performed. The predicted results are compared with those for the reactor loaded with standard 37-element bundles. The total channel I-131 release at the end of transient for EFF accident is calculated to be 380.8 TBq and 602.9 TBq for the CANFLEX bundle and standard bundle channel cases, respectively. They are 4.9% and 7.9% of total inventory, respectively. The lower total releases of the CANFLEX bundle O6 channel are attributed to the lower initial fuel temperatures caused by the lower linear element power of the CANFLEX bundle compared with the standard bundle. 4 refs., 1 fig., 4 tabs. (Author)

Estimation of wildfire size and risk changes due to fuels treatments

Science.gov (United States)

Cochrane, M.A.; Moran, C.J.; Wimberly, M.C.; Baer, A.D.; Finney, M.A.; Beckendorf, K.L.; Eidenshink, J.; Zhu, Z.

2012-01-01

Human land use practices, altered climates, and shifting forest and fire management policies have increased the frequency of large wildfires several-fold. Mitigation of potential fire behaviour and fire severity have increasingly been attempted through pre-fire alteration of wildland fuels using mechanical treatments and prescribed fires. Despite annual treatment of more than a million hectares of land, quantitative assessments of the effectiveness of existing fuel treatments at reducing the size of actual wildfires or how they might alter the risk of burning across landscapes are currently lacking. Here, we present a method for estimating spatial probabilities of burning as a function of extant fuels treatments for any wildland fire-affected landscape. We examined the landscape effects of more than 72 000 ha of wildland fuel treatments involved in 14 large wildfires that burned 314 000 ha of forests in nine US states between 2002 and 2010. Fuels treatments altered the probability of fire occurrence both positively and negatively across landscapes, effectively redistributing fire risk by changing surface fire spread rates and reducing the likelihood of crowning behaviour. Trade offs are created between formation of large areas with low probabilities of increased burning and smaller, well-defined regions with reduced fire risk.

Treatment of Head and Neck Cancer in Adults - Health Professional Version

Science.gov (United States)

Find information about prognosis, staging, and treatment for adult head and neck cancer sites: hypopharynx, larynx, lip and oral cavity, neck cancer with occult primary, nasopharynx, oropharynx, paranasal sinus and nasal cavity, and salivary gland cancer.

Measurements of bundle end flux peaking effects in 37-element CANDU PHW fuel

International Nuclear Information System (INIS)

French, P.M.

1977-10-01

Thermal neutron bundle end flux peaking factors have been measured in fresh 37-element Bruce reactor natural UO 2 clusters in heavy water moderator, both with and without staggered plenums at the fuel stack ends, in representative elements throughout the clusters. The measurements were made at a square lattice pitch of 28.58 cm with heavy water coolant. The results indicate that outer element peaking factors are 1.142 +- 0.009 for bundles containing no plenums, and 1.155 +- 0.006 and 1.177 +- 0.006 at the non-plenum and plenum element ends respectively, for bundles containing staggered plenums, irrespective of the azimuthal orientation between pairs of bundles. Measurements are also reported for bundles containing plenums in every outer element, for bundles separated by a stainless steel flux suppressor, for longer graphite plenums, and for changes in plenum and bundle gap lengths. Some theoretical comparisons with the results, reported by other authors, have been summarized. (author)

Fuel cycle services

International Nuclear Information System (INIS)

Gruber, Gerhard J.

1990-01-01

TRIGA reactor operators are increasingly concerned about the back end of their Fuel Cycle due to a new environmental policy in the USA. The question how to close the Fuel Cycle will have to be answered by all operators sooner or later. Reprocessing of the TRIGA fuel elements is not available. Only long term storage and final disposal can be considered. But for such a storage or disposal a special treatment of the fuel elements and of course a final depository is necessary. NUKEM plans to undertake efforts to assist the TRIGA operators in this area. For that reason we need to know your special needs for today and tomorrow - so that potential processors can consider whether to offer these services on the market. (orig.)

Analysis of head motion prior to and during proton beam therapy

International Nuclear Information System (INIS)

Schulte, Reinhard W.; Fargo, Ramiz A.; Meinass, Helmut J.; Slater, Jerry D.; Slater, James M.

2000-01-01

Purpose: We report on the use of a noninvasive patient motion monitoring system to evaluate the amount of head motion prior to and during proton radiation therapy sessions. Methods and Materials: Two optical displacement sensors, placed close to the patient's head, were used for online monitoring of the head position, with submillimeter accuracy. Motion data, including the difference between start and end position (Dx) and the maximum displacement during the recorded session (Dx-max), were acquired for pretreatment sessions to analyze alignment radiographs, and for treatment sessions. We have recorded 102 pretreatment and 99 treatment sessions in 16 patients immobilized with a thermoplastic mask, and 44 pretreatment and 56 treatment sessions in 13 patients immobilized with vacuum-assisted dental fixation. To avoid incorrect data analysis due to replicate observations, only 1 pretreatment and 1 treatment session per patient were selected at random for statistical comparison of mean or median motion parameters in different subgroups. Results: Both techniques showed similar immobilization efficiencies. The median Dx and Dx-max values were 0.18 mm and 0.46 mm, respectively, for 16 treatment sessions with mask immobilization, and 0.22 mm and 0.50 mm, respectively, for 13 treatment sessions with dental immobilization. Motion parameters for pretreatment and treatment sessions were not statistically different. Conclusion: Online verification of patient's head motion is feasible and provides valuable data for confirmation of proper treatment delivery in individual patients, as well as for the evaluation of different immobilization methods

Electrometallurgical treatment of TMI-2 fuel debris

International Nuclear Information System (INIS)

Karell, E.J.; Gourishankar, K.V.; Johnson, G.K.

1997-01-01

Argonne National Laboratory (ANL) has developed an electrometallurgical treatment process suitable for conditioning DOE oxide spent fuel for long-term storage or disposal. The process consists of an initial oxide reduction step that converts the actinide oxides to a metallic form, followed by an electrochemical separation of uranium from the other fuel constituents. The final product of the process is a uniform set of stable waste forms suitable for long-term storage or disposal. The suitability of the process for treating core debris from the Three Mile Island-2 (TMI-2) reactor is being evaluated. This paper reviews the results of preliminary experimental work performed using simulated TMI-2 fuel debris

Nonrigid Image Registration for Head and Neck Cancer Radiotherapy Treatment Planning With PET/CT

International Nuclear Information System (INIS)

Ireland, Rob H.; Dyker, Karen E.; Barber, David C.; Wood, Steven M.; Hanney, Michael B.; Tindale, Wendy B.; Woodhouse, Neil; Hoggard, Nigel; Conway, John; Robinson, Martin H.

2007-01-01

Purpose: Head and neck radiotherapy planning with positron emission tomography/computed tomography (PET/CT) requires the images to be reliably registered with treatment planning CT. Acquiring PET/CT in treatment position is problematic, and in practice for some patients it may be beneficial to use diagnostic PET/CT for radiotherapy planning. Therefore, the aim of this study was first to quantify the image registration accuracy of PET/CT to radiotherapy CT and, second, to assess whether PET/CT acquired in diagnostic position can be registered to planning CT. Methods and Materials: Positron emission tomography/CT acquired in diagnostic and treatment position for five patients with head and neck cancer was registered to radiotherapy planning CT using both rigid and nonrigid image registration. The root mean squared error for each method was calculated from a set of anatomic landmarks marked by four independent observers. Results: Nonrigid and rigid registration errors for treatment position PET/CT to planning CT were 2.77 ± 0.80 mm and 4.96 ± 2.38 mm, respectively, p = 0.001. Applying the nonrigid registration to diagnostic position PET/CT produced a more accurate match to the planning CT than rigid registration of treatment position PET/CT (3.20 ± 1.22 mm and 4.96 ± 2.38 mm, respectively, p = 0.012). Conclusions: Nonrigid registration provides a more accurate registration of head and neck PET/CT to treatment planning CT than rigid registration. In addition, nonrigid registration of PET/CT acquired with patients in a standardized, diagnostic position can provide images registered to planning CT with greater accuracy than a rigid registration of PET/CT images acquired in treatment position. This may allow greater flexibility in the timing of PET/CT for head and neck cancer patients due to undergo radiotherapy

Analytical chemistry needs for nuclear safeguards in nuclear fuel reprocessing

International Nuclear Information System (INIS)

Hakkila, E.A.

1977-01-01

A fuel reprocessing plant designed to process 1500 tons of light water reactor fuel per year will recover 15 tons of Pu during that time, or approximately 40 to 50 kg of Pu per day. Conventional nuclear safeguards accountability has relied on batch accounting at the head and tail ends of the reprocessing plant with semi-annual plant cleanout to determine in-process holdup. An alternative proposed safeguards system relies on dynamic material accounting whereby in-line NDA and conventional analytical techniques provide indications on a daily basis of SNM transfers into the system and information of Pu holdup within the system. Some of the analytical requirements and problems for dynamic materials accounting in a nuclear fuel reprocessing plant are described. Some suggestions for further development will be proposed

Fuels planning: science synthesis and integration; forest structure and fire hazard fact sheet 05: fuel treatment principles for complex landscapes

Science.gov (United States)

Rocky Mountain Research Station USDA Forest Service

2004-01-01

Appropriate types of thinning and surface fuel treatments are clearly useful in reducing surface and crown fire hazards under a wide range of fuels and topographic situations. This paper provides well-established scientific principles and simulation tools that can be used to adjust fuel treatments to attain specific risk levels.

Session 1984-1985. Radioactive waste. Minutes of evidence, Monday 13 May 1985. British Nuclear Fuels plc

Energy Technology Data Exchange (ETDEWEB)

1985-01-01

The Environment Select Committee of the House of Commons received a memorandum from British Nuclear Fuels plc on the treatment and preparation for disposal of radioactive wastes, under the headings: introduction; waste categories; waste management policy; waste arisings; waste treatment plans; appendix I - British Nuclear Fuels plc; appendix II - the nuclear fuel cycle for Magnox, AGR and LWR reactors; appendix III - control of liquid radioactive discharges from Sellafield and their environmental impact. Representatives of BNF plc were examined on the subject of the memorandum and the minutes of evidence are recorded.

Session 1984-85. Radioactive waste. Minutes of evidence, Monday 13 May 1985. British Nuclear Fuels plc

International Nuclear Information System (INIS)

1985-01-01

The Environment Select Committee of the House of Commons received a memorandum from British Nuclear Fuels plc on the treatment and preparation for disposal of radioactive wastes, under the headings: introduction; waste categories; waste management policy; waste arisings; waste treatment plans; appendix I - British Nuclear Fuels plc; appendix II - the nuclear fuel cycle for Magnox, AGR and LWR reactors; appendix III - control of liquid radioactive discharges from Sellafield and their environmental impact. Representatives of BNF plc were examined on the subject of the memorandum and the minutes of evidence are recorded. (U.K.)

A Study of the Effect of the Front-End Styling of Sport Utility Vehicles on Pedestrian Head Injuries

Directory of Open Access Journals (Sweden)

Guanjun Zhang

2018-01-01

Full Text Available Background. The number of sport utility vehicles (SUVs on China market is continuously increasing. It is necessary to investigate the relationships between the front-end styling features of SUVs and head injuries at the styling design stage for improving the pedestrian protection performance and product development efficiency. Methods. Styling feature parameters were extracted from the SUV side contour line. And simplified finite element models were established based on the 78 SUV side contour lines. Pedestrian headform impact simulations were performed and validated. The head injury criterion of 15 ms (HIC15 at four wrap-around distances was obtained. A multiple linear regression analysis method was employed to describe the relationships between the styling feature parameters and the HIC15 at each impact point. Results. The relationship between the selected styling features and the HIC15 showed reasonable correlations, and the regression models and the selected independent variables showed statistical significance. Conclusions. The regression equations obtained by multiple linear regression can be used to assess the performance of SUV styling in protecting pedestrians’ heads and provide styling designers with technical guidance regarding their artistic creations.

Modeling fuel treatment leverage: Encounter rates, risk reduction, and suppression cost impacts

Science.gov (United States)

Matthew P. Thompson; Karin L. Riley; Dan Loeffler; Jessica R. Haas

2017-01-01

The primary theme of this study is the cost-effectiveness of fuel treatments at multiple scales of investment. We focused on the nexus of fuel management and suppression response planning, designing spatial fuel treatment strategies to incorporate landscape features that provide control opportunities that are relevant to fire operations. Our analysis explored the...

Hydrothermal treatment of grape marc for solid fuel applications

International Nuclear Information System (INIS)

Mäkelä, Mikko; Kwong, Chi Wai; Broström, Markus; Yoshikawa, Kunio

2017-01-01

Highlights: • The effects of treatment temperature and liquid pH on char and liquid properties. • Liquid pH had a statistically significant effect only on liquid carbon yield. • Higher treatment temperature increased char volatiles that can enhance ignitability. • Char showed promising fuel properties if elevated ash phosphorus can be tolerated. - Abstract: The treatment and disposal of grape marc, a residue from grape processing, represents a significant economic and environmental challenge for the winemaking industry. Hydrothermal treatment of grape marc could be an efficient way for producing solid fuels on-site at the wineries. In this work the effects of treatment temperature and liquid pH on grape marc char and liquid properties were determined based on laboratory experiments and the combustion characteristics of char were assessed through thermogravimetric analysis and fuel ash classification. The results showed that hydrothermal treatment increased the energy and carbon contents and decreased the ash content of grape marc. The effect of liquid pH was statistically significant (p < 0.05) only for the determined carbon yield of liquid samples. The energy yield from grape marc was maximized at lower treatment temperatures, which also decreased the content of less thermally stable compounds in the attained char. Higher treatment temperatures decreased grape marc solid, carbon and energy yields and led to an increase in thermally labile compounds compared to lower temperatures likely due to the condensation of liquid compounds or volatiles trapped in the pores of char particles. The alkali metal contents of char ash were reduced coupled with an increase in respective phosphorus. Overall the results support the use of hydrothermally treated grape marc in solid fuel applications, if elevated levels of ash phosphorus can be tolerated.

Microcontroller based automation system for end plug welding of test fuel pins in solgel facility

International Nuclear Information System (INIS)

Prabhakar Rao, J.; Srinivas, K.C.; Prabhu, T.V.; Ravi, N.

2010-01-01

A microcontroller based stepper motor control and driver Unit for 'XY' positioning system is designed and developed to perform the 'pick-place' of fuel tube to pre-determined coordinates. This Unit provides a fine movement of the fuel tube to get perfect position for welding. The Graphical User Interface software running on PC displays the absolute position of the XY system and provides all the required control buttons to achieve the accurate positioning. The welding of clad tube with end plug is carried out in a high precision welding fixture by operating it remotely. This paper discusses about the Hardware and Software features and implementation of the instrumentation. (author)

Recent advancements of chemical engineering in front end fuel cycle technologies at NFC. Contributed Paper IT-01

International Nuclear Information System (INIS)

Saibaba, N.

2014-01-01

On front end fuel cycle side, Nuclear Fuel Complex (NFC) has been a pioneer in processing the uranium and zirconium ore concentrates from different sources. The uranium and zirconium ore concentrates are converted into nuclear grade uranium and zirconium di oxide powders through the conventional TBP purification and precipitation route. In case of zirconium powders, they are converted into pure nuclear grade zirconium sponge through chlorination route for the production of zirconium alloys, which are mainly used as reactor core structural material

Using Sankey diagrams to map energy flow from primary fuel to end use

International Nuclear Information System (INIS)

Subramanyam, Veena; Paramshivan, Deepak; Kumar, Amit; Mondal, Md. Alam Hossain

2015-01-01

Highlights: • Energy flows from both supply and demand sides shown through Sankey diagrams. • Energy flows from reserves to energy end uses for primary and secondary fuels shown. • Five main energy demand sectors in Alberta are analyzed. • In residential/commercial sectors, highest energy consumption is in space heating. • In the industrial sector, highest energy use is in the mining subsector. - Abstract: The energy sector is the largest contributor to gross domestic product (GDP), income, employment, and government revenue in both developing and developed nations. But the energy sector has a significant environmental footprint due to greenhouse gas (GHG) emissions. Efficient production, conversion, and use of energy resources are key factors for reducing the environmental footprint. Hence it is necessary to understand energy flows from both the supply and the demand sides. Most energy analyses focus on improving energy efficiency broadly without considering the aggregate energy flow. We developed Sankey diagrams that map energy flow for both the demand and supply sides for the province of Alberta, Canada. The diagrams will help policy/decision makers, researchers, and others to understand energy flow from reserves through to final energy end uses for primary and secondary fuels in the five main energy demand sectors in Alberta: residential, commercial, industrial, agricultural, and transportation. The Sankey diagrams created for this study show total energy consumption, useful energy, and energy intensities of various end-use devices. The Long-range Energy Alternatives Planning System (LEAP) model is used in this study. The model showed that Alberta’s total input energy in the five demand sectors was 189 PJ, 186 PJ, 828.5PJ, 398 PJ, and 50.83 PJ, respectively. On the supply side, the total energy input and output were found to be 644.84 PJ and 239 PJ, respectively. These results, along with the associated energy flows were depicted pictorially using

Quantification of Back-End Nuclear Fuel Cycle Metrics Uncertainties Due to Cross Sections

International Nuclear Information System (INIS)

Tracy E. Stover Jr.

2007-01-01

This work examines uncertainties in the back end fuel cycle metrics of isotopic composition, decay heat, radioactivity, and radiotoxicity. Most advanced fuel cycle scenarios, including the ones represented in this work, are limited by one or more of these metrics, so that quantification of them becomes of great importance in order to optimize or select one of these scenarios. Uncertainty quantification, in this work, is performed by propagating cross-section covariance data, and later number density covariance data, through a reactor physics and depletion code sequence. Propagation of uncertainty is performed primarily via the Efficient Subspace Method (ESM). ESM decomposes the covariance data into singular pairs and perturbs input data along independent directions of the uncertainty and only for the most significant values of that uncertainty. Results of these perturbations being collected, ESM directly calculates the covariance of the observed output posteriori. By exploiting the rank deficient nature of the uncertainty data, ESM works more efficiently than traditional stochastic sampling, but is shown to produce equivalent results. ESM is beneficial for very detailed models with large amounts of input data that make stochastic sampling impractical. In this study various fuel cycle scenarios are examined. Simplified, representative models of pressurized water reactor (PWR) and boiling water reactor (BWR) fuels composed of both uranium oxide and mixed oxides are examined. These simple models are intended to give a representation of the uncertainty that can be associated with open uranium oxide fuel cycles and closed mixed oxide fuel cycles. The simplified models also serve as a demonstration to show that ESM and stochastic sampling produce equivalent results, because these models require minimum computer resources and have amounts of input data small enough such that either method can be quickly implemented and a numerical experiment performed. The simplified

Treatment of late sequelae after radiotherapy for head and neck cancer.

Science.gov (United States)

Strojan, Primož; Hutcheson, Katherine A; Eisbruch, Avraham; Beitler, Jonathan J; Langendijk, Johannes A; Lee, Anne W M; Corry, June; Mendenhall, William M; Smee, Robert; Rinaldo, Alessandra; Ferlito, Alfio

2017-09-01

Radiotherapy (RT) is used to treat approximately 80% of patients with cancer of the head and neck. Despite enormous advances in RT planning and delivery, a significant number of patients will experience radiation-associated toxicities, especially those treated with concurrent systemic agents. Many effective management options are available for acute RT-associated toxicities, but treatment options are much more limited and of variable benefit among patients who develop late sequelae after RT. The adverse impact of developing late tissue damage in irradiated patients may range from bothersome symptoms that negatively affect their quality of life to severe life-threatening complications. In the region of the head and neck, among the most problematic late effects are impaired function of the salivary glands and swallowing apparatus. Other tissues and structures in the region may be at risk, depending mainly on the location of the irradiated tumor relative to the mandible and hearing apparatus. Here, we review the available evidence on the use of different therapeutic strategies to alleviate common late sequelae of RT in head and neck cancer patients, with a focus on the critical assessment of the treatment options for xerostomia, dysphagia, mandibular osteoradionecrosis, trismus, and hearing loss. Copyright © 2017 Elsevier Ltd. All rights reserved.

Mitigating fuel handling situations during station blackout in TAPP-3 and

International Nuclear Information System (INIS)

Chugh, V.K.; Roy, Shibaji; Gupta, H.; Inder Jit

2002-01-01

Full text: On power refueling is one of the important features of PHWRs. fuelling machine (FM) Head becomes part of the reactor pressure boundary during refueling operations. Hot irradiated (spent) fuel bundles are received in the FM Head from the Reactor and transferred to spent fuel storage bay (SFSB). These bundles pass through various fuel handling (FH) Equipment under submerged condition except during the dry transfer operation. Situations of station blackout (SBO) i.e. postulated simultaneous failure of Class III and Class IV electric power, could persist for a long period, during on-reactor or off-reactor FH operations, with the spent fuel bundles being any where in the system between the reactor and SFSB. The cooling provisions for the spent fuel bundles vary depending upon the stage of operation. During SBO, it becomes difficult to maintain cooling to these fuel bundles due to the limited availability of Class II power and instrument air. However, cooling is essential, to ensure the safety of the bundles. As discussed in the paper, safety of these fuel bundles in the system and/or for those lying in the liner tube region of the reactor end fitting is ensured, during SBO, by resorting to passive means like stay-put, gravity- fill, D 2 O-steaming etc. for cooling the bundles. Various scenarios have been identified for cooling provisions of the bundles in the system. The paper also describes consequences like loss of D 2 O inventory, rise in ambient temperature and pressure and tritium build-up in Reactor Building, emanating from these cooling schemes

Demonstration and development of safeguards techniques in the PNC reprocessing plant. Part of a coordinated programme on the use of installed instrumentation in fuel reprocessing facilities for safeguards purposes

International Nuclear Information System (INIS)

Kurihara, H.

1979-04-01

A hull-monitoring system in the Head-End facility and systems for surveillance and containment in the spent fuel receiving and storage facility at Tokai Reprocessing Plant are described. Operating experience on them is analyzed

Fuels planning: science synthesis and integration; forest structure and fire hazard fact sheet 04: role of silviculture in fuel treatments

Science.gov (United States)

Rocky Mountain Research Station USDA Forest Service

2004-01-01

The principal goals of fuel treatments are to reduce fireline intensities, reduce the potential for crown fires, improve opportunities for successful fire suppression, and improve forest resilience to forest fires. This fact sheet discusses thinning, and surface fuel treatments, as well as challenges associated with those treatments.

BONE GRAFTING ENHANCED BY PLATELET-RICH PLASMA IN TREATMENT OF AVASCULAR NECROSIS OF FEMORAL HEAD

Directory of Open Access Journals (Sweden)

A. A. Korytkin

2018-01-01

Full Text Available Treatment of avascular necrosis of the femoral head is an issue of current interest while it affects young and employable people. So far there is no well-defined strategy of management which would help to postpone hip arthroplasty and further revision procedure. Hip sparing surgical treatment of avascular necrosis of the femoral head by bone grafting prior to head collapse proved to be a viable option not only during early stages of disease but also at advanced stages. Platelet-rich plasma (PRP addition to treatment plan potentially helps improving bone regeneration in situ.In this article the authors present a case of a 37 years old patient with avascular necrosis of the femoral head at a fragmentation stage (type 4B by ARCO. The authors centrifuged 15 ml of autologous whole blood (1500 RPM obtained by a special double-contoured syringe. During the surgical stage of treatment PRP and morselized bone graft were mixed to introduce and impact into the debrided zone of avascular necrosis. The authors also introduced 0.3–0.4 ml of PRP into the debrided zone of avascular necrosis after bone grafting. At 6 months follow-up CT images of the studied patient demonstrated signs of bone reorganization and no loss of femoral head sphericity. Preoperative Visual Analogue Scale (VAS, Harris Hip Score (HHS and Hip disability and Osteoarthritis Outcome Score (HOOS prior to treatment were 60, 45 and 33 points respectively. Postoperative VAS, HHS and HOOS scores were 10, 78 and 78 respectively. In the authors’ opinion, impaction bone grafting enhanced by PRP helps obtaining good and excellent outcomes not only at early but also at advanced stages of avascular necrosis.

Nuclear fuel pellet charging device

International Nuclear Information System (INIS)

Komuro, Kojiro.

1990-01-01

The present invention concerns a nuclear fuel pellet loading device, in which nuclear fuel pellets are successively charged from an open end of a fuel can while rotating the can. That is, a fuel can sealed at one end with an end plug and opened at the other end is rotated around its pipe axis as the center on a rotationally diriving table. During rotation of the fuel can, nuclear fuel pellets are successively charged by means of a feed rod of a feeding device to the inside of the fuel can. The fuel can is rotated while being supported horizontally and the fuel pellets are charged from the open end thereof. Alternatively, the fuel can is rotated while being supported obliquely and the fuel pellets are charged gravitationally into the fuel can. In this way, the damages to the barrier of the fuel can can be reduce. Further, since the fuel pellets can be charged gravitationally by rotating the fuel can while being supported obliquely, the damages to the barrier can be reduced remarkably. (I.S.)

Treatment of Head and Neck Paragangliomas With External Beam Radiation Therapy

International Nuclear Information System (INIS)

Dupin, Charles; Lang, Philippe; Dessard-Diana, Bernadette; Simon, Jean-Marc; Cuenca, Xavier; Mazeron, Jean-Jacques; Feuvret, Loïc

2014-01-01

Purpose: To retrospectively assess the outcomes of radiation therapy in patients with head and neck paragangliomas. Methods and Materials: From 1990 to 2009, 66 patients with 81 head and neck paragangliomas were treated by conventional external beam radiation therapy in 25 fractions at a median dose of 45 Gy (range, 41.4-68 Gy). One case was malignant. The median gross target volume and planning target volume were 30 cm 3 (range, 0.9-243 cm 3 ) and 116 cm 3 (range, 24-731 cm 3 ), respectively. Median age was 57.4 years (range, 15-84 years). Eleven patients had multicentric lesions, and 8 had family histories of paraganglioma. Paragangliomas were located in the temporal bone, the carotid body, and the glomus vagal in 51, 18, and 10 patients, respectively. Forty-six patients had exclusive radiation therapy, and 20 had salvage radiation therapy. The median follow-up was 4.1 years (range, 0.1-21.2 years). Results: One patient had a recurrence of temporal bone paraganglioma 8 years after treatment. The actuarial local control rates were 100% at 5 years and 98.7% at 10 years. Patients with multifocal tumors and family histories were significantly younger (42 years vs 58 years [P=.002] and 37 years vs 58 years [P=.0003], respectively). The association between family predisposition and multifocality was significant (P<.001). Two patients had cause-specific death within the 6 months after irradiation. During radiation therapy, 9 patients required hospitalization for weight loss, nausea, mucositis, or ophthalmic zoster. Two late vascular complications occurred (middle cerebral artery and carotid stenosis), and 2 late radiation-related meningiomas appeared 15 and 18 years after treatment. Conclusion: Conventional external beam radiation therapy is an effective and safe treatment option that achieves excellent local control; it should be considered as a first-line treatment of choice for head and neck paragangliomas

Challenges and approaches in planning fuel treatments across fire-excluded forested landscapes

Science.gov (United States)

B.M. Collins; S.L. Stephens; J.J. Moghaddas; J. Battles

2010-01-01

Placing fuel reduction treatments across entire landscapes such that impacts associated with high-intensity fire are lessened is a difficult goal to achieve, largely because of the immense area needing treatment. As such, fire scientists and managers have conceptually developed and are refining methodologies for strategic placement of fuel treatments that...

Quantifying the potential impacts of fuel treatments on wildfire suppression costs volume

Science.gov (United States)

Matthew P. Thompson; Nicole M. Vaillant; Jessica R. Haas; Krista M. Gebert; Keith D. Stockmann

2013-01-01

Modeling the impacts and effects of hazardous fuel reduction treatments is a pressing issue within the wildfire management community. Prospective evaluation of fuel treatments allows for comparison of alternative treatment strategies in terms of socioeconomic and ecological impacts and facilitates analysis of tradeoffs across land management objectives (Stockmann et al...

Burner and dissolver off-gas treatment in HTR fuel reprocessing

International Nuclear Information System (INIS)

Barnert-Wiemer, H.; Heidendael, M.; Kirchner, H.; Merz, E.; Schroeder, G.; Vygen, H.

1979-01-01

In the reprocessing of HTR fuel, essentially all of the gaseous fission products are released during the heat-end tratment, which includes burning of the graphite matrix and dissolving of the heavy metallic residues in THOREX reagent. Three facilities for off-gas cleaning are described, the status of the facility development and test results are reported. Hot tests with a continuous dissolver for HTR-type fuel (throughput 2 kg HM/d) with a closed helium purge loop have been carried out. Preliminary results of these experiments are reported

Fuels planning: science synthesis and integration; environmental consequences fact sheet 04: wildlife responses to fuels treatments: key considerations

Science.gov (United States)

David Pilliod

2004-01-01

Managers face a difficult task in predicting the effects of fuels treatments on wildlife populations, mostly because information on how animals respond to fuels treatments is scarce or does not exist. This paper discusses key considerations-aspects of an animal's ecology and available information-that, despite the scarcity of information, may make predictions of...

Fact sheet on fuel manufacturing and utilization

International Nuclear Information System (INIS)

2006-01-01

The Nuclear Fuel Cycle and Materials Section (NFCMS) supports Member States to improve in-pile fuel performance and management of materials; and to develop advanced fuel technologies for ensuring reliability and economic efficiency of the nuclear fuel cycle, provides assistance to Member States to support fuel-manufacturing capability, including quality assurance techniques, optimization of manufacturing parameters and radiation protection, supports the development fuel modeling expertise in Member States, covering both normal operation and postulated and severe accident conditions, provides information and support for the operation of Nuclear Power Plant to ensure that the environment and water chemistry is appropriate for fuel operation, supports fuel failure investigations, including equipment for failed fuel detection and for post-irradiation examination and inspection, as well as fuel repair, provides information and support research into the basic properties of fuel materials, including UO2, MOX, (Th, Pu)O2, (Th, U233)O2 fuels and zirconium alloy cladding and fuel assembly components and offers guidance on the relationship with back-end requirement (interim storage, transport, reprocessing, disposal), fuel utilization and management, MOX fuels, alternative fuels and advanced fuel technology and materials, economic and other aspects of nuclear fuel use (e.g. environmental impact). Recently NFCMS provided support to a Member State manufacturing Gadolinia doped fuel and provided in-mast sipping equipment to a Nuclear Power Plant to allow the determination of fuel failure. Member States interested in fuel performance and manufacture should contact the Technical Cooperation Department of the Agency and Member States interested in knowing more about the Agency's programme on source management should contact: C. Ganguly, Section Head, V. Inozemtsev, J. Killeen

Front-end and back-end electrochemistry of molten salt in accelerator-driven transmutation systems

International Nuclear Information System (INIS)

Williamson, M.A.; Venneri, F.

1995-01-01

The objective of this work is to develop preparation and clean-up processes for the fuel and carrier salt in the Los Alamos Accelerator-Driven Transmutation Technology molten salt nuclear system. The front-end or fuel preparation process focuses on the removal of fission products, uranium, and zirconium from spent nuclear fuel by utilizing electrochemical methods (i.e., electrowinning). The same method provides the separation of the so-called noble metal fission products at the back-end of the fuel cycle. Both implementations would have important diversion safeguards. The proposed separation processes and a thermodynamic analysis of the electrochemical separation method are presented

Fast breeder reactor fuel reprocessing R and D: technological development for a commercial plant

International Nuclear Information System (INIS)

Colas, J.; Saudray, D.; Coste, J.A.; Roux, J.P.; Jouan, A.

1987-01-01

The technological developments undertaken by the CEA are applied to a plant project of a 50 t/y capacity, having to reprocess in particular the SUPERPHENIX 1 reactor fuel. French experience on fast breeder reactor fuel reprocessing is presented, then the 50 t/y capacity plant project and the research and development installations. The R and D programs are described, concerning: head-end operations, solvent extractions, Pu02 conversion and storage, out-of-specification Pu02 redissolution, fission products solution vitrification, conditioning of stainless steel hulls by melting, development of remote operation equipments, study of corrosion and analytical problems

Bioremediation of diesel fuel contaminated soils

International Nuclear Information System (INIS)

Troy, M.A.; Jerger, D.E.

1992-01-01

Bioremediation techniques were successfully employed in the cost-effective cleanup of approximately 8400 gallons of diesel fuel which had been accidentally discharged at a warehouse in New Jersey. Surrounding soils were contaminated with the diesel fuel at concentrations exceeding 1,470 mg/kg total petroleum hydrocarbons as measured by infrared spectroscopy (TPH-IR, EPA method 418.1, modified for soils). This paper reports on treatment of the contaminated soils through enhanced biological land treatment which was chosen for the soil remediation pursuant to a New Jersey Pollutant Discharge Elimination System - Discharge to Ground Water (NJPDES-DGW) permit. Biological land treatment of diesel fuel focuses on the breakdown of the hydrocarbon fractions by indigenous aerobic microorganisms in the layers of soil where oxygen is made available. Metabolism by these microorganisms can ultimately reduce the hydrocarbons to innocuous end products. The purpose of biological land treatment was to reduce the concentration of the petroleum hydrocarbon constituents of the diesel fuel in the soil to 100 ppm total petroleum hydrocarbons (TPH)

Patient Choice of Nonsurgical Treatment Contributes to Disparities in Head and Neck Squamous Cell Carcinoma.

Science.gov (United States)

Parhar, Harman S; Anderson, Donald W; Janjua, Arif S; Durham, J Scott; Prisman, Eitan

2018-06-01

Objectives There are well-established outcome disparities among different demographic groups with head and neck squamous cell carcinoma (HNSCC). We aimed to investigate the potential contribution of patient choice of nonsurgical treatment to these disparities by estimating the rate of this phenomenon, identifying its predictors, and estimating the effect on cancer-specific survival. Study Design Retrospective nationwide analysis. Settings Surveillance, Epidemiology, and End Results Database (2004-2014). Subjects and Methods Patients with HNSCC, who were recommended for primary surgery, were included. Multivariable logistic regression was used to identify demographic and clinical factors associated with patient choice of nonsurgical treatment, and Kaplan Meier/Cox regression was used to analyze survival. Results Of 114,506 patients with HNSCC, 58,816 (51.4%) were recommended for primary surgery, and of those, 1550 (2.7%) chose nonsurgical treatment. Those who chose nonsurgical treatment were more likely to be older (67.1 ± 12.6 vs 63.6 ± 13.1, P unmarried (OR married, 0.50; 95% CI, 0.44-0.58), had an advanced tumor, and had a hypopharyngeal or laryngeal primary. Choice of nonsurgical treatment imparted a 2.16-fold (95% CI, 2.02-2.30) increased risk of cancer-specific death. Conclusion Of the patients, 2.7% chose nonsurgical treatment despite a provider recommendation that impairs survival. Choice of nonsurgical treatment is associated with older age, having Black or Asian ethnicity, being unmarried, having an advanced stage tumor, and having a primary site in the hypopharynx or larynx. Knowledge of these disparities may help providers counsel patients and help patients make informed decisions.

Monte Carlo simulation of radiation treatment machine heads

International Nuclear Information System (INIS)

Mohan, R.

1988-01-01

Monte Carlo simulations of radiation treatment machine heads provide practical means for obtaining energy spectra and angular distributions of photons and electrons. So far, most of the work published in the literature has been limited to photons and the contaminant electrons knocked out by photons. This chapter will be confined to megavoltage photon beams produced by medical linear accelerators and 60 Co teletherapy units. The knowledge of energy spectra and angular distributions of photons and contaminant electrons emerging from such machines is important for a variety of applications in radiation dosimetry

Evaluation of strategies for end storage of high-level reactor fuel; Vurdering av strategier for sluttlagring av hoeyaktivt reaktorbrensel

Energy Technology Data Exchange (ETDEWEB)

NONE

2001-07-01

This report evaluates a national strategy for end-storage of used high-level reactor fuel from the research reactors at Kjeller and in Halden. This strategy presupposes that all the important phases in handling the high-level material, including temporary storage and deposition, are covered. The quantity of spent fuel from Norwegian reactors is quite small. In addition to the technological issues, ethical, environmental, safety and economical requirements are emphasized.

Biocidal treatment and preservation of liquid fuels

Energy Technology Data Exchange (ETDEWEB)

Siegert, W.

1995-05-01

Strict microbiological limit values are the result of damage caused by microorganisms in fuels. With MAR 71, a biocide based on methylenebisoxazolidine, a product is available which has been tested and approved by leading car manufacturers, the mineral oil industry, and NATO. Depending on the degree of microbiological contamination, different decontamination concepts are presented, and recommendations for the treatment of fuels which are contaminated when purchased are given. In order to avoid recontamination, planning principles or the new design of tanks are necessary. The possibility of convenient, economical and regular drainage is a key factor.

Final Environmental Impact Statement for the Treatment and Management of Sodium-Bonded Spent Nuclear Fuel

International Nuclear Information System (INIS)

2000-01-01

DOE is responsible for the safe and efficient management of its sodium-bonded spent nuclear fuel. This fuel contains metallic sodium, a highly reactive material; metallic uranium, which is also reactive; and in some cases, highly enriched uranium. The presence of reactive materials could complicate the process of qualifying and licensing DOE's sodium-bonded spent nuclear fuel inventory for disposal in a geologic repository. Currently, more than 98 percent of this inventory is located at the Idaho National Engineering and Environmental Laboratory (INEEL), near Idaho Falls, Idaho. In addition, in a 1995 agreement with the State of Idaho, DOE committed to remove all spent nuclear fuel from Idaho by 2035. This EIS evaluates the potential environmental impacts associated with the treatment and management of sodium-bonded spent nuclear fuel in one or more facilities located at Argonne National Laboratory-West (ANL-W) at INEEL and either the F-Canyon or Building 105-L at the Savannah River Site (SRS) near Aiken, South Carolina. DOE has identified and assessed six proposed action alternatives in this EIS. These are: (1) electrometallurgical treatment of all fuel at ANL-W, (2) direct disposal of blanket fuel in high-integrity cans with the sodium removed at ANL-W, (3) plutonium-uranium extraction (PUREX) processing of blanket fuel at SRS, (4) melt and dilute processing of blanket fuel at ANL-W, (5) melt and dilute processing of blanket fuel at SRS, and (6) melt and dilute processing of all fuel at ANL-W. In addition, Alternatives 2 through 5 include the electrometallurgical treatment of driver fuel at ANL-W. Under the No Action Alternative, the EIS evaluates both the continued storage of sodium-bonded spent nuclear fuel until the development of a new treatment technology or direct disposal without treatment. Under all of the alternatives, the affected environment is primarily within 80 kilometers (50 miles) of spent nuclear fuel treatment facilities. Analyses indicate

Nuclear fuel assembly

International Nuclear Information System (INIS)

Hayashi, Hiroshi; Watari, Yoshio; Hizahara, Hiroshi; Masuoka, Ryuzo.

1970-01-01

When exchanging nuclear fuel assemblies during the operation of a nuclear reactor, melting of fuel bodies, and severence of tubular claddings is halted at the time of insertion by furnishing a neutron absorbing material such as B 10 , Cd, Gd or the like at the forward end of the fuel assembly to thereby lower the power peak at the forward ends of the fuel elements to within tolerable levels and thus prevent both fuel liquification and excessive expansion. The neutron absorbing material may be attached in the form of a plate to the fuel assembly forward tie plate, or may be inserted as a pellet into the front end of the tubular cladding. (Owens, K.J.)

The conceptual flowsheet of effluent treatment during preparing spherical fuel elements of HTR

Energy Technology Data Exchange (ETDEWEB)

Ying, Quan, E-mail: quanying@tsinghua.edu.cn; Xiao-tong, Chen; Bing, Liu; Gen-na, Fu; Yang, Wang; You-lin, Shao; Zhen-ming, Lu; Ya-ping, Tang; Chun-he, Tang

2014-05-01

High temperature gas-cooled reactor (HTR) is one of the advanced nuclear reactors owing to its inherent safety and broad applications. For HTR, one of the key components is the ceramic fuel element. During the preparation of spherical fuel elements, the radioactive effluent treatment is necessary. Referring to the current treatment technologies and methods, the conceptual flowsheet of low-level radioactive effluent treatment during preparing spherical fuel elements was established. According to the above treatment process, the uranium concentration was decreased from 200 mg/l to the level of discharged standard.

Peaceful nuclear programme and front end nuclear fuel cycle activities in Pakistan

International Nuclear Information System (INIS)

S. Mukhtar Ahmed

1999-01-01

Pakistan has a modest but broad based nuclear programme related to peaceful uses of atomic energy in nuclear power, agriculture, medicine and industry. While development projects in these areas form the major segment of Pakistan Atomic Energy Commission's work, complimentary activities in basic research and human resource development are also supported. PAEC through its activities has been moving towards the goal of achieving self-reliance for its existing programme in an international atmosphere of embargoes and restrictions and in pursuit of creating an infrastructure to help sustain an indigenous nuclear power programme. To solve the local needs and requirements, radioisotopes and nuclear techniques have been applied in agriculture, medicine, hydrology and industry. PAEC has one large research and development establishment in physical sciences, three R and D centers in agriculture, one in biotechnology, and ten nuclear medical centers for diagnostics and oncology treatment. Two research reactors form nucleus of research and development activities in nuclear sciences. In the power sector a 137 Mew CANDU power reactor is in operation in Karachi since 1971. Another 300 Mew PWR is under construction and is nearing completion. Front-end fuel cycle and engineering infrastructure facilities have been established to support continued operation of Karachi Nuclear Power Plant (KANUPP). To support the engineering activities it has established facilities for precision workshops, non-destructive testing center and a welding institute. (author)

Fuel assembly supporting structure

International Nuclear Information System (INIS)

Aisch, F.W.; Fuchs, H.P.; Knoedler, D.; Steinke, A.; Steven, J.

1976-01-01

For use in forming the core of a pressurized-water reactor, a fuel assembly supporting structure for holding a bundle of interspaced fuel rods, is formed by interspaced end pieces having holes in which the end portions of control rod guide tubes are inserted, fuel rod spacer grids being positioned by these guide tubes between the end pieces. The end pieces are fastened to the end portions of the guide tubes, to integrate the supporting structure, and in the case of at least one of the end pieces, this is done by means which releases that end piece from the guide tubes when the end pieces receive an abnormal thrust force directed towards each other and which would otherwise place the guide tubes under a compressive stress that would cause them to buckle. The spacer grids normally hold the fuel rods interspaced by distances determined by nuclear physics, and buckling of the control rod guide tubes can distort the fuel rod spacer grids with consequent dearrangement of the fuel rod interspacing. A sudden loss of pressure in a pressurized-water reactor pressure vessel can result in the pressurized coolant in the vessel discharging from the vessel at such high velocity as to result in the abnormal thrust force on the end pieces of each fuel assembly, which could cause buckling of the control rod guide tubes when the end pieces are fixed to them in the normal rigid and unyielding manner

Clinical response and safety of malathion shampoo for treatment of head lice in a primary school.

Science.gov (United States)

Wananukul, Siriwan; Chatproedprai, Susheera; Tempark, Therdpong; Wananukul, Winai

2011-04-01

Help eradicate or at least alleviating head lice in a primary school with malathion shampoo and to study clinical response and safety of malathion shampoo. All students were examined by using a fine-toothed lice comb to help detect live lice. Direct visual examination and the collection of nits for microscopic examination were performed to differentiate viable nits from empty nits. Diagnosis of head lice was made by the presence of lice. All students that had lice and/or nits were treated with malathion shampoo. Malathion shampoo was also provided for all family members. Pediculocidal efficacy was by the presence or absence of live lice. Blood for red blood cell cholinesterase activity was drawn in 32 volunteers before treatment and after the second treatment. At the first visit, 629 students were examined and 48 students had live head lice. The infestation rate was 13% in girls and 1.3% in boys. The cure rate was 93% after the first treatment. The reported side effects were nausea, a burning sensation, and irritation that was found in five (4%), 10 (7%) and three (2%) students respectively. The mean of RBC cholinesterase activity before and after two applications showed significant changes (p = 0.03). It was -7.5 +/- 4.1% reduction from the initial, but all were in the normal range. There was no report of clinical manifestation of malathion toxicity. Malathion shampoo is safe and effective in the treatment of head lice. There is significant skin absorption so a scalp examination for head lice should be done before subsequent application to avoid unnecessary exposure.

Prophylactic treatment of mycotic mucositis in radiotherapy of patients with head and neck cancers

Energy Technology Data Exchange (ETDEWEB)

Koc, M.; Aktas, E. [Ataturk Univ., Erzurum (Turkey). Medical School

2003-02-01

Patients undergoing radiotherapy for head and neck cancer are at increased risk of developing oral candidiasis. The objective of this study was to investigate the clinical Candida mucositis and interruptions in radiotherapy in patients suffering from head and neck cancer, receiving fluconazole in comparison with a control group without specific prophylaxis. Eighty consecutive patients were randomized in a prospective double-blind trial of prophylactic oral fluconazole or treatment with the same drug when mycotic infections appeared. Adult head and neck cancer patients who were undergoing treatment with radiotherapy and/or chemotherapy, radiotherapeutic coverage of the entire oropharynx and oral cavity at least 3 cm anterior to the retromolar trigone and receiving a total dose of more than 6000 cGy and Karnofsky Performance Status (KPS) >70 were included in the study. Group A received radiation therapy plus fluconazole (Fluzole 100 mg/day) starting from the sixth irradiation session throughout the treatment; 40 patients in group B received the same baseline treatment, but were given fluconazole only when mycotic infections appeared. We evaluated 37 patients in group A and the first 37 patients were evaluated in group B. Three of the patients in group A (8.1%) and 14 of the patients in group B (37.8%) demonstrated clinical candidasis. Radiotherapy was interrupted in all of these patients. The differences between the two groups were statistically significant with respect to clinical candidiasis (P=0.005). The median discontinuation time was 5 days (range, 3-7 days) in group A and 7 days (range, 4-10 days) in group B. The median dose resulting in clinical candidiasis was 3200 cGy (range, 2200-5800 cGy) in all groups. In the fluconazole group it was 4200 cGy and in the control group 2800 cGy. These results suggest that patients undergoing head and neck radiation therapy are at risk of developing candidiasis and that fluconazole may be used to reduce the frequency of

Prophylactic treatment of mycotic mucositis in radiotherapy of patients with head and neck cancers

International Nuclear Information System (INIS)

Koc, M.; Aktas, E.

2003-01-01

Patients undergoing radiotherapy for head and neck cancer are at increased risk of developing oral candidiasis. The objective of this study was to investigate the clinical Candida mucositis and interruptions in radiotherapy in patients suffering from head and neck cancer, receiving fluconazole in comparison with a control group without specific prophylaxis. Eighty consecutive patients were randomized in a prospective double-blind trial of prophylactic oral fluconazole or treatment with the same drug when mycotic infections appeared. Adult head and neck cancer patients who were undergoing treatment with radiotherapy and/or chemotherapy, radiotherapeutic coverage of the entire oropharynx and oral cavity at least 3 cm anterior to the retromolar trigone and receiving a total dose of more than 6000 cGy and Karnofsky Performance Status (KPS) >70 were included in the study. Group A received radiation therapy plus fluconazole (Fluzole 100 mg/day) starting from the sixth irradiation session throughout the treatment; 40 patients in group B received the same baseline treatment, but were given fluconazole only when mycotic infections appeared. We evaluated 37 patients in group A and the first 37 patients were evaluated in group B. Three of the patients in group A (8.1%) and 14 of the patients in group B (37.8%) demonstrated clinical candidasis. Radiotherapy was interrupted in all of these patients. The differences between the two groups were statistically significant with respect to clinical candidiasis (P=0.005). The median discontinuation time was 5 days (range, 3-7 days) in group A and 7 days (range, 4-10 days) in group B. The median dose resulting in clinical candidiasis was 3200 cGy (range, 2200-5800 cGy) in all groups. In the fluconazole group it was 4200 cGy and in the control group 2800 cGy. These results suggest that patients undergoing head and neck radiation therapy are at risk of developing candidiasis and that fluconazole may be used to reduce the frequency of

End-to-end tests using alanine dosimetry in scanned proton beams

Science.gov (United States)

Carlino, A.; Gouldstone, C.; Kragl, G.; Traneus, E.; Marrale, M.; Vatnitsky, S.; Stock, M.; Palmans, H.

2018-03-01

This paper describes end-to-end test procedures as the last fundamental step of medical commissioning before starting clinical operation of the MedAustron synchrotron-based pencil beam scanning (PBS) therapy facility with protons. One in-house homogeneous phantom and two anthropomorphic heterogeneous (head and pelvis) phantoms were used for end-to-end tests at MedAustron. The phantoms were equipped with alanine detectors, radiochromic films and ionization chambers. The correction for the ‘quenching’ effect of alanine pellets was implemented in the Monte Carlo platform of the evaluation version of RayStation TPS. During the end-to-end tests, the phantoms were transferred through the workflow like real patients to simulate the entire clinical workflow: immobilization, imaging, treatment planning and dose delivery. Different clinical scenarios of increasing complexity were simulated: delivery of a single beam, two oblique beams without and with range shifter. In addition to the dose comparison in the plastic phantoms the dose obtained from alanine pellet readings was compared with the dose determined with the Farmer ionization chamber in water. A consistent systematic deviation of about 2% was found between alanine dosimetry and the ionization chamber dosimetry in water and plastic materials. Acceptable agreement of planned and delivered doses was observed together with consistent and reproducible results of the end-to-end testing performed with different dosimetric techniques (alanine detectors, ionization chambers and EBT3 radiochromic films). The results confirmed the adequate implementation and integration of the new PBS technology at MedAustron. This work demonstrates that alanine pellets are suitable detectors for end-to-end tests in proton beam therapy and the developed procedures with customized anthropomorphic phantoms can be used to support implementation of PBS technology in clinical practice.

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

Energy Technology Data Exchange (ETDEWEB)

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

2016-10-15

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

Measuring the effect of fuel treatments on forest carbon using landscape risk analysis

Directory of Open Access Journals (Sweden)

A. A. Ager

2010-12-01

Full Text Available Wildfire simulation modelling was used to examine whether fuel reduction treatments can potentially reduce future wildfire emissions and provide carbon benefits. In contrast to previous reports, the current study modelled landscape scale effects of fuel treatments on fire spread and intensity, and used a probabilistic framework to quantify wildfire effects on carbon pools to account for stochastic wildfire occurrence. The study area was a 68 474 ha watershed located on the Fremont-Winema National Forest in southeastern Oregon, USA. Fuel reduction treatments were simulated on 10% of the watershed (19% of federal forestland. We simulated 30 000 wildfires with random ignition locations under both treated and untreated landscapes to estimate the change in burn probability by flame length class resulting from the treatments. Carbon loss functions were then calculated with the Forest Vegetation Simulator for each stand in the study area to quantify change in carbon as a function of flame length. We then calculated the expected change in carbon from a random ignition and wildfire as the sum of the product of the carbon loss and the burn probabilities by flame length class. The expected carbon difference between the non-treatment and treatment scenarios was then calculated to quantify the effect of fuel treatments. Overall, the results show that the carbon loss from implementing fuel reduction treatments exceeded the expected carbon benefit associated with lowered burn probabilities and reduced fire severity on the treated landscape. Thus, fuel management activities resulted in an expected net loss of carbon immediately after treatment. However, the findings represent a point in time estimate (wildfire immediately after treatments, and a temporal analysis with a probabilistic framework used here is needed to model carbon dynamics over the life cycle of the fuel treatments. Of particular importance is the long-term balance between emissions from the

Measuring the effect of fuel treatments on forest carbon using landscape risk analysis

Science.gov (United States)

Ager, A. A.; Finney, M. A.; McMahan, A.; Cathcart, J.

2010-12-01

Wildfire simulation modelling was used to examine whether fuel reduction treatments can potentially reduce future wildfire emissions and provide carbon benefits. In contrast to previous reports, the current study modelled landscape scale effects of fuel treatments on fire spread and intensity, and used a probabilistic framework to quantify wildfire effects on carbon pools to account for stochastic wildfire occurrence. The study area was a 68 474 ha watershed located on the Fremont-Winema National Forest in southeastern Oregon, USA. Fuel reduction treatments were simulated on 10% of the watershed (19% of federal forestland). We simulated 30 000 wildfires with random ignition locations under both treated and untreated landscapes to estimate the change in burn probability by flame length class resulting from the treatments. Carbon loss functions were then calculated with the Forest Vegetation Simulator for each stand in the study area to quantify change in carbon as a function of flame length. We then calculated the expected change in carbon from a random ignition and wildfire as the sum of the product of the carbon loss and the burn probabilities by flame length class. The expected carbon difference between the non-treatment and treatment scenarios was then calculated to quantify the effect of fuel treatments. Overall, the results show that the carbon loss from implementing fuel reduction treatments exceeded the expected carbon benefit associated with lowered burn probabilities and reduced fire severity on the treated landscape. Thus, fuel management activities resulted in an expected net loss of carbon immediately after treatment. However, the findings represent a point in time estimate (wildfire immediately after treatments), and a temporal analysis with a probabilistic framework used here is needed to model carbon dynamics over the life cycle of the fuel treatments. Of particular importance is the long-term balance between emissions from the decay of dead trees

Effects of fuel treatments on carbon-disturbance relationships in forests of the northern Rocky Mountains

Science.gov (United States)

Elizabeth Reinhardt; Lisa Holsinger

2010-01-01

Fuel treatments alter conditions in forested stands at the time of the treatment and subsequently. Fuel treatments reduce on-site carbon and also change the fire potential and expected outcome of future wildfires, including their carbon emissions. We simulated effects of fuel treatments on 140 stands representing seven major habitat type groups of the northern Rocky...

What are Head Cavities? - A History of Studies on Vertebrate Head Segmentation.

Science.gov (United States)

Kuratani, Shigeru; Adachi, Noritaka

2016-06-01

Motivated by the discovery of segmental epithelial coeloms, or "head cavities," in elasmobranch embryos toward the end of the 19th century, the debate over the presence of mesodermal segments in the vertebrate head became a central problem in comparative embryology. The classical segmental view assumed only one type of metamerism in the vertebrate head, in which each metamere was thought to contain one head somite and one pharyngeal arch, innervated by a set of cranial nerves serially homologous to dorsal and ventral roots of spinal nerves. The non-segmental view, on the other hand, rejected the somite-like properties of head cavities. A series of small mesodermal cysts in early Torpedo embryos, which were thought to represent true somite homologs, provided a third possible view on the nature of the vertebrate head. Recent molecular developmental data have shed new light on the vertebrate head problem, explaining that head mesoderm evolved, not by the modification of rostral somites of an amphioxus-like ancestor, but through the polarization of unspecified paraxial mesoderm into head mesoderm anteriorly and trunk somites posteriorly.

A randomized controlled trial of positioning treatments in infants with positional head shape deformities.

Science.gov (United States)

Hutchison, B Lynne; Stewart, Alistair W; De Chalain, Tristan B; Mitchell, Edwin A

2010-10-01

Randomized controlled trials of treatment for deformational plagiocephaly and brachycephaly have been lacking in the literature. Infants (n = 126) presenting to a plagiocephaly clinic were randomized to either positioning strategies or to positioning plus the use of a Safe T Sleep™ positioning wrap. Head shape was measured using a digital photographic technique, and neck function was assessed. They were followed up at home 3, 6 and 12 months later. There was no difference in head shape outcomes for the two treatment groups after 12 months of follow-up, with 42% of infants having head shapes in the normal range by that time. Eighty per cent of children showed good improvement. Those that had poor improvement were more likely to have both plagiocephaly and brachycephaly and to have presented later to clinic. Most infants improved over the 12-month study period, although the use of a sleep positioning wrap did not increase the rate of improvement. © 2010 The Author(s)/Journal Compilation © 2010 Foundation Acta Paediatrica.

Evaluation of radiotherapy methods for adaptative head and neck treatment with RapidArc®

International Nuclear Information System (INIS)

Mazaro, Sarah J.; Vasconcellos, Herminiane L.; Silva, Laura E. da; Bastos, Fernanda M.; Silva, Leonardo P. da; Alvaro S; Migoviski, Igor

2015-01-01

Head and neck cancer is considered a public health problem worldwide. The intensity-modulated techniques have shown benefit in the treatment of these sites, particularly with respect to reduction of deterministic effects of risk, such as parotid. Anatomical variations in cases of head and neck are very frequent and may lead, for example, to an overdose in the parotid. This can be mitigated if making use of adaptive radiation therapy. The work aims to analyze a methodology to redo the planning of treatments, through 02 acquisitions of TC. The results showed that, due to a reduction in the volumes of the parotid, the doses delivered to these organs are underestimated, which is relevant to readapt the treatment, with the addition of only a second scan without the need of the third. (author)

The back end of the nuclear fuel cycle: Technical and economic analysis-Part 2

International Nuclear Information System (INIS)

Roglans-Ribas, J.; Spinrad, B.I.

1990-01-01

The back end of the nuclear fuel cycle has been analyzed under current conditions in the United States, including the constraints imposed by the Nuclear Waste Policy Act of 1982 and its amendments. The scenarios for two closed cycles, a regular reprocessing cycle and a reprocessing scheme with cesium and strontium fractionation, are described. The storage of spent fuel discharged from the reactors and the disposal of reprocessed waste are studied for both reprocessing cycles. The economics of waste storage and disposal for the two closed cycles are compared with each other and with the reference once-through cycle. The results show that a standard reprocessing cycle results in the minimum cost for storage and disposal. When reporcessing costs are considered, the closed cycles can compete economically with the once-through cycle only if net reprocessing costs are very low

Fuel rod with axial regions of annular and standard fuel pellets

International Nuclear Information System (INIS)

Freeman, T.R.

1991-01-01

This patent describes a fuel rod for use in a nuclear reactor fuel assembly. It comprises: an elongated hollow cladding tube; a pair of end plugs connected to and sealing the cladding tube at opposite ends of thereof; and an axial stack of fuel pellets contained in and extending between the end plugs at the opposite ends of the tube, all of the fuel pellets contained in the tube being composed of fissile material being enriched above the level of natural enrichment; the fuel pellets in the stack thereof being provided in an arrangement of axial regions. The arrangement of axial regions including a pair of first axial regions defined respectively at the opposite ends of the pellet stack adjacent to the respective end plugs. The pellets in the first axial regions being identical in number and having annular configurations with an annulus of a first void size. The arrangement of axial regions also including another axial region defined between the first axial regions, some of the pellets in the another axial region having solid configurations

Treatment of lymphangiomas of the head and neck in children by intralesional injection of OK-432 (Picibanil).

Science.gov (United States)

Brewis, C; Pracy, J P; Albert, D M

2000-04-01

The treatments previously used for lymphangiomas of the head and neck in children-surgery and intralesional injection of sclerosants-are associated with significant morbidity. A new treatment-intralesional injection of OK-432-was used for lymphangiomas of the head and neck in 11 children. The results were total shrinkage in two, marked shrinkage in two, slight shrinkage in five and no response in two. The results were not affected by previous surgery nor by whether aspiration prior to injection was possible. There were no recurrences in those children in whom shrinkage occurred and no child had subsequent surgery following injection. The results of this series support those of previous series showing that OK-432 injection is an effective and safe treatment for lymphangiomas of the head and neck in children.

Back-end of the research reactor fuel cycle

International Nuclear Information System (INIS)

Gruber, Gehard J.

1996-01-01

This paper outlines the status of topics and issues related to: (1) Research Reactor Spent Nuclear Fuel Return to the U.S., including policy, shipments and ports of entry, management sites, fees, storage technologies, contracts, actual shipment, and legal process, (2) UKAEA: MTR Spent Nuclear Fuel Reprocessing, (3) COGEMA: MTR Spent Nuclear Fuel Reprocessing, and (4) Intermediate Storage + Direct Disposal for Research Reactors. (author)

Radiation exposure monitoring and control in front-end fuel cycle facilities

International Nuclear Information System (INIS)

Khan, A.H.

2003-01-01

The front end nuclear fuel cycle facilities presently operational in India are the mining and processing of beach mineral sands along the southern coast of Kerala, Tamilnadu and Orissa, mining and processing of uranium ore in Singhbhum-East in Jharkhand and refining and fuel fabrication at Hyderabad and Trombay. Dedicated Health Physics Units set up at each site regularly carry out in-plant and personnel monitoring to ensure safe working conditions and evaluate radiation exposure of workers and advise appropriate control measures. External gamma radiation, radon, thoron, their progeny and airborne long-lived activity due to radioactive dust are monitored. Personal dosimeters are also issued to workers. The total radiation exposure of workers from external and internal sources is evaluated from the plant and personal monitoring data. Provision of adequate ventilation, control of dust and spillage of active solutions, prompt decontamination, use of personal protective appliances and worker education are the key factors in keeping the doses to the workers well within the regulatory limits. It has been observed that the total radiation dose to workers has been well below 20 mSv.y - 1 at all stages of operations. The monitoring methodologies and summary of radiation exposure data for different facilities during the last few years are presented in the paper. (author)

Fuel and nuclear fuel cycle

International Nuclear Information System (INIS)

Prunier, C.

1998-01-01

The nuclear fuel is studied in detail, the best choice and why in relation with the type of reactor, the properties of the fuel cans, the choice of fuel materials. An important part is granted to the fuel assembly of PWR type reactor and the performances of nuclear fuels are tackled. The different subjects for research and development are discussed and this article ends with the particular situation of mixed oxide fuels ( materials, behavior, efficiency). (N.C.)

Determination of end-of-life-failure fractions of HTGR-fuel particles by postirradiation annealing and beta autoradiography

International Nuclear Information System (INIS)

Thiele, B.A.; Herren, M.

1978-11-01

Fission-product contamination of the helium coolant of High-Temperature Gas-Cooled Reactors (HTGR) is strongly influenced by the end-of-life (EOL) failed-particle fraction. Knowledge of the EOL-failure fraction is the basis for model calculations to predict the total fission product release from the reactor core. After disintegration of irradiation fuel rods, fuel particles are placed in individual holes of a graphite tray. During a 5-h heat treatment at 1000 0 C in a helium atmosphere failed particles leak fission products, especially the volatile cesium, into the graphite. After unloading a β-autoradiograph of the tray is made. Holes that housed defective particles are identified from black spots on the β-sensitive film. The EOL-failure fraction is the ratio of defective particles to the total number of particles tested. The technique is called PIAA, PostIrradiation Annealing and Autoradiography. The PIAA technique was applied to particles of a Trisocoated highly-enriched UO 2 fissile batch irradiated to a burnup of 35% FIMA at an irradiation temperature of 1250 0 C. Visual examination showed all particles to be intact. From 11 to 47% of the particles had failed, as determined by PIAA. Further, postirradiation examination showed that localized corrosion of the silicon carbide coating by fission-product rare-earth chlorides had occurred

The treatment of cancer in the head and neck

International Nuclear Information System (INIS)

Sato, Yasuo; Nomura, Yasunari; Kobayashi, Takeo; Inouye, Kenbun; Kumazawa, Akiyoshi

1979-01-01

1,438 cases of head and neck tumors were seen in our clinic during the period from 1965 - 1978. Under our multidisciplinary treatment, average dosage of radiation for nasal-paranasal tumors was 200 rad, for oral-mesopharyngeal tumors 1,800 rad, for nasopharyngeal tumors 2,400 rad, for laryngeal tumors 3,400 rad and for hypopharyngeal tumors 4,400 rad. After reduction of tumor mass and topical cleaning procedure, 1) a dosage of radiation-number of patients curve shifted to lower left, 2) repeated surgeries for recurrences became less frequent, 3) extended surgeries were unnecessary and 4) social rehabilitation of patients was obtained much easier even in aged. Principles of our treatment were simple: short hospitalization and careful long term follow-up. Treatment plan should be decided according to clinical finding and course of illness in each cases. (author)

Viewpoint of utilities regarding fuel management of nuclear power plants

International Nuclear Information System (INIS)

Held, C.; Moraw, G.; Schneeberger, M.; Szeless, A.

1977-01-01

The engagement of utilities in nuclear power requires them to engage in an increasing amount of fuel management activities in order to carry out all the tasks involved. Essentially, these activities involve two main areas: The procurement of all steps of the fuel cycle from the head to the back end; and in-core fuel management. A general survey of the different steps of the nuclear fuel cycle is presented together with the related activities and responsibilities which have to be borne by the utilities. Today's increasing utility involvement in the nuclear fuel management is shown, as well as future fuel management trends. The fuel management activities of the utilities are analysed with respect to organizational, technical, safeguarding, and financial aspects. The active participation of the utilities in fuel management helps to achieve high availability and flexibility of the nuclear power plant during its whole life as well as safe waste isolation. This can be ensured by continuous optimization of all fuel management aspects of the power plant or, on a larger scale, of a power plant system, i.e. activities by utilities to minimize fuel-cycle effects on the environment, which include optimization of fuel behaviour, and radiation exposure to the public and personnel; and technical and economic evaluations by utilities of out- and in-core fuel management. (author)

Development in the manufacture of fuel assembly components at Nuclear Fuel Complex

International Nuclear Information System (INIS)

Saibaba, N.

2012-01-01

The integrity of the fuel bundle and pellet-clad mechanical and chemical interaction (PCMCI) is the major limiting factor in achieving high burn up in thermal as well as fast reactors. Zircaloy based fuel bundle used for Indian pressurized heavy water reactor consists of number of components such as fuel clad tube, end cap bearing pad and spacer pad. These tubular, bar and sheet components are manufactured at Nuclear Fuel Complex using a series of thermomechanical processes involving hot and cold working with intermediate heat treatment. This paper is aimed at bringing out recent advances in NFC in the manufacture of fuel assembly components. Zircaloy based double clad tube adopting co-extrusion route followed by cold pilgering was successfully produced for its potential usage for high burnup in advance thermal reactors such as Advanced Heavy Water Reactors, This paper also includes process modifications carried out in the manufacture of clad tube and end cap components based on in-depth metallurgical studies. A radial forging process was established for primary breakdown of arc melted ingot which allows for better soundness and homogeneous microstructure. Manufacturing route of bar components for end caps was suitably modified by adopting only barrel straightening to minimize the residual stress and thereby increasing the recovery appreciably. NFC also supplies clad tube for fast breeder reactors where limiting factor for burn up are void swelling and fuel-clad interaction. In view of this, advance claddings such as P/M based 9Cr - Oxide Dispersion strengthened (ODS) steel clad and Zirconium lined T91 (9Cr-1 Mo) steel double clad have been successfully produced. Zirconium lined T91 (9Cr-1 Mo) double clad tubes required was successfully produced by adopting the method of co-pilgering, as a candidate material for clad tubes of Fast Breeder Reactors. (author)

Electrometallurgical treatment of metallic spent nuclear fuel stored at the Hanford Site

International Nuclear Information System (INIS)

Laidler, J.J.; Gay, E.C.

1996-01-01

The major component of the DOE spent nuclear fuel inventory is the metallic fuel stored at the Hanford site in the southeastern part of the state of Washington. Most of this fuel was discharged from the N-Reactor; a small part of the inventory is fuel from the early Hanford production reactors. The U.S. Department of Energy (DOE) plans to remove these fuels from the spent fuel storage pools in which they are presently stored, dry them, and place them in interim storage at a location at the Hanford site that is far removed from the Columbia River. It is not yet certain that these fuels will be acceptable for disposal in a mined geologic repository without further treatment, due to their potential pyrophoric character. A practical method for treatment of the Hanford metallic spent fuel, based on an electrorefining process, has been developed and has been demonstrated with unirradiated N-Reactor fuel and with simulated single-pass reactor (SPR) spent fuel. The process can be operated with any desired throughput rates; being a batch process, it is simply a matter of setting the size of the electrorefiner modules and the number of such modules. A single module, prototypic of a production-scale module, has been fabricated and testing is in progress at a throughput rate of 150 kg (heavy metal) per day. The envisioned production version would incorporate additional anode baskets and cathode tubes and provide a throughput rate of 333 kgHM/day. A system with four of these modules would permit treatment of Hanford metallic fuels at a rate of at least 250 metric tons per year

The back end of the fuel cycle and CANDU

International Nuclear Information System (INIS)

Allan, C.J.; Dormuth, K.W.

2001-01-01

CANDU reactor operators have benefited from several advantages of the CANDU system and from AECL's experience, with regard to spent fuel handling, storage and disposal. AECL has over 20 years experience in development and application of medium-term storage and research and development on the disposal of used fuel. As a result of AECL's experience, short-term and medium-term storage and the associated handling of spent CANDU fuel are well proven and economic, with an extremely high degree of public and environmental protection. In fact, both short-term (water-pool) and medium-term (dry canister) storage of CANDU fuel are comparable or lower in cost per unit of energy than for PWRs. Both pool storage and dry spent fuel storage are fully proven, with many years of successful, safe operating experience. AECL's extensive R and D on the permanent disposal of spent-fuel has resulted in a defined concept for Canadian fuel disposal in crystalline rock. This concept was recently confirmed as ''technically acceptable'' by an independent environmental review panel. Thus, the Canadian program represents an international demonstration of the feasibility and safety of geological disposal of nuclear fuel waste. Much of the technology behind the Canadian concept can be adapted to permanent land-based disposal strategies chosen by other countries. In addition, the Canadian development has established a baseline for CANDU fuel permanent disposal costs. Canadian and international work has shown that the cost of permanent CANDU fuel disposal is similar to the cost of LWR fuel disposal per unit of electricity produced. (author)

Targeted therapies and radiation for the treatment of head and neck cancer

International Nuclear Information System (INIS)

Kim, Gwi Eon

2004-01-01

The purpose of this review is to provide an update on novel radiation treatments for head and neck cancer. Despite the remarkable advances in chemotherapy and radiotherapy techniques, the management of advanced head and neck cancer remains challenging. Epidermal growth factor receptor (EGFR) is an appealing target for novel therapies in head and neck cancer because not only EGFR activation stimulates many important signaling pathways associated with cancer development and progression, and importantly, resistance to radiation. Furthermore, EGFR overexpression is known to be portended for a worse outcome in patients with advanced head and neck cancer. Two categories of compounds designed to abrogate EGFR signaling, such as monoclonal antibodies (Cetuximab) and tyrosine kinase inhibitors (ZD1839 and OSI-774) have been assessed and have been most extensively studied in preclinical models and clinical trials. Additional TKIs in clinical trials include a reversible agent, Cl-1033, which blocks activation of all erbB receptors. Encouraging preclinical data for head and neck cancers resulted in rapid translation into the clinic. Results from initial clinical trials show rather surprisingly that only minority of patients benefited from EGFR inhibition as monotherapy or in combination with chemotherapy. In this review, we begin with a brief summary of erbB-mediated signal transduction. Subsequently, we present data on prognostic-predictive value of erbB receptor expression in HNC followed by preclinical and clinical data on the role of EGFR antagonists alone or in combination with radiation in the treatment of HNC. Finally, we discuss the emerging thoughts on resistance to EGFR blockade and efforts in the development of multiple-targeted therapy for combination with chemotherapy or radiation. Current challenges for investigators are to determine (1) who will benefit from targeted agents and which agents are most appropriate to combine with radiation and/or chemotherapy, (2

TMI-2 reactor-vessel head removal and damaged-core-removal planning

International Nuclear Information System (INIS)

Logan, J.A.; Hultman, C.W.; Lewis, T.J.

1982-01-01

A major milestone in the cleanup and recovery effort at TMI-2 will be the removal of the reactor vessel closure head, planum, and damaged core fuel material. The data collected during these operations will provide the nuclear power industry with valuable information on the effects of high-temperature-dissociated coolant on fuel cladding, fuel materials, fuel support structural materials, neutron absorber material, and other materials used in reactor structural support components and drive mechanisms. In addition, examination of these materials will also be used to determine accident time-temperature histories in various regions of the core. Procedures for removing the reactor vessel head and reactor core are presented

Treatment of Head and Neck Paragangliomas With External Beam Radiation Therapy

Energy Technology Data Exchange (ETDEWEB)

Dupin, Charles, E-mail: c.dupin@bordeaux.unicancer.fr [Department of Radiotherapy, Comprehensive Cancer Center, Institut Bergonié, Bordeaux (France); Lang, Philippe [Department of Radiotherapy, Pitié Salpétrière, Paris (France); Dessard-Diana, Bernadette [Department of Radiotherapy, Hopital Européen Georges Pompidou, Paris (France); Simon, Jean-Marc; Cuenca, Xavier; Mazeron, Jean-Jacques; Feuvret, Loïc [Department of Radiotherapy, Pitié Salpétrière, Paris (France)

2014-06-01

Purpose: To retrospectively assess the outcomes of radiation therapy in patients with head and neck paragangliomas. Methods and Materials: From 1990 to 2009, 66 patients with 81 head and neck paragangliomas were treated by conventional external beam radiation therapy in 25 fractions at a median dose of 45 Gy (range, 41.4-68 Gy). One case was malignant. The median gross target volume and planning target volume were 30 cm{sup 3} (range, 0.9-243 cm{sup 3}) and 116 cm{sup 3} (range, 24-731 cm{sup 3}), respectively. Median age was 57.4 years (range, 15-84 years). Eleven patients had multicentric lesions, and 8 had family histories of paraganglioma. Paragangliomas were located in the temporal bone, the carotid body, and the glomus vagal in 51, 18, and 10 patients, respectively. Forty-six patients had exclusive radiation therapy, and 20 had salvage radiation therapy. The median follow-up was 4.1 years (range, 0.1-21.2 years). Results: One patient had a recurrence of temporal bone paraganglioma 8 years after treatment. The actuarial local control rates were 100% at 5 years and 98.7% at 10 years. Patients with multifocal tumors and family histories were significantly younger (42 years vs 58 years [P=.002] and 37 years vs 58 years [P=.0003], respectively). The association between family predisposition and multifocality was significant (P<.001). Two patients had cause-specific death within the 6 months after irradiation. During radiation therapy, 9 patients required hospitalization for weight loss, nausea, mucositis, or ophthalmic zoster. Two late vascular complications occurred (middle cerebral artery and carotid stenosis), and 2 late radiation-related meningiomas appeared 15 and 18 years after treatment. Conclusion: Conventional external beam radiation therapy is an effective and safe treatment option that achieves excellent local control; it should be considered as a first-line treatment of choice for head and neck paragangliomas.

Experience of using MOSFET detectors for dose verification measurements in an end-to-end 192Ir brachytherapy quality assurance system.

Science.gov (United States)

Persson, Maria; Nilsson, Josef; Carlsson Tedgren, Åsa

Establishment of an end-to-end system for the brachytherapy (BT) dosimetric chain could be valuable in clinical quality assurance. Here, the development of such a system using MOSFET (metal oxide semiconductor field effect transistor) detectors and experience gained during 2 years of use are reported with focus on the performance of the MOSFET detectors. A bolus phantom was constructed with two implants, mimicking prostate and head & neck treatments, using steel needles and plastic catheters to guide the 192 Ir source and house the MOSFET detectors. The phantom was taken through the BT treatment chain from image acquisition to dose evaluation. During the 2-year evaluation-period, delivered doses were verified a total of 56 times using MOSFET detectors which had been calibrated in an external 60 Co beam. An initial experimental investigation on beam quality differences between 192 Ir and 60 Co is reported. The standard deviation in repeated MOSFET measurements was below 3% in the six measurement points with dose levels above 2 Gy. MOSFET measurements overestimated treatment planning system doses by 2-7%. Distance-dependent experimental beam quality correction factors derived in a phantom of similar size as that used for end-to-end tests applied on a time-resolved measurement improved the agreement. MOSFET detectors provide values stable over time and function well for use as detectors for end-to-end quality assurance purposes in 192 Ir BT. Beam quality correction factors should address not only distance from source but also phantom dimensions. Copyright © 2017 American Brachytherapy Society. Published by Elsevier Inc. All rights reserved.

The Nuclear Fuel Cycle

International Nuclear Information System (INIS)

2011-08-01

This brochure describes the nuclear fuel cycle, which is an industrial process involving various activities to produce electricity from uranium in nuclear power reactors. The cycle starts with the mining of uranium and ends with the disposal of nuclear waste. The raw material for today's nuclear fuel is uranium. It must be processed through a series of steps to produce an efficient fuel for generating electricity. Used fuel also needs to be taken care of for reuse and disposal. The nuclear fuel cycle includes the 'front end', i.e. preparation of the fuel, the 'service period' in which fuel is used during reactor operation to generate electricity, and the 'back end', i.e. the safe management of spent nuclear fuel including reprocessing and reuse and disposal. If spent fuel is not reprocessed, the fuel cycle is referred to as an 'open' or 'once-through' fuel cycle; if spent fuel is reprocessed, and partly reused, it is referred to as a 'closed' nuclear fuel cycle.

An Integrated Model for Identifying Linkages Between the Management of Fuel Treatments, Fire and Ecosystem Services

Science.gov (United States)

Bart, R. R.; Anderson, S.; Moritz, M.; Plantinga, A.; Tague, C.

2015-12-01

Vegetation fuel treatments (e.g. thinning, prescribed burning) are a frequent tool for managing fire-prone landscapes. However, predicting how fuel treatments may affect future wildfire risk and associated ecosystem services, such as forest water availability and streamflow, remains a challenge. This challenge is in part due to the large range of conditions under which fuel treatments may be implemented, as response is likely to vary with species type, rates of vegetation regrowth, meteorological conditions and physiographic properties of the treated site. It is also due to insufficient understanding of how social factors such as political pressure, public demands and economic constraints affect fuel management decisions. To examine the feedbacks between ecological and social dimensions of fuel treatments, we present an integrated model that links a biophysical model that simulates vegetation and hydrology (RHESSys), a fire spread model (WMFire) and an empirical fuel treatment model that accounts for agency decision-making. We use this model to investigate how management decisions affect landscape fuel loads, which in turn affect fire severity and ecosystem services, which feedback to management decisions on fuel treatments. We hypothesize that this latter effect will be driven by salience theory, which predicts that fuel treatments are more likely to occur following major wildfire events. The integrated model provides a flexible framework for answering novel questions about fuel treatments that span social and ecological domains, areas that have previously been treated separately.

Status of the treatment of irradiated LWR fuel

International Nuclear Information System (INIS)

1985-03-01

This survey report provides a broad background of information on technology established in spent fuel treatment plants now in operation where the uranium and plutonium are separated from the fission products and main features of the next generation of treatment plants. The programmes in the various countries are discussed. A number of papers were included in the references

Evaluation of head movement periodicity and irregularity during locomotion of Caenorhabditis elegans

Directory of Open Access Journals (Sweden)

Ryuzo eShingai

2013-03-01

Full Text Available Caenorhabditis elegans is suitable for studying the nervous system, which controls behavior. C. elegans shows sinusoidal locomotion on an agar plate. The head moves not only sinusoidally but also more complexly, which reflects regulation of the head muscles by the nervous system. The head movement becomes more irregular with senescence. To date, the head movement complexity has not been quantitatively analyzed. We propose two simple methods for evaluation of the head movement regularity on an agar plate using image analysis. The methods calculate metrics that are a measure of how the head end movement is correlated with body movement. In the first method, the length along the trace of the head end on the agar plate between adjacent intersecting points of the head trace and the quasi-midline of the head trace, which was made by sliding an averaging window of 1/2 the body wavelength, was obtained. Histograms of the lengths showed periodic movement of the head and deviation from it. In the second method, the intersections between the trace of the head end and the trace of the 5 (near the pharynx or 50% (the mid-body point from the head end in the centerline length of the worm image were marked. The length of the head trace between adjacent intersections was measured, and a histogram of the lengths was produced. The histogram for the 5% point showed deviation of the head end movement from the movement near the pharynx. The histogram for the 50% point showed deviation of the head movement from the sinusoidal movement of the body center. Application of these methods to wild type and several mutant strains enabled evaluation of their head movement periodicity and irregularity, and revealed a difference in the age-dependence of head movement irregularity between the strains. A set of five parameters obtained from the histograms reliably identifies differences in head movement between strains.

Audiological findings in patients treated with radio- and concomitant chemotherapy for head and neck tumors

International Nuclear Information System (INIS)

Dell'Aringa, Ana Helena B; Isaac, Myrian L; Arruda, Gustavo V; Esteves, Maria Carolina BN; Dell'Aringa, Alfredo Rafael; Júnior, José Luis S; Rodrigues, Alexandre F

2009-01-01

To evaluate the functionality of the auditory system in patients who underwent radiotherapy and chemotherapy treatment with cisplatin to treat head and neck tumors. Case series with planned data collection. From May 2007 to May 2008 by the Department of Otorhinolaryngology and the Department of Oncology/Radiotherapy at Faculdade de Medicina de Marília. Audiological evaluation (Pure Tone Audiometry (air and bone conduction), Speech Audiometry, Tympanometry, Acoustic Reflex testing and Distortion Product Otoacoustic Emissions) was performed in 17 patients diagnosed with head and neck neoplasia and treated with chemotherapy, using cisplatin, and radiotherapy. 12 left ears (70.5%) and 11 right ears (64.7%) presented bilateral decreased hearing soon after the treatment for the frequency 1 kHz (mild auditory damage) and for the frequency 8 kHz (more significant auditory damage). Patients with head and neck cancer submitted to the conventional radiotherapy treatment, combined with the chemotherapy with cisplatin, presented a high incidence of decreased hearing by the end of treatment. Strong evidence was observed linking auditory alteration to the amount of radiotherapy treatment

A simplified approach to WWER-440 fuel assembly head benchmark

International Nuclear Information System (INIS)

Muehlbauer, P.

2010-01-01

The WWER-440 fuel assembly head benchmark was simulated with FLUENT 12 code as a first step of validation of the code for nuclear reactor safety analyses. Results of the benchmark together with comparison of results provided by other participants and results of measurement will be presented in another paper by benchmark organisers. This presentation is therefore focused on our approach to this simulation as illustrated on the case 323-34, which represents a peripheral assembly with five neighbours. All steps of the simulation and some lessons learned are described. Geometry of the computational region supplied as STEP file by organizers of the benchmark was first separated into two parts (inlet part with spacer grid, and the rest of assembly head) in order to keep the size of the computational mesh manageable with regard to the hardware available (HP Z800 workstation with Intel Zeon four-core CPU 3.2 GHz, 32 GB of RAM) and then further modified at places where shape of the geometry would probably lead to highly distorted cells. Both parts of the geometry were connected via boundary profile file generated at cross section, where effect of grid spacers is still felt but the effect of out flow boundary condition used in the computations of the inlet part of geometry is negligible. Computation proceeded in several steps: start with basic mesh, standard k-ε model of turbulence with standard wall functions and first order upwind numerical schemes; after convergence (scaled residuals lower than 10-3) and near-wall meshes local adaptation when needed, realizable k-ε of turbulence was used with second order upwind numerical schemes for momentum and energy equations. During iterations, area-average temperature of thermocouples and area-averaged outlet temperature which are the main figures of merit of the benchmark were also monitored. In this 'blind' phase of the benchmark, effect of spacers was neglected. After results of measurements are available, standard validation

Nuclear fuel treatment facility for 'Mutsu'

International Nuclear Information System (INIS)

Kanazawa, Toshio; Fujimura, Kazuo; Horiguchi, Eiji; Kobayashi, Tetsuji; Tamekiyo, Yoshizou

1989-01-01

A new fixed mooring harbor in Sekinehama and surrounding land facilities to accommodate a test voyage for the nuclear-powered ship 'Mutsu' in 1990 were constructed by the Japan Atomic Energy Research Institute. Kobe Steel took part in the construction of the nuclear fuel treatment process in various facilities, beginning in October, 1988. This report describes the outline of the facility. (author)

Fuel column retainer using radially compressed spring

International Nuclear Information System (INIS)

Johansson, E.B.

1989-01-01

This patent describes a fuel rod construction including a fuel rod having an inside cylindrical diameter, cylindrical fuel pellets placed within the rod. The cylindrical fuel pellets having a diameter less than the inside cylindrical diameter and being stacked end to end for a distance less than the length of the fuel rod inside the fuel rod; Zircaloy end plugs for sealing the rod at either end; a compression spring adjacent one end of the rods for biasing the pellets to and towards the other end of the rod. An improvement in the Zircaloy spring is described

System and method for controlling a combustor assembly

Science.gov (United States)

York, William David; Ziminsky, Willy Steve; Johnson, Thomas Edward; Stevenson, Christian Xavier

2013-03-05

A system and method for controlling a combustor assembly are disclosed. The system includes a combustor assembly. The combustor assembly includes a combustor and a fuel nozzle assembly. The combustor includes a casing. The fuel nozzle assembly is positioned at least partially within the casing and includes a fuel nozzle. The fuel nozzle assembly further defines a head end. The system further includes a viewing device configured for capturing an image of at least a portion of the head end, and a processor communicatively coupled to the viewing device, the processor configured to compare the image to a standard image for the head end.

Cast-to-cast variation in end-plug welds for TRIGA fuel elements

International Nuclear Information System (INIS)

Gondac, C.; Truta, C.

2013-01-01

In the Institute for Nuclear Research (INR) Pitesti - TRIGA Reactor Department there are under development activities for assembling TRIGA-LEU fuel elements locally manufactured, through autogenous Tungsten-Inert-Gas (TIG) welding. Due to specific problems occurring in welding Ni alloys, namely the dissimilar joint between Inconel 600 and Inconel 800 at the end-plug weld, weldability tests on Inconel 600 under various conditions were performed. The tests had been carried out in two stages: basic tests, on simple turned rods of Inconel 600; confirmation tests, on real (actual) end plug –to – clad welding. The basic tests had been done on simple rods machined (turned) at 13.8 mm (main diameter of the plugs) on which there have been made simple semicircular weldings ( no joint involved). Confirmation tests were done on the plug-clad assembly (dissimilar welding Incoloy-Inconel), with the welding parameters resulted from the preliminary conclusions of the basic tests. After welding, the samples were transversally sectioned, prepared for metallographic examination according to the specific procedure. The samples were examined at the metallographic microscope, and photo records for each sectioned welding bead have been taken . Measurements have been made on the recorded photos resulting the essential characteristics of the penetration: width W, depth d and ratio W/d. From the obtained results the following conclusions can be formulated: the penetration depth of the end-plug weld at the TRIGA fuel element varies substantially depending on the material cast of which the plug is produced; the optimization tests had covered the whole range of parameters in which do not appear systematic defects in welds that are specific to the alloys of Nickel ( porosity, hot cracking); for 2011-2012 casts higher energy (640 As) is required compared to the welding energy used for the 2009 batch, but to be sure that the manufacturing requirements are fulfilled, it is necessary to carry

Using fine-scale fuel measurements to assess wildland fuels, potential fire behavior and hazard mitigation treatments in the southeastern USA

Science.gov (United States)

Roger D. Ottmar; John I. Blake; William T. Crolly

2012-01-01

The inherent spatial and temporal heterogeneity of fuel beds in forests of the southeastern United States may require fine scale fuel measurements for providing reliable fire hazard and fuel treatment effectiveness estimates. In a series of five papers, an intensive, fine scale fuel inventory from the Savanna River Site in the southeastern United States is used for...

Temporal optimisation of fuel treatment design in blue gum (Eucalyptus globulus) plantations

Science.gov (United States)

Ana Martin; Brigite Botequim; Tiago M. Oliveira; Alan Ager; Francesco Pirotti

2016-01-01

This study was conducted to support fire and forest management planning in eucalypt plantations based on economic, ecological and fire prevention criteria, with a focus on strategic prioritisation of fuel treatments over time. The central objective was to strategically locate fuel treatments to minimise losses from wildfire while meeting budget constraints and demands...

Cetuximab: its unique place in head and neck cancer treatment

Directory of Open Access Journals (Sweden)

Specenier P

2013-04-01

Full Text Available Pol Specenier, Jan B Vermorken Department of Medical Oncology, Antwerp University Hospital, Edegem, Belgium Abstract: Head and neck cancer is the sixth most common cancer worldwide. At present, globally about 650,000 new cases of squamous cell carcinoma of the head and neck (SCCHN are diagnosed each year. The epidermal growth factor receptor (EGFR is almost invariably expressed in SCCHN. Overexpression of the EGFR is a strong and independent unfavorable prognostic factor in SCCHN. Cetuximab is a chimeric monoclonal antibody, which binds with high affinity to the extracellular domain of the human EGFR, blocking ligand binding, resulting in inhibition of the receptor function. It also targets cytotoxic immune effector cells towards EGFR-expressing tumor cells (antibody dependent cell-mediated cytotoxicity. The addition of cetuximab to radiotherapy (RT improves locoregional control and survival when compared to RT alone. The addition of cetuximab to platinum-based chemoradiation (CRT is feasible but does not lead to an improved outcome. Cetuximab plus RT has never been compared prospectively to CRT, which therefore remains the standard treatment for patients with locoregionally advanced SCCHN for whom surgery is not considered the optimal treatment, provided they can tolerate CRT. The addition of cetuximab to platinum-based chemotherapy prolongs survival in patients with recurrent or metastatic SCCHN. The combination of a platinum-based regimen and cetuximab should be considered as the standard first line regimen for patients who can tolerate this treatment. Keywords: SCCHN, cetuximab, recurrent metastatic, locoregionally advanced, chemoradiation

Outcomes of Vacuum-Assisted Therapy in the Treatment of Head and Neck Wounds.

Science.gov (United States)

Satteson, Ellen S; Crantford, John Clayton; Wood, Jeyhan; David, Lisa R

2015-10-01

Head and neck wounds can present a reconstructive challenge for the plastic surgeon. Whether from skin cancer, trauma, or burns, there are many different treatment modalities used to dress and manage complex head and neck wounds. Vacuum-assisted closure (VAC) therapy has been used on wounds of nearly every aspect of the body but not routinely in the head and neck area. This study was conducted to demonstrate our results using the VAC in the treatment of complex head and neck wounds. This is an IRB-approved, retrospective review of 69 patients with 73 head and neck wounds that were managed using the VAC between 1999 and 2008. The wound mechanism, location, and size, length of VAC therapy, patient comorbidities, use of radiation, complications, and ultimate outcome were assessed. In this patient population, the VAC was utilized because the standard reconstructive ladder was not a good option or had previously failed. Sixty-nine patients with complex head and neck wounds were treated with the wound VAC. The mean age of the patients was 66 years, with a range of 5-96 years. Males outnumbered females in this study nearly 2:1. Eighty-six percent of patients had wounds secondary to cancer, 8% secondary to trauma, 3% secondary to infection, and 3% secondary to burns. The VAC was used as a dressing over skin grafts in 50%, over Integra in 21%, and over open debrided wounds in 29%. Wounds healed without complication in 44% of the skin grafts, 67% of Integra-covered wounds, and 71% of debrided wounds. Minor complications included failure of complete graft take, failure of granulation tissue formation in open debrided wounds, infection, and hematoma formation under skin grafts. Major complications included positive cancer margins requiring reexcision and death secondary to pulmonary embolism, sepsis, and metastatic cancer. Most complications resolved with dressing changes, repeat grafting, or the administration of antibiotics. Our results demonstrate that the wound VAC

LIFE vs. LWR: End of the Fuel Cycle

International Nuclear Information System (INIS)

Farmer, J.C.; Blink, J.A.; Shaw, H.F.

2008-01-01

The worldwide energy consumption in 2003 was 421 quadrillion Btu (Quads), and included 162 quads for oil, 99 quads for natural gas, 100 quads for coal, 27 quads for nuclear energy, and 33 quads for renewable sources. The projected worldwide energy consumption for 2030 is 722 quads, corresponding to an increase of 71% over the consumption in 2003. The projected consumption for 2030 includes 239 quads for oil, 190 quads for natural gas, 196 quads for coal, 35 quads for nuclear energy, and 62 quads for renewable sources (International Energy Outlook, DOE/EIA-0484, Table D1 (2006) p. 133]. The current fleet of light water reactors (LRWs) provides about 20% of current U.S. electricity, and about 16% of current world electricity. The demand for electricity is expected to grow steeply in this century, as the developing world increases its standard of living. With the increasing price for oil and gasoline within the United States, as well as fear that our CO2 production may be driving intolerable global warming, there is growing pressure to move away from oil, natural gas, and coal towards nuclear energy. Although there is a clear need for nuclear energy, issues facing waste disposal have not been adequately dealt with, either domestically or internationally. Better technological approaches, with better public acceptance, are needed. Nuclear power has been criticized on both safety and waste disposal bases. The safety issues are based on the potential for plant damage and environmental effects due to either nuclear criticality excursions or loss of cooling. Redundant safety systems are used to reduce the probability and consequences of these risks for LWRs. LIFE engines are inherently subcritical, reducing the need for systems to control the fission reactivity. LIFE engines also have a fuel type that tolerates much higher temperatures than LWR fuel, and has two safety systems to remove decay heat in the event of loss of coolant or loss of coolant flow. These features of

Treatment alternatives for non-fuel-bearing hardware

International Nuclear Information System (INIS)

Ross, W.A.; Clark, L.L.; Oma, K.H.

1987-01-01

This evaluation compared four alternatives for the treatment or processing of non-fuel bearing hardware (NFBH) to reduce its volume and prepare it for disposal. These treatment alternatives are: shredding; shredding and low pressure compaction; shredding and supercompaction; and melting. These alternatives are compared on the basis of system costs, waste form characteristics, and process considerations. The study recommends that melting and supercompaction alternatives be further considered and that additional testing be conducted for these two alternatives

Fuel treatment effectiveness in reducing fire intensity and spread rate - An experimental overview

Science.gov (United States)

Eric Mueller; Nicholas Skowronski; Albert Simeoni; Kenneth Clark; Robert Kremens; William Mell; Michael Gallagher; Jan Thomas; Alexander Filkov; Mohamad El Houssami; John Hom; Bret Butler

2014-01-01

Fuel treatments represent a significant component of the wildfire mitigation strategy in the United States. However, the lack of research aimed at quantifying the explicit effectiveness of fuel treatments in reducing wildfire intensity and spread rate limits our ability to make educated decisions about the type and placement of these treatments. As part of a larger...

Undesirable financial effects of head and neck cancer radiotherapy during the initial treatment period

Directory of Open Access Journals (Sweden)

Helen Egestad

2015-01-01

Full Text Available Background: Healthcare cost and reforms are at the forefront of international debates. One of the current discussion themes in oncology is whether and how patients’ life changes due to costs of cancer care. In Norway, the main part of the treatment costs is supported by general taxpayer revenues. Objectives: The objective of this study was to clarify whether head and neck cancer patients (n=67 in northern Norway experienced financial health-related quality of life (HRQOL deterioration due to costs associated with treatment. Design: HRQOL was examined by the European Organization for Research and Treatment of Cancer (EORTC QLQ-C30 in the beginning and in the end of radiation treatment in patients treated at the University Hospital in Northern Norway. Changes in financial HRQOL were calculated and compared by paired sample T-tests. Multiple regression analyses were used to examine correlations among gender, marital status, age and treatment with or without additional chemotherapy and changes in the HRQOL domain of financial difficulties. Results: The majority of score results at both time points were in the lower range (mean 15–25, indicating limited financial difficulties. We observed no statistically significant differences by gender, marital status and age. Increasing financial difficulties during treatment were reported by male patients and those younger than 65, that is, patients who were younger than retirement age. The largest effect was seen in singles. However, differences were not statistically significant. Conclusions: During the initial phase of the disease trajectory, no significant increase in financial difficulties was found. This is in line with the aims of the Norwegian public healthcare model. However, long-term longitudinal studies should be performed, especially with regard to the trends we observed in single, male and younger patients.

Conceptual design of the alcohol waste treatment equipment

International Nuclear Information System (INIS)

Fujisawa, Morio; Nitta, Kazuhiko; Morita, Yasuhiro; Nakada, Eiju

2001-01-01

This report describes the result of Conceptual Design of the Alcohol Waste Treatment Equipment. The experimental fast Reactor, JOYO, saves the radioactive alcohol waste at storage tank. As this alcohol waste is not able to treat with existing equipment, it is stored about 5 m 3 . And the amount of this is increasing every year. So it is necessary to treat the alcohol waste by chemical resolution for example. On account of this, the investigative test about filtration and dialyzer, and conceptual design about catalyst oxidation process, which is composed from head end process to resolution, are done. The results of investigation show as follows. 1. Investigative Test about filtration and dialyzer. (1) The electric conduction is suitable for the judgement of alkyl sodium hydrolysis Alkyl sodium hydrolysis is completed below 39% alcohol concentration. (2) The microfiltration is likely to separate the solid in alcohol waste. (3) From laboratory test, the electrodialyzer is effective for sodium separation in alcohol waste. And sodium remove rate, 96-99%, is confirmed. 2. Conceptual Design. The candidate process is as follows. (1) The head end process is electrodialyzer, and chemical resolution process is catalyst oxidation. (2) The head end process is not installed, and chemical resolution process is catalyst oxidation. (3) The head end process is electrodialyzer, and alcohol extracted by pervaporation. In this Conceptual Design, as far these process, the components, treatment ability, properties of waste, chemical mass balance, safety for fire and explosion, and the plot plan are investigated. As a result, remodeling the existing facility into catalyst oxidation process is effective to treat the alcohol waste, and treatment ability is about 1.25 l/h. (author)

Sturdy on Orbital TIG Welding Properties for Nuclear Fuel Test Rod

International Nuclear Information System (INIS)

Joung, Changyoung; Hong, Jintae; Kim, Kahye; Huh, Sungho

2014-01-01

We developed a precision TIG welding system that is able to weld the seam between end-caps and a fuel cladding tube for the nuclear fuel test rod and rig. This system can be mainly classified into an orbital TIG welder (AMI, M-207A) and a pressure chamber. The orbital TIG welder can be independently used, and it consists of a power supply unit, a microprocessor, water cooling unit, a gas supply unit and an orbital weld head. In this welder, the power supply unit mainly supplies GTAW power for a welding specimen and controls an arc starting of high frequency, supping of purge gas, arc rotation through the orbital TIG welding head, and automatic timing functions. In addition, the pressure chamber is used to make the welded surface of the cladding specimen clean with the inert gas filled inside the chamber. To precisely weld the cladding tube, a welding process needs to establish a schedule program for an orbital TIG welding. Therefore, the weld tests were performed on a cladding tube and dummy rods under various conditions. This paper describes not only test results on parameters of the purge gas flow rates and the chamber gas pressures for the orbital TIG welding, but also test results on the program establishment of an orbital TIG welding system to weld the fuel test rods. Various welding tests were performed to develop the orbital TIG welding techniques for the nuclear fuel test rod. The width of HAZ of a cladding specimen welded with the identical power during an orbital TIG welding cycle was continuously increased from a welded start-point to a weld end-point because of heat accumulation. The welding effect of the PGFR and CGP shows a relatively large difference for FSS and LSS. Each hole on the cladding specimens was formed in the 1bar CGP with the 20L/min PGFR but not made in the case of the PGFR of 10L/min in the CGP of 2bar. The optimum schedule program of the orbital TIG welding system to weld the nuclear fuel test rod was established through the program

Sturdy on Orbital TIG Welding Properties for Nuclear Fuel Test Rod

Energy Technology Data Exchange (ETDEWEB)

Joung, Changyoung; Hong, Jintae; Kim, Kahye; Huh, Sungho [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2014-05-15

We developed a precision TIG welding system that is able to weld the seam between end-caps and a fuel cladding tube for the nuclear fuel test rod and rig. This system can be mainly classified into an orbital TIG welder (AMI, M-207A) and a pressure chamber. The orbital TIG welder can be independently used, and it consists of a power supply unit, a microprocessor, water cooling unit, a gas supply unit and an orbital weld head. In this welder, the power supply unit mainly supplies GTAW power for a welding specimen and controls an arc starting of high frequency, supping of purge gas, arc rotation through the orbital TIG welding head, and automatic timing functions. In addition, the pressure chamber is used to make the welded surface of the cladding specimen clean with the inert gas filled inside the chamber. To precisely weld the cladding tube, a welding process needs to establish a schedule program for an orbital TIG welding. Therefore, the weld tests were performed on a cladding tube and dummy rods under various conditions. This paper describes not only test results on parameters of the purge gas flow rates and the chamber gas pressures for the orbital TIG welding, but also test results on the program establishment of an orbital TIG welding system to weld the fuel test rods. Various welding tests were performed to develop the orbital TIG welding techniques for the nuclear fuel test rod. The width of HAZ of a cladding specimen welded with the identical power during an orbital TIG welding cycle was continuously increased from a welded start-point to a weld end-point because of heat accumulation. The welding effect of the PGFR and CGP shows a relatively large difference for FSS and LSS. Each hole on the cladding specimens was formed in the 1bar CGP with the 20L/min PGFR but not made in the case of the PGFR of 10L/min in the CGP of 2bar. The optimum schedule program of the orbital TIG welding system to weld the nuclear fuel test rod was established through the program

Universal high-temperature heat treatment furnace for FBR mixed uranium and plutonium carbide fuel

International Nuclear Information System (INIS)

Handa, Muneo; Takahashi, Ichiro; Watanabe, Hitoshi

1978-10-01

A universal high-temperature heat treatment furnace for LMFBR advanced fuels was installed in Plutonium Fuel Laboratory, Oarai Research Establishment. Design, construction and performance of the apparatus are described. With the apparatus, heat treatment of the fuel under a controlled gas atmosphere and quenching of the fuel with blowing helium gas are possible. Equipment to measure impurity gas release of the fuel is also provided. Various plutonium enclosure techniques, e.g., a gas line filter with new exchange mechanics, have been developed. In performance test, results of the enclosure techniques are described. (author)

[Effect of vascular endothelial growth factor and tumor necrosis factor receptor for treatment of avascular necrosis of the femoral head in rabbits].

Science.gov (United States)

Hu, Zhi-ming; Zhou, Ming-qian; Gao, Ji-min

2008-12-01

To evaluate the therapeutic effect of vascular endothelial growth factor (VEGF) and tumor necrosis factor receptor (TNFR) on avascular necrosis of the femoral head in rabbits. Avascular necrosis of the femoral head was induced in 26 New Zealand white rabbits by injections of horse serum and prednisolone. The rabbits were then divided into VEGF/TNFR treatment group, VEGF treatment group, and untreated model group, with another 4 normal rabbits as the normal control group. In the two treatment groups, the therapeutic agents were injected percutaneously into the femoral head. Enzyme-linked immunosorbent assay was performed to determine the concentration of TNF-alpha in rabbit serum followed by pathological examination of the changes in the bone tissues, bone marrow hematopoietic tissue and the blood vessels in the femoral head. Compared with the model group, the rabbits with both VEGF and TNFR treatment showed decreased serum concentration of TNF-alpha with obvious new vessel formation, decreased empty bone lacunae in the femoral head and hematopoietic tissue proliferation in the bone marrow cavity. Percutaneous injection of VEGF and TNFR into the femoral head can significantly enhance bone tissue angiogenesis and ameliorate osteonecrosis in rabbits with experimental femoral head necrosis.

Study of pneumatic hydropulse filter for feed clarification in reprocessing plant head-end

International Nuclear Information System (INIS)

Siddiqui, I.A.; Shah, B.V.; Salunke, S.U.; Kumar, S.V.

1991-01-01

A Pneumatic Hydropulse (PHP) Filter with sintered stainless steel cartridges was tested for suitability in reprocessing plant head-end filtration. The filter was tested with simulated slurry containing between 25 and 400 ppm of calcium carbonate particulates in the size ranges 45 to 53 micron and 53 to 75 micron at varying flow rates. Procedures were developed for dislodging the layer of solids on the cartidridges and regenerating the filter remotely. Application of 5.4 kg/cm 2 air to the dome of the filter during regenaration was found to be optimum for dislodging the particulate layer on the cartridges. No difficulties due to choking of the filter cartridges were experienced during operation and good regeneration by remote operation was possible. Approach velocity at the filter medium was about 6 cm/min. The efficiency of regeneration was better than 90%. Filtration efficiency was found to be better than 90%. Solid loading capacity was found to increase with increase of particle size and feed concentration. (author). 2 figs., 10 tabs

Spent fuel management in France: Reprocessing, conditioning, recycling

International Nuclear Information System (INIS)

Giraud, J.P.; Montalembert, J.A. de

1994-01-01

The French energy policy has been based for 20 years on the development of nuclear power. The some 75% share of nuclear in the total electricity generation, representing an annual production of 317 TWh requires full fuel cycle control from the head-end to the waste management. This paper presents the RCR concept (Reprocessing, Conditioning, Recycling) with its industrial implementation. The long lasting experience acquired in reprocessing and MOX fuel fabrication leads to a comprehensive industrial organization with minimized impact on the environment and waste generation. Each 900 MWe PWR loaded with MOX fuel avoids piling up 2,500 m 3 per year of mine tailings. By the year 2000, less than 500 m 3 of high-level and long-lived waste will be annually produced at La Hague for the French program. The fuel cycle facilities and the associated MOX loading programs are ramping-up according to schedule. Thus, the RCR concept is a reality as well as a policy adopted in several countries. Last but not least, RCR represents a strong commitment to non-proliferation as it is the way to fully control and master the plutonium inventory

Legal, institutional, and political issues in transportation of nuclear materials at the back end of the LWR nuclear fuel cycle

International Nuclear Information System (INIS)

Lippek, H.E.; Schuller, C.R.

1979-03-01

A study was conducted to identify major legal and institutional problems and issues in the transportation of spent fuel and associated processing wastes at the back end of the LWR nuclear fuel cycle. (Most of the discussion centers on the transportation of spent fuel, since this activity will involve virtually all of the legal and institutional problems likely to be encountered in moving waste materials, as well.) Actions or approaches that might be pursued to resolve the problems identified in the analysis are suggested. Two scenarios for the industrial-scale transportation of spent fuel and radioactive wastes, taken together, high-light most of the major problems and issues of a legal and institutional nature that are likely to arise: (1) utilizing the Allied General Nuclear Services (AGNS) facility at Barnwell, SC, as a temporary storage facility for spent fuel; and (2) utilizing AGNS for full-scale commercial reprocessing of spent LWR fuel

Legal, institutional, and political issues in transportation of nuclear materials at the back end of the LWR nuclear fuel cycle

Energy Technology Data Exchange (ETDEWEB)

Lippek, H.E.; Schuller, C.R.

1979-03-01

A study was conducted to identify major legal and institutional problems and issues in the transportation of spent fuel and associated processing wastes at the back end of the LWR nuclear fuel cycle. (Most of the discussion centers on the transportation of spent fuel, since this activity will involve virtually all of the legal and institutional problems likely to be encountered in moving waste materials, as well.) Actions or approaches that might be pursued to resolve the problems identified in the analysis are suggested. Two scenarios for the industrial-scale transportation of spent fuel and radioactive wastes, taken together, high-light most of the major problems and issues of a legal and institutional nature that are likely to arise: (1) utilizing the Allied General Nuclear Services (AGNS) facility at Barnwell, SC, as a temporary storage facility for spent fuel; and (2) utilizing AGNS for full-scale commercial reprocessing of spent LWR fuel.

Radiological considerations in the design of Reprocessing Uranium Plant (RUP) of Fast Reactor Fuel Cycle Facility (FRFCF), Kalpakkam

International Nuclear Information System (INIS)

Chandrasekaran, S.; Rajagopal, V.; Jose, M.T.; Venkatraman, B.

2012-01-01

A Fast Reactor Fuel Cycle Facility (FRFCF) being planned at Indira Gandhi Centre for Atomic Research, Kalpakkam is an integrated facility with head end and back end of fuel cycle plants co-located in a single place, to meet the refuelling needs of the prototype fast breeder reactor (PFBR). Reprocessed uranium oxide plant (RUP) is one such plant in FRFCF to built to meet annual requirements of UO 2 for fabrication of fuel sub-assemblies (FSAs) and radial blanket sub-assemblies (RSAs) for PFBR. RUP receives reprocessed uranium oxide powder (U 3 O 8 ) from fast reactor fuel reprocessing plant (FRP) of FRFCF. Unlike natural uranium oxide plant, RUP has to handle reprocessed uranium oxide which is likely to have residual fission products activity in addition to traces of plutonium. As the fuel used for PFBR is recycled within these plants, formation of higher actinides in the case of plutonium and formation of higher levels of 232 U in the uranium product would be a radiological problem to be reckoned with. The paper discussed the impact of handling of multi-recycled reprocessed uranium in RUP and the radiological considerations

[Application of virtual reality in surgical treatment of complex head and neck carcinoma].

Science.gov (United States)

Zhou, Y Q; Li, C; Shui, C Y; Cai, Y C; Sun, R H; Zeng, D F; Wang, W; Li, Q L; Huang, L; Tu, J; Jiang, J

2018-01-07

Objective: To investigate the application of virtual reality technology in the preoperative evaluation of complex head and neck carcinoma and he value of virtual reality technology in surgical treatment of head and neck carcinoma. Methods: The image data of eight patients with complex head and neck carcinoma treated from December 2016 to May 2017 was acquired. The data were put into virtual reality system to built the three-dimensional anatomical model of carcinoma and to created the surgical scene. The process of surgery was stimulated by recognizing the relationship between tumor and surrounding important structures. Finally all patients were treated with surgery. And two typical cases were reported. Results: With the help of virtual reality, surgeons could adequately assess the condition of carcinoma and the security of operation and ensured the safety of operations. Conclusions: Virtual reality can provide the surgeons with the sensory experience in virtual surgery scenes and achieve the man-computer cooperation and stereoscopic assessment, which will ensure the safety of surgery. Virtual reality has a huge impact on guiding the traditional surgical procedure of head and neck carcinoma.

Metal waste forms from treatment of EBR-II spent fuel

International Nuclear Information System (INIS)

Abraham, D. P.

1998-01-01

Demonstration of Argonne National Laboratory's electrometallurgical treatment of spent nuclear fuel is currently being conducted on irradiated, metallic driver fuel and blanket fuel elements from the Experimental Breeder Reactor-II (EBR-II) in Idaho. The residual metallic material from the electrometallurgical treatment process is consolidated into an ingot, the metal waste form (MWF), by employing an induction furnace in a hot cell. Scanning electron microscopy (SEM) and chemical analyses have been performed on irradiated cladding hulls from the driver fuel, and on samples from the alloy ingots. This paper presents the microstructures of the radioactive ingots and compares them with observations on simulated waste forms prepared using non-irradiated material. These simulated waste forms have the baseline composition of stainless steel - 15 wt % zirconium (SS-15Zr). Additions of noble metal elements, which serve as surrogates for fission products, and actinides are made to that baseline composition. The partitioning of noble metal and actinide elements into alloy phases and the role of zirconium for incorporating these elements is discussed in this paper

How word-beginnings constrain the pronunciations of word-ends in the reading aloud of English: the phenomena of head- and onset-conditioning

Directory of Open Access Journals (Sweden)

Anastasia Ulicheva

2015-12-01

Full Text Available Background. A word whose body is pronounced in different ways in different words is body-inconsistent. When we take the unit that precedes the vowel into account for the calculation of body-consistency, the proportion of English words that are body-inconsistent is considerably reduced at the level of corpus analysis, prompting the question of whether humans actually use such head/onset-conditioning when they read.Methods. Four metrics for head/onset-constrained body-consistency were calculated: by the last grapheme of the head, by the last phoneme of the onset, by place and manner of articulation of the last phoneme of the onset, and by manner of articulation of the last phoneme of the onset. Since these were highly correlated, principal component analysis was performed on them.Results. Two out of four resulting principal components explained significant variance in the reading-aloud reaction times, beyond regularity and body-consistency.Discussion. Humans read head/onset-conditioned words faster than would be predicted based on their body-consistency and regularity only. We conclude that humans are sensitive to the dependency between word-beginnings and word-ends when they read aloud, and that this dependency is phonological in nature, rather than orthographic.

Ipsilateral dislocation of the radial head associated with fracture of distal end of the radius: a case report and review of the literature

Directory of Open Access Journals (Sweden)

Gupta Vinay

2013-06-01

Full Text Available 【Abstract】Dislocation of the radial head in adults is uncommon. A simultaneous dislocation of the radial head and fracture of the ipsilateral distal end of radius with no other associated injuries is extremely rare. As far as we know, such an injury after an unusual mode of injury has been seldom reported in the English literature. We report such a case without any associated injuries or comorbidity. Closed reduction was performed within two hours after injury and results were satisfactory. Immobilisation was continued for 3 weeks. Gradual mobilisation was started after removal of the plaster under the supervision of a physiotherapist. At 6 months’ follow-up, the patient had no residual pain at the elbow with full flexion & extension. Almost full supination with a restriction of last 10 degrees of pronation was achieved. There was no evidence of instability of the elbow. Key words: Radial heads; Dislocations; Radius fractures

Performance of Microbial Fuel Cell for Wastewater Treatment and Electricity Generation

Directory of Open Access Journals (Sweden)

Z Yavari

2013-06-01

Full Text Available Renewable energy will have an important role as a resource of energy in the future. Microbial fuel cell (MFC is a promising method to obtain electricity from organic matter andwastewater treatment simultaneously. In a pilot study, use of microbial fuel cell for wastewater treatment and electricity generation investigated. The bacteria of ruminant used as inoculums. Synthetic wastewater used at different organic loading rate. Hydraulic retention time was aneffective factor in removal of soluble COD and more than 49% removed. Optimized HRT to achieve the maximum removal efficiency and sustainable operation could be regarded 1.5 and 2.5 hours. Columbic efficiency (CE affected by organic loading rate (OLR and by increasing OLR, CE reduced from 71% to 8%. Maximum voltage was 700mV. Since the microbial fuel cell reactor considered as an anaerobic process, it may be an appropriate alternative for wastewater treatment

Mode of treatment affects quality of life in head and neck cancer survivors: Implications for holistic care.

Science.gov (United States)

Bower, Wendy Fiona; Vlantis, Alexander Christopher; Chung, Tiffany M L; Van Hasselt, C Andrew

2010-10-01

As adverse effects of live-saving treatment are unavoidable surgeons have a duty to address physical changes and quality of life issues that matter to head and neck (H&N) cancer patients. We propose a tailored holistic care package. This study compared the quality of life of H&N cancer survivors managed with different approaches in the follow-up phase after initial treatment and identified factors adversely impacting quality of life parameters. H&N cancer patients studied: 1) surgery only, 2) radiotherapy only, 3) surgery and radiotherapy, and 4) any combination of surgery, chemotherapy or radiotherapy. Patients unable to communicate in Cantonese, with thyroid cancer or end-of-life disease were excluded. EORTC QLQ-H&N35 Cantonese version was administered at least 1 year after initial H&N cancer treatment. Quality of life impairment was worse in all of the domains for combination therapy versus monotherapy patients. Scores between surgery or radiotherapy-only patients were not significantly different. Radiotherapy preceding surgery impacted significantly more on speech than surgery before the radiotherapy. Patients with advanced disease had more impairment of quality of life in each domain than patients with early disease. Coughing, eating problems, sticky saliva, and difficulties with social contact were all significant predictors of problems associated with a dry mouth.

Back-end nuclear fuel cycle strategy: The approaches in Ukraine

International Nuclear Information System (INIS)

Afnasyev, A.; Medun, V.; Trehub, Yu.

2002-01-01

Ukraine has 14 nuclear units in operation and 4 units more under construction. Now in Ukraine a share of installed nuclear capacity in total installed capacity is essential and it is planned to increase it further. In this connection a spent nuclear fuel management in Ukraine for the current period and future is becoming important in a nuclear fuel cycle. A current situation in relation to the spent nuclear fuel management in Ukraine is described in the paper. It is reviewed: legislative basis for a spent nuclear fuel management strategy; an assessment for a spent fuel growth; the national possibilities for the spent fuel management; an organization chart for a spent nuclear fuel management, etc. Some factors that can determine a long-term spent fuel management strategy in Ukraine are in the conclusion. (author)

Lanthanide - actinide separation: a challenge in the back end of nuclear fuel cycle

International Nuclear Information System (INIS)

Mohapatra, P.K.

2015-01-01

Due to their similar size and chemical state, separation of trivalent lanthanide and actinide ions has always been a challenging topic of research. Of late, the growing concern for the radioactive waste management in the back end of the nuclear fuel cycle has led to the possibility of transmuting the long-lived transuranides in high flux reactors. This necessitates the development of processes for the separation of lanthanides and actinides in acidic/low pH media. In view of the high absorption cross section of few lanthanides, their presence in relatively large proportion (10-100 times) impedes the transmutation process. Processes such as the TRAMEX and TALSPEAK have been used for the separation of lanthanides from trivalent actinides. Of late soft donor ligands containing S and N donor atoms have been used for the selective extraction of trivalent actinide ions. The commercially available S-donor compound, CYANEX 301 (bis(2,4,4-trimethylpentyl) dithiophosphinic acid) has been used to yield separation factor (S.F.) values in the excess of 6000. Synergistic extraction with N-donor ligands such as 2,2'-bipyridyl and 1,10-phenanthroline have yielded S.F. values close to 40,000. N-donor ligands such as BTP (bis-triazinylpyridine), BTBP (bis-triazinylbipyridyl) and BTPhen (bis-triazinyl-phenanthroline) have been particularly effective from relatively acidic feed conditions. The present lecture will give a brief outline of the separation processes and experimental results of studies carried out using various S and N donor ligands. Use of room temperature ionic liquids for more favorable separations will be highlighted. Liquid membrane separation results for application to back end nuclear fuel cycle will also be discussed. (author)

All-in-one theranostic nanoagent for head and neck cancer treatment

Science.gov (United States)

Dreifuss, Tamar; Davidi, Erez Shmuel; Motiei, Menachem; Barnoy, Eran; Bragilovski, Dimitri; Lubimov, Leon; Kindler, Marc Jose Jonathan; Popovtzer, Aron; Popovtzer, Rachela

2018-02-01

Despite the significant improvement in the treatment paradigm of head and neck cancer, owing to advanced radiation techniques in combination with chemotherapy, resistance of tumors remains a critical problem, leading to poor outcomes and negative prognosis. In addition, chemotherapeutic agents result in severe systemic toxicity due to nonselective damaging of normal cells. Recently, nanoparticle-based approaches have gained broad attention for improving both radiation therapy and chemotherapy. In this study, we present a dual effect nanoplatform, consists of gold nanoparticles coated with glucose and cisplatin (CG-GNPs), which simultaneously acts as a radiosensitizer and as a carrier which specifically deliver cisplatin to head and neck tumor. Our CG-GNPs showed significant penetration into tumor cells and similar cellular toxicity as cisplatin alone. Moreover, in combination with radiation treatment, CG-GNPs led to greater tumor reduction than that of free cisplatin with radiation. Furthermore, our CG-GNPs also demonstrated highly efficient imaging capabilities, as they act as ideal tumor-targeted CT contrast agent. Therefore, this single nano-formulation is a promising theranostic agent that has the potential to increase the antitumor effect and allow imaging guided therapy.

Reprocessing RTR fuel in the La Hague plants

International Nuclear Information System (INIS)

Thomasson, J.; Drain, F.; David, A.

2001-01-01

Starting in 2006, research reactors operators will be fully responsible for the back-end management of their spent fuel. It appears that the only solution for this management is treatment-conditioning, which could be done at the La Hague reprocessing complex in France. The fissile material can be separated in the reprocessing plants and the final waste can be encapsulated in a matrix adapted to its potential hazards. RTR reprocessing at La Hague would require some modifications, since the plant had been primarily designed to reprocess fuel from light water reactors. Many provisions have been taken at the plant design stage, however, and the modifications would be feasible even during active operations, as was done from 1993 to 1995 when a new liquid waste management was implemented, and when one of the two vitrification facilities was improved. To achieve RTR back-end management, COGEMA and its partners are also conducting R and D to define a new generation of LEU fuel with performance characteristics approximating those of HEU fuel. This new-generation fuel would be easier to reprocess. (author)

Reprocessing RTR fuel in the La Hague plants

Energy Technology Data Exchange (ETDEWEB)

Thomasson, J. [Cogema, F-78140 Velizy (France); Drain, F.; David, A. [SGN, F-78182 Saint Quentin en Yvelines (France)

2001-07-01

Starting in 2006, research reactors operators will be fully responsible for the back-end management of their spent fuel. It appears that the only solution for this management is treatment-conditioning, which could be done at the La Hague reprocessing complex in France. The fissile material can be separated in the reprocessing plants and the final waste can be encapsulated in a matrix adapted to its potential hazards. RTR reprocessing at La Hague would require some modifications, since the plant had been primarily designed to reprocess fuel from light water reactors. Many provisions have been taken at the plant design stage, however, and the modifications would be feasible even during active operations, as was done from 1993 to 1995 when a new liquid waste management was implemented, and when one of the two vitrification facilities was improved. To achieve RTR back-end management, COGEMA and its partners are also conducting R and D to define a new generation of LEU fuel with performance characteristics approximating those of HEU fuel. This new-generation fuel would be easier to reprocess. (author)

Reprocessing RTR fuel in the La Hague plants

Energy Technology Data Exchange (ETDEWEB)

Thomasson, J. [Cogema, 78 - Velizy Villacoublay (France); Drain, F.; David, A. [SGN, 78 - Saint Quentin en Yveline (France)

2001-07-01

Starting in 2006, research reactors operators will be fully responsible for their research and testing reactors spent fuel back-end management. It appears that the only solution for this management is treatment-conditioning, which could be done at the La Hague reprocessing complex in France. The fissile material can be separated in the reprocessing plants and the final waste can be encapsulated in a matrix adapted to its potential hazards. RTR reprocessing at La Hague would require some modifications, since the plant had been primarily designed to reprocess fuel from light water reactors. Many provisions have been taken at the plant design stage, however, and the modifications would be feasible even during active operations, as was done from 1993 to 1995 when a new liquid waste management was implemented, and when one of the two vitrification facilities was improved. To achieve RTR back-end management, COGEMA and its partners are also conducting R and D to define a new generation of LEU fuel with performance characteristics approximating those of HEU fuel. This new-generation fuel would be easier to reprocess. (author)

Multilateral controls of nuclear fuel-cycle in Asia

International Nuclear Information System (INIS)

Choi, Jor-Shan

2010-01-01

To meet increasing energy demand and climate change issues, nuclear energy is expected to expand during the next decades in both developed and developing countries. This expansion, most visibly in Asian countries would no doubt be accompanied with complex and intractable challenges to global peace and security, notably in the back-end of the nuclear fuel cycle. What to do with the growing stocks of spent fuel in existing nuclear programs? And how to reduce proliferation concerns when spent fuels are generated in less stable regions of the world? The answers to these questions may lie in the possibility of multilateral (or regional) control of nuclear materials and technologies in the back-end of nuclear fuel cycle. One of the areas of interest is technology, e.g., spent fuel treatment (reprocessing) for long term sustainability and environmental-friendly disposal of radioactive wastes, as an alternative to directly disposing spent fuel in geologic repository. The other is to seek for regional centers for centralized interim spent fuel storage which can eventually turn into disposal facilities. Such centers could help facilitate the possibilities of spent fuel take-back/take-away from countries located in less stable regions for fix-period storage. (author)

Hybrid disassembly system for cellular telephone end-of-life treatment

Energy Technology Data Exchange (ETDEWEB)

Kniebel, M.; Basdere, B.; Seliger, G. [Technical Univ. Berlin, Inst. for Machine Tools and Factory Management, Dept. of Assembly Technology and Factory Management, Berlin (Germany)

2004-07-01

Concern over the negative environmental impacts associated with the production, use, and end-of-life (EOL) of cellular telephones is particularly high due to large production volumes and characteristically short time scales of technological and stylistic obsolescence. Landfilled or incinerated cellular telephones create the potential for release of toxic substances. The European legislation has passed the directive on Waste of Electrical and Electronic Equipment (WEEE) to regulate their collection and appropriate end-of-life treatment. Manufacturers must conduct material recycling or remanufacturing processes to recover resources. While recovery rates can hardly be met economically by material recycling, remanufacturing and reusing cellular phones is developing into a reasonable alternative. Both end-of-life options require disassembly processes for WEEE compliant treatment. Due to the high number of different cell phone variants and their typical design that fits components into tight enclosing spaces, cellular phone disassembly becomes a challenging task. These challenges and the expected high numbers of phones to be returned in the course of the WEEE urges for automated disassembly. A hybrid disassembly system has been developed to ensure the mass-treatment of obsolete cellular phones. It has been integrated into a prototypical remanufacturing factory for cellular phones that has been planned based on market data. (orig.)

Deployment Evaluation Methodology for the Electrometallurgical Treatment of DOE-EM Spent Nuclear Fuel

International Nuclear Information System (INIS)

Ramer, Ronald James; Adams, James Paul; Rynearson, Michael Ardel; Dahl, Christian Adam

1999-01-01

The Department of Energy - Environmental Management (DOE-EM) National Spent Nuclear Fuel Program (NSNFP) is charged with the disposition of legacy Spent Nuclear Fuel (SNF). The NSNFP, conducted by Lockheed Martin Idaho Technology Co. (LMITCO) at the Idaho National Engineering and Environmental Laboratory (INEEL), is evaluating final disposition of SNF in the DOE complex. While direct repository disposal of the SNF is the preferred disposition option, some DOE SNF may need treatment to meet acceptance criteria at various disposition sites. Evaluations of treatment needs and options have been previously prepared, and further evaluations are ongoing activities in the DOE-EM NSNFP. The treatments may range from electrometallurgical treatment (EMT) and chemical dissolution to engineering controls. As a planning basis, a need is assumed for a treatment process, either as a primary or backup technology, that is compatible with, and cost-effective for, this portion of the DOE-EM inventory. The current planning option for treating this SNF, pending completion of development work and National Environmental Policy Act (NEPA) analysis, is the EMT process under development by Argonne National Laboratory - West (ANL-W). A decision on the deployment of the EMT is pending completion of an engineering scale demonstration currently in progress at ANL-W. Treatment options and treatment locations will depend on fuel type and location of the fuel. One of the first steps associated with selecting one or more sites for treating SNF in the DOE complex is to determine the cost of each option. An economic analysis will assist in determining which fuel treatment alternative attains the optimum disposition of SNF at the lowest possible cost to the government and the public. One of the major issues associated with SNF treatment is final disposition of treatment products and associated waste streams. During conventional SNF treatment, various chemicals are added that may increase the product

Failure pattern and salvage treatment after radical treatment of head and neck cancer

DEFF Research Database (Denmark)

Pagh, Anja; Grau, Cai; Overgaard, Jens

2016-01-01

Purpose The aim of the study was to test the hypothesis that head and neck cancer (HNC) patients benefit from specialized follow-up (FU), as this strategy ensures timely detection of relapses for successful salvage treatment. This was done by evaluation of the pattern of failure, the temporal...... recordings of recurrent disease in 567 patients with primary tumors of the larynx, pharynx, oral cavity, nasal cavity, paranasal sinuses and salivary glands. A review of medical records was performed in order to update and supplement the database. Results Failures of the 567 patients were primarily in T...

Assessment and Treatment Considerations for Post Traumatic Stress Disorder at End of Life.

Science.gov (United States)

Glick, Debra M; Cook, Joan M; Moye, Jennifer; Kaiser, Anica Pless

2018-01-01

Post traumatic stress disorder (PTSD) may first emerge, reemerge, or worsen as individuals approach end of life and may complicate the dying process. Unfortunately, lack of awareness of the occurrence and/or manifestation of PTSD at end of life can lead to PTSD going unaddressed. Even if PTSD is properly diagnosed, traditional evidence-based trauma-focused treatments may not be feasible or advisable with this group as many patients at end of life often lack the physical and mental stamina to participate in traditional psychotherapy. This article reviews the clinical and empirical literature on PTSD at end of life, as well as discusses assessment and psychotherapy treatment issues with this neglected population. In addition, it expands on the current reviews of this literature 1-3 by extrapolating results from nontraditional treatment approaches with other patient populations. Elements of these approaches with patients sharing similar characteristics and/or comorbidities with patients with PTSD at end of life may provide additional benefits for the latter population. Clinical implications and suggestions for interdisciplinary care providers are provided.

Suspension scheme for fuel pin

International Nuclear Information System (INIS)

Butts, C.E.; Gray, H.C.

1975-01-01

A description is presented of a nuclear fuel pin suspension arrangement comprising, in combination, a rod; a first beam member connected to said rod at one end; a plurality of parallel-spaced slidable fuel support plates attached to said first beam member, the longitudinal axis of first beam member being perpendicular to the longitudinal axis of each of said fuel support plates, a first coupling means disposed along the length of the first beam member for permitting slidable fuel support plates parallel movement with respect to the longitudinal axis of said first beam member, a second coupling means located at one end of each of slidable fuel plates for slidably engaging first coupling means of first beam member, a second beam member connected to the other end of each of parallel-spaced slidable fuel support plates and providing an extension, second beam member being provided with a third coupling means disposed along the length of second beam member at one end thereof; and a plurality of fuel pins provided with a fourth coupling means located at one end of each fuel pin for slidably engaging third coupling means of second beam member to permit each fuel pin parallel movement with respect to the longitudinal axis of second beam member. (U.S.)

Nuclear fuel elements

International Nuclear Information System (INIS)

Nakai, Keiichi

1983-01-01

Purpose: To decrease the tensile stresses resulted in a fuel can as well as prevent decladding of fuel pellets into the bore holes by decreasing the inner pressure within the nuclear fuel element. Constitution: A fuel can is filled with hollow fuel pellets, inserted with a spring for retaining the hollow fuel pellets with an appropriate force and, thereafter, closely sealed at the both ends with end plugs. A cylindrical body is disposed into the bore holes of the hollow fuel pellets. Since initial sealing gases and/or gaseous nuclear fission products can thus be excluded from the bore holes where the temperature is at the highest level, the inner pressure of the nuclear fuel element can be reduced to decrease the tensile strength resulted to the fuel can. Furthermore, decladding of fuel pellets into the bore holes can be prevented. (Moriyama, K.)

Facilities of fuel transfer for nuclear reactors

International Nuclear Information System (INIS)

Wade, E.E.

1977-01-01

This invention relates to sodium cooled fast breeder reactors. It particularly concerns facilities for the transfer of fuel assemblies between the reactor core and a fuel transfer area. The installation is simple in construction and enables a relatively small vessel to be used. In greater detail, the invention includes a vessel with a head, fuel assemblies housed in this vessel, and an inlet and outlet for the coolant covering these fuel assemblies. The reactor has a fuel transfer area in communication with this vessel and gear inside the vessel for the transfer of these fuel assemblies. These facilities are borne by the vessel head and serve to transfer the fuel assemblies from the vessel to the transfer area; whilst leaving the fuel assemblies completely immersed in a continuous mass of coolant. A passageway is provided between the vessel and this transfer area for the fuel assemblies. Facilities are provided for closing off this passageway so that the inside of the reactor vessel may be isolated as desired from this fuel transfer area whilst the reactor is operating [fr

Endovascular treatment of head and neck arteriovenous malformations

Energy Technology Data Exchange (ETDEWEB)

Dmytriw, A.A. [University Health Network, Joint Department of Medical Imaging, Toronto, Ontario (Canada); Ter Brugge, K.G.; Krings, T.; Agid, R. [Toronto Western Hospital, Division of Neuroradiology, Department of Medical Imaging, Toronto, Ontario (Canada)

2014-03-15

Head and neck arteriovenous malformations (H and N AVM) are associated with considerable clinical and psychosocial burden and present a significant treatment challenge. We evaluated the presentation, response to treatment, and outcome of patients with H and N AVMs treated by endovascular means at our institution. Patients with H and N AVMs treated by endovascular means from 1984 to 2012 were evaluated retrospectively. These included AVMs involving the scalp, orbit, maxillofacial, and upper neck localizations. Patient's clinical files, radiological images, catheter angiograms, and surgical reports were reviewed. Eighty-nine patients with H and N AVMs (46 females, 43 males; 48 small, 41 large) received endovascular therapy. The goals of treatment were curative (n = 30), palliative (n = 34), or presurgical (n = 25). The total number of endovascular treatment sessions was 244 (average of 1.5 per patient). The goal of treatment was met in 92.1 % of cases. Eventual cure was achieved in 42 patients accounting for 58.4 % (52/89) of all patients who underwent treatment for any goal. Twenty-eight of these patients were cured by embolization alone (28/89, 31.4 %) of which 18 were single-hole AVFs. Twenty-four were cured by planned surgical excision after presurgical embolization (24/89, 27 %). Seven patients (7/89, 7.2 %) suffered transient and two (2/89, 2.2 %) permanent endovascular treatment complications. Endovascular treatment is effective for H and N AVMs and relatively safe. It is particularly effective for symptom palliation and presurgical aid. Embolization is curative mostly in small lesions and single-hole fistulas. In patients with large non-curable H and N AVMs, endovascular therapy is often the only palliative option. (orig.)

Fuels planning: science synthesis and integration; economic uses fact sheet 09: Mechanical treatment costs

Science.gov (United States)

Rocky Mountain Research Station USDA Forest Service

2005-01-01

Although fuel reduction treatments are widespread, there is great variability and uncertainty in the cost of conducting treatments. Researchers from the Rocky Mountain Research Station, USDA Forest Service, have developed a model for estimating the per-acre cost for mechanical fuel reduction treatments. Although these models do a good job of identifying factors that...

Closed Fuel Cycle Waste Treatment Strategy

Energy Technology Data Exchange (ETDEWEB)

Vienna, J. D. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Collins, E. D. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Crum, J. V. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Ebert, W. L. [Argonne National Lab. (ANL), Argonne, IL (United States); Frank, S. M. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Garn, T. G. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Gombert, D. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Jones, R. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Jubin, R. T. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Maio, V. C. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Marra, J. C. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Matyas, J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Nenoff, T. M. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Riley, B. J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Sevigny, G. J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Soelberg, N. R. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Strachan, D. M. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Thallapally, P. K. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Westsik, J. H. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

2015-02-01

This study is aimed at evaluating the existing waste management approaches for nuclear fuel cycle facilities in comparison to the objectives of implementing an advanced fuel cycle in the U.S. under current legal, regulatory, and logistical constructs. The study begins with the Global Nuclear Energy Partnership (GNEP) Integrated Waste Management Strategy (IWMS) (Gombert et al. 2008) as a general strategy and associated Waste Treatment Baseline Study (WTBS) (Gombert et al. 2007). The tenets of the IWMS are equally valid to the current waste management study. However, the flowsheet details have changed significantly from those considered under GNEP. In addition, significant additional waste management technology development has occurred since the GNEP waste management studies were performed. This study updates the information found in the WTBS, summarizes the results of more recent technology development efforts, and describes waste management approaches as they apply to a representative full recycle reprocessing flowsheet. Many of the waste management technologies discussed also apply to other potential flowsheets that involve reprocessing. These applications are occasionally discussed where the data are more readily available. The report summarizes the waste arising from aqueous reprocessing of a typical light-water reactor (LWR) fuel to separate actinides for use in fabricating metal sodium fast reactor (SFR) fuel and from electrochemical reprocessing of the metal SFR fuel to separate actinides for recycle back into the SFR in the form of metal fuel. The primary streams considered and the recommended waste forms include; Tritium in low-water cement in high integrity containers (HICs); Iodine-129: As a reference case, a glass composite material (GCM) formed by the encapsulation of the silver Mordenite (AgZ) getter material in a low-temperature glass is assumed. A number of alternatives with distinct advantages are also considered including a fused silica waste form